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Sample records for documentation program code

  1. Application programming interface document for the modernized Transient Reactor Analysis Code (TRAC-M)

    International Nuclear Information System (INIS)

    Mahaffy, J.; Boyack, B.E.; Steinke, R.G.

    1998-05-01

    The objective of this document is to ease the task of adding new system components to the Transient Reactor Analysis Code (TRAC) or altering old ones. Sufficient information is provided to permit replacement or modification of physical models and correlations. Within TRAC, information is passed at two levels. At the upper level, information is passed by system-wide and component-specific data modules at and above the level of component subroutines. At the lower level, information is passed through a combination of module-based data structures and argument lists. This document describes the basic mechanics involved in the flow of information within the code. The discussion of interfaces in the body of this document has been kept to a general level to highlight key considerations. The appendices cover instructions for obtaining a detailed list of variables used to communicate in each subprogram, definitions and locations of key variables, and proposed improvements to intercomponent interfaces that are not available in the first level of code modernization

  2. Code requirements document: MODFLOW 2.1: A program for predicting moderator flow patterns

    International Nuclear Information System (INIS)

    Peterson, P.F.

    1992-03-01

    Sudden changes in the temperature of flowing liquids can result in transient buoyancy forces which strongly impact the flow hydrodynamics via flow stratification. These effects have been studied for the case of potential flow of stratified liquids to line sinks, but not for moderator flow in SRS reactors. Standard codes, such as TRAC and COMMIX, do not have the capability to capture the stratification effect, due to strong numerical diffusion which smears away the hot/cold fluid interface. A related problem with standard codes is the inability to track plumes injected into the liquid flow, again due to numerical diffusion. The combined effects of buoyant stratification and plume dispersion have been identified as being important in operation of the Supplementary Safety System which injects neutron-poison ink into SRS reactors to provide safe shutdown in the event of safety rod failure. The MODFLOW code discussed here provides transient moderator flow pattern information with stratification effects, and tracks the location of ink plumes in the reactor. The code, written in Fortran, is compiled for Macintosh II computers, and includes subroutines for interactive control and graphical output. Removing the graphics capabilities, the code can also be compiled on other computers. With graphics, in addition to the capability to perform safety related computations, MODFLOW also provides an easy tool for becoming familiar with flow distributions in SRS reactors

  3. Document image retrieval through word shape coding.

    Science.gov (United States)

    Lu, Shijian; Li, Linlin; Tan, Chew Lim

    2008-11-01

    This paper presents a document retrieval technique that is capable of searching document images without OCR (optical character recognition). The proposed technique retrieves document images by a new word shape coding scheme, which captures the document content through annotating each word image by a word shape code. In particular, we annotate word images by using a set of topological shape features including character ascenders/descenders, character holes, and character water reservoirs. With the annotated word shape codes, document images can be retrieved by either query keywords or a query document image. Experimental results show that the proposed document image retrieval technique is fast, efficient, and tolerant to various types of document degradation.

  4. Toward Documentation of Program Evolution

    DEFF Research Database (Denmark)

    Vestdam, Thomas; Nørmark, Kurt

    2005-01-01

    The documentation of a program often falls behind the evolution of the program source files. When this happens it may be attractive to shift the documentation mode from updating the documentation to documenting the evolution of the program. This paper describes tools that support the documentatio....... It is concluded that our approach can help revitalize older documentation, and that discovery of the fine grained program evolution steps help the programmer in documenting the evolution of the program....

  5. Program EPICSHOW. A computer code to allow interactive viewing of the EPIC data libraries (Version 98-1). Summary documentation

    International Nuclear Information System (INIS)

    Pronyaev, V.G.; McLaughlin, P.K.

    1999-01-01

    EPICSHOW (Electron Photon Interactive Code - Show Data) is an interactive graphics code that allows users to view and interact with neutron, photon, electron and light charged particle data. Besides on screen graphics the code provides hard copy in the form of tabulated listings and Postscript output files. The code has been implemented on UNIX, IBM-PC, Power MAC, and even Laptop computers. It should be relatively easy to use it on almost any computer. All of the data included in this system is based on the Lawrence Livermore National Laboratory Databases and the neutron and photon data is used in the TART97 Monte Carlo transport code system. (author)

  6. MINET [momentum integral network] code documentation

    International Nuclear Information System (INIS)

    Van Tuyle, G.J.; Nepsee, T.C.; Guppy, J.G.

    1989-12-01

    The MINET computer code, developed for the transient analysis of fluid flow and heat transfer, is documented in this four-part reference. In Part 1, the MINET models, which are based on a momentum integral network method, are described. The various aspects of utilizing the MINET code are discussed in Part 2, The User's Manual. The third part is a code description, detailing the basic code structure and the various subroutines and functions that make up MINET. In Part 4, example input decks, as well as recent validation studies and applications of MINET are summarized. 32 refs., 36 figs., 47 tabs

  7. Review of SKB's Code Documentation and Testing

    International Nuclear Information System (INIS)

    Hicks, T.W.

    2005-01-01

    SKB is in the process of developing the SR-Can safety assessment for a KBS 3 repository. The assessment will be based on quantitative analyses using a range of computational codes aimed at developing an understanding of how the repository system will evolve. Clear and comprehensive code documentation and testing will engender confidence in the results of the safety assessment calculations. This report presents the results of a review undertaken on behalf of SKI aimed at providing an understanding of how codes used in the SR 97 safety assessment and those planned for use in the SR-Can safety assessment have been documented and tested. Having identified the codes us ed by SKB, several codes were selected for review. Consideration was given to codes used directly in SKB's safety assessment calculations as well as to some of the less visible codes that are important in quantifying the different repository barrier safety functions. SKB's documentation and testing of the following codes were reviewed: COMP23 - a near-field radionuclide transport model developed by SKB for use in safety assessment calculations. FARF31 - a far-field radionuclide transport model developed by SKB for use in safety assessment calculations. PROPER - SKB's harness for executing probabilistic radionuclide transport calculations using COMP23 and FARF31. The integrated analytical radionuclide transport model that SKB has developed to run in parallel with COMP23 and FARF31. CONNECTFLOW - a discrete fracture network model/continuum model developed by Serco Assurance (based on the coupling of NAMMU and NAPSAC), which SKB is using to combine hydrogeological modelling on the site and regional scales in place of the HYDRASTAR code. DarcyTools - a discrete fracture network model coupled to a continuum model, recently developed by SKB for hydrogeological modelling, also in place of HYDRASTAR. ABAQUS - a finite element material model developed by ABAQUS, Inc, which is used by SKB to model repository buffer

  8. Codes and standards and other guidance cited in regulatory documents

    International Nuclear Information System (INIS)

    Nickolaus, J.R.; Bohlander, K.L.

    1996-08-01

    As part of the U.S. Nuclear Regulatory Commission (NRC) Standard Review Plan Update and Development Program (SRP-UDP), Pacific Northwest National Laboratory developed a listing of industry consensus codes and standards and other government and industry guidance referred to in regulatory documents. The SRP-UDP has been completed and the SRP-Maintenance Program (SRP-MP) is now maintaining this listing. Besides updating previous information, Revision 3 adds approximately 80 citations. This listing identifies the version of the code or standard cited in the regulatory document, the regulatory document, and the current version of the code or standard. It also provides a summary characterization of the nature of the citation. This listing was developed from electronic searches of the Code of Federal Regulations and the NRC's Bulletins, Information Notices, Circulars, Enforcement Manual, Generic Letters, Inspection Manual, Policy Statements, Regulatory Guides, Standard Technical Specifications and the Standard Review Plan (NUREG-0800)

  9. Codes and standards and other guidance cited in regulatory documents

    Energy Technology Data Exchange (ETDEWEB)

    Nickolaus, J.R.; Bohlander, K.L.

    1996-08-01

    As part of the U.S. Nuclear Regulatory Commission (NRC) Standard Review Plan Update and Development Program (SRP-UDP), Pacific Northwest National Laboratory developed a listing of industry consensus codes and standards and other government and industry guidance referred to in regulatory documents. The SRP-UDP has been completed and the SRP-Maintenance Program (SRP-MP) is now maintaining this listing. Besides updating previous information, Revision 3 adds approximately 80 citations. This listing identifies the version of the code or standard cited in the regulatory document, the regulatory document, and the current version of the code or standard. It also provides a summary characterization of the nature of the citation. This listing was developed from electronic searches of the Code of Federal Regulations and the NRC`s Bulletins, Information Notices, Circulars, Enforcement Manual, Generic Letters, Inspection Manual, Policy Statements, Regulatory Guides, Standard Technical Specifications and the Standard Review Plan (NUREG-0800).

  10. Note related to the elaboration of a coding by key sentences for the programming of a document automatic selection system

    International Nuclear Information System (INIS)

    Leroy, A.; Braffort, P.

    1959-01-01

    This note deals with the providing of CEA documentalists with a tool for coding studies. The authors first discuss issues related to code selection criteria (author classification, topic classification, and so on), and propose an overview and a discussion of linguistic models. They also comment how diagrams illustrating relationships between words are built up, and propose a diagram representation example which includes different concepts such as conditions, properties, object, tools or processes (for example hardness for a steel, batch processing for a condition, or sintering for a process), and also the introduction of negation. Then, the authors address how basic concepts can be highlighted, describe how key sentences can be built up, and propose an example analysis in the case of a published article dealing with nuclear reactors (in this case, the study of a liquid-metal neutron absorber for the control of a gas-cooled power reactor). Perspectives of evolution are finally discussed

  11. Scheme Program Documentation Tools

    DEFF Research Database (Denmark)

    Nørmark, Kurt

    2004-01-01

    are separate and intended for different documentation purposes they are related to each other in several ways. Both tools are based on XML languages for tool setup and for documentation authoring. In addition, both tools rely on the LAML framework which---in a systematic way---makes an XML language available...... as named functions in Scheme. Finally, the Scheme Elucidator is able to integrate SchemeDoc resources as part of an internal documentation resource....

  12. Documentation of Concurrent programs.

    Science.gov (United States)

    1983-07-01

    preparing the documentation formats, and Tom McDonald for preparing the supplemental materials and statistical analyses. 16 [ 1 -16- I j REFERENCES I Boehm...34*h (eeeeeotop to enter h, to IAmlOCSot land ,uoMXM to R&’T- kfC ’Cod At 1*1 ,lgo: 0) 4 O ~ en ttR .I SA’ tgOhegl that ’t to 40n. .hi &ren a ~ O toll s

  13. Interim report for documentation of computer programs for crude oil profile analysis. [Codes, CV, CRULE, CPR, CIMPACT, ENT ADJ, REF VOLS, CIMP PRT, C MODEL, C PRINT

    Energy Technology Data Exchange (ETDEWEB)

    This report is summarizing the findings and documenting the programs developed by Economic Regulatory Administration (ERA) for the Crude Oil Profile Analysis. Based on a variety of estimates and assumptions from different sources, ERA developed a series of computer programs which generate a 24-month projection of the crude oil production in each of the price categories. AVANTE International Systems Corporation is contracted to provide an organized documentation for all of these data base, assumptions, estimation rationale and computing procedures.

  14. Final technical position on documentation of computer codes for high-level waste management

    International Nuclear Information System (INIS)

    Silling, S.A.

    1983-06-01

    Guidance is given for the content of documentation of computer codes which are used in support of a license application for high-level waste disposal. The guidelines cover theoretical basis, programming, and instructions for use of the code

  15. BASIC Instructional Program: System Documentation.

    Science.gov (United States)

    Dageforde, Mary L.

    This report documents the BASIC Instructional Program (BIP), a "hands-on laboratory" that teaches elementary programming in the BASIC language, as implemented in the MAINSAIL language, a machine-independent revision of SAIL which should facilitate implementation of BIP on other computing systems. Eight instructional modules which make up…

  16. 1995 building energy codes and standards workshops: Summary and documentation

    Energy Technology Data Exchange (ETDEWEB)

    Sandahl, L.J.; Shankle, D.L.

    1996-02-01

    During the spring of 1995, Pacific Northwest National Laboratory (PNNL) conducted four two-day Regional Building Energy Codes and Standards workshops across the US. Workshops were held in Chicago, Denver, Rhode Island, and Atlanta. The workshops were designed to benefit state-level officials including staff of building code commissions, energy offices, public utility commissions, and others involved with adopting/updating, implementing, and enforcing building energy codes in their states. The workshops provided an opportunity for state and other officials to learn more about residential and commercial building energy codes and standards, the role of the US Department of Energy and the Building Standards and Guidelines Program at Pacific Northwest National Laboratory, Home Energy Rating Systems (HERS), Energy Efficient Mortgages (EEM), training issues, and other topics related to the development, adoption, implementation, and enforcement of building energy codes. Participants heard success stories, got tips on enforcement training, and received technical support materials. In addition to receiving information on the above topics, workshop participants had an opportunity to provide input on code adoption issues, building industry training issues, building design issues, and exemplary programs across the US. This paper documents the workshop planning, findings, and follow-up processes.

  17. Nevada Administrative Code for Special Education Programs.

    Science.gov (United States)

    Nevada State Dept. of Education, Carson City. Special Education Branch.

    This document presents excerpts from Chapter 388 of the Nevada Administrative Code, which concerns definitions, eligibility, and programs for students who are disabled or gifted/talented. The first section gathers together 36 relevant definitions from the Code for such concepts as "adaptive behavior,""autism,""gifted and…

  18. Documentation of the heat conduction code TRANCO

    International Nuclear Information System (INIS)

    Callahan, G.D.

    1975-01-01

    A transient heat conduction code used for thermal, thermoelastic, thermoelastic/plastic, and thermo/viscoelastic analyses is presented. The code can solve two-dimensional X-Y and axially symmetric R-theta-z thermal problems with the following conditions: constant temperature, constant flux, convective, or adiabatic boundary conditions; time-dependent or constant internal heat generation; and anisotropic thermal conductivities

  19. PSP Program close out documentation

    Energy Technology Data Exchange (ETDEWEB)

    Andringa, K.; Hootman, H.E.; Ferrara, A.S.; Smith, P.K.; Congdon, J.W.; Randolph, H.W.; Young, R.H.; Driggers, F.E.; Topp, S.V.

    1985-12-31

    In December 1982 DOE-SR directed SRL to study the feasibility and impact of a program to lower the U-236 content of the Highly Enriched Uranium (HEU) stockpile used as fuel for the SRP reactors. In response to this request SRL assessed four technologies, Atomic Vapor Laser Isotope Separation (AVLIS), Molecular Laser Isotope Separation (MLIS), Gas Centrifuge, and the Plasma Separation Process (PSP) for this purpose with the assistance of the Engineering Department. In April 1983 cost/benefit analyses for these processes, high spot cost estimates for production facilities, and process uncertainties were submitted to DOE-SR with a recommendation to proceed with the conceptual design and supporting development programs for a facility based on the use of the PSP process. The current program status for the PSP development program at SRL and the design and documentation of a production facility at SRP, referred to as the Fuel Improvement Demonstration Facility (FIDF), is described in this report.

  20. Documentation and verification of the SHAFT code

    International Nuclear Information System (INIS)

    St John, C.M.

    1991-12-01

    The SHAFT code incorporates equations to compute stresses in a shaft liner when the rock through which a shaft passes is subject to known three-dimensional states of stress or strain. The deformation modes considered are hoop deformation, axial deformation, and shear on a plane normal to the shaft axis. Interaction between the liner and the soil and rock is considered, and it is assumed that the liner is in place before loading is applied. This code is intended to be used interactively but creates a permanent record complete with necessary quality assurance information. The code has been carefully verified for the case of generalized plane strain, in which an arbitrary axial strain can be defined. It may also be used for plane stress analysis. Output is given in the form of stresses at selected sample points in the linear and the rock and a simple graphical representation of the distribution of stress through the liner. 12 figs., 13 tabs

  1. City Reach Code Technical Support Document

    Energy Technology Data Exchange (ETDEWEB)

    Athalye, Rahul A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Chen, Yan [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Zhang, Jian [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Liu, Bing [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Frankel, Mark [New Buildings Inst., Portland, OR (United States); Lyles, Mark [New Buildings Inst., Portland, OR (United States)

    2017-10-31

    This report describes and analyzes a set of energy efficiency measures that will save 20% energy over ASHRAE Standard 90.1-2013. The measures will be used to formulate a Reach Code for cities aiming to go beyond national model energy codes. A coalition of U.S. cities together with other stakeholders wanted to facilitate the development of voluntary guidelines and standards that can be implemented in stages at the city level to improve building energy efficiency. The coalition's efforts are being supported by the U.S. Department of Energy via Pacific Northwest National Laboratory (PNNL) and in collaboration with the New Buildings Institute.

  2. Fossil energy program. Summary document

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-05-01

    This program summary document presents a comprehensive overview of the research, development, and demonstration (RD and D) activities that will be performed in FY 1981 by the Assistant Secretary for Fossil Energy (ASFE), US Department of Energy (DOE). The ASFE technology programs for the fossil resources of coal, petroleum (including oil shale) and gas have been established with the goal of making substantive contributions to the nation's future supply and efficienty use of energy. On April 29, 1977, the Administration submitted to Congress the National Energy Plan (NEP) and accompanying legislative proposals designed to establish a coherent energy policy structure for the United States. Congress passed the National Energy Act (NEA) on October 15, 1978, which allows implementation of the vital parts of the NEP. The NEP was supplemented by additional energy policy statements culminating in the President's address on July 15, 1979, presenting a program to further reduce dependence on imported petroleum. The passage of the NEA-related energy programs represent specific steps by the Administration and Congress to reorganize, redirect, and clarify the role of the Federal Government in the formulation and execution of national energy policy and programs. The energy technology RD and D prog4rams carried out by ASFE are an important part of the Federal Government's effort to provide the combination and amounts of energy resources needed to ensure national security and continued economic growth.

  3. Software Design Document for the AMP Nuclear Fuel Performance Code

    International Nuclear Information System (INIS)

    Philip, Bobby; Clarno, Kevin T.; Cochran, Bill

    2010-01-01

    The purpose of this document is to describe the design of the AMP nuclear fuel performance code. It provides an overview of the decomposition into separable components, an overview of what those components will do, and the strategic basis for the design. The primary components of a computational physics code include a user interface, physics packages, material properties, mathematics solvers, and computational infrastructure. Some capability from established off-the-shelf (OTS) packages will be leveraged in the development of AMP, but the primary physics components will be entirely new. The material properties required by these physics operators include many highly non-linear properties, which will be replicated from FRAPCON and LIFE where applicable, as well as some computationally-intensive operations, such as gap conductance, which depends upon the plenum pressure. Because there is extensive capability in off-the-shelf leadership class computational solvers, AMP will leverage the Trilinos, PETSc, and SUNDIALS packages. The computational infrastructure includes a build system, mesh database, and other building blocks of a computational physics package. The user interface will be developed through a collaborative effort with the Nuclear Energy Advanced Modeling and Simulation (NEAMS) Capability Transfer program element as much as possible and will be discussed in detail in a future document.

  4. The Vicinity of Program Documentation Tools

    DEFF Research Database (Denmark)

    Nørmark, Kurt

    between program development tools.  In the central part of the paper we introduce a mapping of documentation flow between program development tools.  In addition we discuss a set of locally developed tools which is related to program documentation.  The use of test cases as examples in an interface......Program documentation plays a vital role in almost all programming processes.  Program documentation flows between separate tools of a modularized environment, and in between the components of an integrated development environment as well.  In this paper we discuss the flow of program documentation...... documentation tool is a noteworthy and valuable contribution to the documentation flow.  As an additional contribution we identify several circular relationships which illustrate feedback of documentation to the program editor from other tools in the development environment....

  5. Instruction in Documentation for Computer Programming

    Science.gov (United States)

    Westley, John W.

    1976-01-01

    In addition to the input/output record format, the program flowchart, the program listing, and the program test output, eight documentation items are suggested in order that they may serve as a base from which to start teaching program documentation. (Author/AG)

  6. Magnetic fusion program summary document

    International Nuclear Information System (INIS)

    1979-04-01

    This document outlines the current and planned research, development, and commercialization (RD and C) activities of the Offic of Fusion Energy under the Assistant Secretary for Energy Technology, US Department of Energy (DOE). The purpose of this document is to explain the Office of Fusion Energy's activities to Congress and its committees and to interested members of the public

  7. Health physics source document for codes of practice

    International Nuclear Information System (INIS)

    Pearson, G.W.; Meggitt, G.C.

    1989-05-01

    Personnel preparing codes of practice often require basic Health Physics information or advice relating to radiological protection problems and this document is written primarily to supply such information. Certain technical terms used in the text are explained in the extensive glossary. Due to the pace of change in the field of radiological protection it is difficult to produce an up-to-date document. This document was compiled during 1988 however, and therefore contains the principle changes brought about by the introduction of the Ionising Radiations Regulations (1985). The paper covers the nature of ionising radiation, its biological effects and the principles of control. It is hoped that the document will provide a useful source of information for both codes of practice and wider areas and stimulate readers to study radiological protection issues in greater depth. (author)

  8. Software requirements specification document for the AREST code development

    International Nuclear Information System (INIS)

    Engel, D.W.; McGrail, B.P.; Whitney, P.D.; Gray, W.J.; Williford, R.E.; White, M.D.; Eslinger, P.W.; Altenhofen, M.K.

    1993-11-01

    The Analysis of the Repository Source Term (AREST) computer code was selected in 1992 by the U.S. Department of Energy. The AREST code will be used to analyze the performance of an underground high level nuclear waste repository. The AREST code is being modified by the Pacific Northwest Laboratory (PNL) in order to evaluate the engineered barrier and waste package designs, model regulatory compliance, analyze sensitivities, and support total systems performance assessment modeling. The current version of the AREST code was developed to be a very useful tool for analyzing model uncertainties and sensitivities to input parameters. The code has also been used successfully in supplying source-terms that were used in a total systems performance assessment. The current version, however, has been found to be inadequate for the comparison and selection of a design for the waste package. This is due to the assumptions and simplifications made in the selection of the process and system models. Thus, the new version of the AREST code will be designed to focus on the details of the individual processes and implementation of more realistic models. This document describes the requirements of the new models that will be implemented. Included in this document is a section describing the near-field environmental conditions for this waste package modeling, description of the new process models that will be implemented, and a description of the computer requirements for the new version of the AREST code

  9. Precise documentation of well-structured programs

    Energy Technology Data Exchange (ETDEWEB)

    Parnas, D.L.; Madey, J.; Iglewski, M. [McMaster Univ., Hamilton, Ontario (Canada)

    1997-11-01

    This paper describes a new form of program documentation that is precise, systematic and readable. This documentation comprises a set of displays supplemented by a lexicon and an index. Each display presents a program fragment in such a way that its correctness can be examined without looking at any other display. Each display has three parts: (1) the specification of the program presented in the display, (2) the program itself, and (3) the specifications of programs invoked by this program. The displays are intended to be used by Software Engineers as a reference document during inspection and maintenance. This paper also introduces a specification technique that is a refinement of Mills functional approach to program documentation and verification; programs are specified and described in tabular form.

  10. Defense Transuranic Waste Program Strategy Document

    International Nuclear Information System (INIS)

    1984-01-01

    The Defense Transuranic Waste Program (DTWP) Strategy Document presents the general strategy for managing transuranic (TRU) waste materials generated during defense and research activities regulated by the US Department of Energy. The Strategy Document includes discussion of objectives and activities relating to the entire Defense Transuranic Waste Program. However, the primary focus is on the specific management responsibilities of the Transuranic Waste Lead Organization (TLO). The document also includes an updated summary of progress on TLO-managed activities over the past year

  11. Technical Basis Document for PFP Area Monitoring Dosimetry Program

    CERN Document Server

    Cooper, J R

    2000-01-01

    This document describes the phantom dosimetry used for the PFP Area Monitoring program and establishes the basis for the Plutonium Finishing Plant's (PFP) area monitoring dosimetry program in accordance with the following requirements: Title 10, Code of Federal Regulations (CFR), part 835, ''Occupational Radiation Protection'' Part 835.403; Hanford Site Radiological Control Manual (HSRCM-1), Part 514; HNF-PRO-382, Area Dosimetry Program; and PNL-MA-842, Hanford External Dosimetry Technical Basis Manual.

  12. Technical Basis Document for PFP Area Monitoring Dosimetry Program

    International Nuclear Information System (INIS)

    COOPER, J.R.

    2000-01-01

    This document describes the phantom dosimetry used for the PFP Area Monitoring program and establishes the basis for the Plutonium Finishing Plant's (PFP) area monitoring dosimetry program in accordance with the following requirements: Title 10, Code of Federal Regulations (CFR), part 835, ''Occupational Radiation Protection'' Part 835.403; Hanford Site Radiological Control Manual (HSRCM-1), Part 514; HNF-PRO-382, Area Dosimetry Program; and PNL-MA-842, Hanford External Dosimetry Technical Basis Manual

  13. Codes and standards and other guidance cited in regulatory documents. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Ankrum, A.; Nickolaus, J.; Vinther, R.; Maguire-Moffitt, N.; Hammer, J.; Sherfey, L.; Warner, R. [Pacific Northwest Lab., Richland, WA (United States)

    1994-08-01

    As part of the US Nuclear Regulatory Commission (NRC) Standard Review Plan Update and Development Program, Pacific Northwest Laboratory developed a listing of industry consensus codes and standards and other government and industry guidance referred to in regulatory documents. In addition to updating previous information, Revision 1 adds citations from the NRC Inspection Manual and the Improved Standard Technical Specifications. This listing identifies the version of the code or standard cited in the regulatory document, the regulatory document, and the current version of the code or standard. It also provides a summary characterization of the nature of the citation. This listing was developed from electronic searches of the Code of Federal Regulations and the NRC`s Bulletins, Information Notices, Circulars, Generic Letters, Policy Statements, Regulatory Guides, and the Standard Review Plan (NUREG-0800).

  14. Codes and standards and other guidance cited in regulatory documents. Revision 1

    International Nuclear Information System (INIS)

    Ankrum, A.; Nickolaus, J.; Vinther, R.; Maguire-Moffitt, N.; Hammer, J.; Sherfey, L.; Warner, R.

    1994-08-01

    As part of the US Nuclear Regulatory Commission (NRC) Standard Review Plan Update and Development Program, Pacific Northwest Laboratory developed a listing of industry consensus codes and standards and other government and industry guidance referred to in regulatory documents. In addition to updating previous information, Revision 1 adds citations from the NRC Inspection Manual and the Improved Standard Technical Specifications. This listing identifies the version of the code or standard cited in the regulatory document, the regulatory document, and the current version of the code or standard. It also provides a summary characterization of the nature of the citation. This listing was developed from electronic searches of the Code of Federal Regulations and the NRC's Bulletins, Information Notices, Circulars, Generic Letters, Policy Statements, Regulatory Guides, and the Standard Review Plan (NUREG-0800)

  15. 2D arc-PIC code description: methods and documentation

    CERN Document Server

    Timko, Helga

    2011-01-01

    Vacuum discharges are one of the main limiting factors for future linear collider designs such as that of the Compact LInear Collider. To optimize machine efficiency, maintaining the highest feasible accelerating gradient below a certain breakdown rate is desirable; understanding breakdowns can therefore help us to achieve this goal. As a part of ongoing theoretical research on vacuum discharges at the Helsinki Institute of Physics, the build-up of plasma can be investigated through the particle-in-cell method. For this purpose, we have developed the 2D Arc-PIC code introduced here. We present an exhaustive description of the 2D Arc-PIC code in two parts. In the first part, we introduce the particle-in-cell method in general and detail the techniques used in the code. In the second part, we provide a documentation and derivation of the key equations occurring in the code. The code is original work of the author, written in 2010, and is therefore under the copyright of the author. The development of the code h...

  16. Software documentation for TRU certification program

    International Nuclear Information System (INIS)

    CLINTON, R.

    1999-01-01

    The document provides validation information for software used to support TRU operational activities. Calculations were performed using a spreadsheet application. This document provides information about the usage of the software application, Microsoft(reg s ign) Excel. Microsoft(reg s ign) Excel spreadsheets were used to perform specific calculations to determine the amount of containers to visually examine and to perform analyses on container head-gas data. Contained in this document are definitions of formulas and variables with relation to the Excel codes used. Also, a demonstration is provided using predetermined values to obtain predetermined results

  17. Documentation for TRACE: an interactive beam-transport code

    International Nuclear Information System (INIS)

    Crandall, K.R.; Rusthoi, D.P.

    1985-01-01

    TRACE is an interactive, first-order, beam-dynamics computer program. TRACE includes space-charge forces and mathematical models for a number of beamline elements not commonly found in beam-transport codes, such as permanent-magnet quadrupoles, rf quadrupoles, rf gaps, accelerator columns, and accelerator tanks. TRACE provides an immediate graphic display of calculative results, has a powerful and easy-to-use command procedure, includes eight different types of beam-matching or -fitting capabilities, and contains its own internal HELP package. This report describes the models and equations used for each of the transport elements, the fitting procedures, and the space-charge/emittance calculations, and provides detailed instruction for using the code

  18. Technical Basis Document for PFP Area Monitoring Dosimetry Program

    Energy Technology Data Exchange (ETDEWEB)

    COOPER, J.R.

    2000-04-17

    This document describes the phantom dosimetry used for the PFP Area Monitoring program and establishes the basis for the Plutonium Finishing Plant's (PFP) area monitoring dosimetry program in accordance with the following requirements: Title 10, Code of Federal Regulations (CFR), part 835, ''Occupational Radiation Protection'' Part 835.403; Hanford Site Radiological Control Manual (HSRCM-1), Part 514; HNF-PRO-382, Area Dosimetry Program; and PNL-MA-842, Hanford External Dosimetry Technical Basis Manual.

  19. Code quality issues in student programs

    NARCIS (Netherlands)

    Keuning, H.W.; Heeren, B.J.; Jeuring, J.T.

    2017-01-01

    Because low quality code can cause serious problems in software systems, students learning to program should pay attention to code quality early. Although many studies have investigated mistakes that students make during programming, we do not know much about the quality of their code. This study

  20. Standards for maintenance documentation of COSMOS programs

    International Nuclear Information System (INIS)

    Burstall, R.F.; Rickets, T.M.; Butland, A.T.D.

    1982-06-01

    The Compatible Open Shop Modular Operating Scheme (COSMOS) is used for fast reactor neutronics and subassembly distortion calculations in the UK. It provides database and databank facilities for this purpose. A large number of applications programs use these facilities. This report sets down the standards agreed for use in the preparation of maintenance documents for these programs. These standards have been developed as the result of experience with earlier more complicated standards. Some of the terminology used in this report is particular to COSMOS, but the general features of the standard may be useful to those responsible for other computer programs. (author)

  1. Program information architecture/document hierarchy

    International Nuclear Information System (INIS)

    Woods, T.W.

    1991-09-01

    The Nuclear Waste Management System (NWMS) Management Systems Improvement Strategy (MSIS) (DOE 1990) requires that the information within the computer program and information management system be ordered into a precedence hierarchy for consistency. Therefore, the US Department of Energy (DOE). Office of Civilian Radioactive Waste Management (OCRWM) requested Westinghouse Hanford Company to develop a plan for NWMS program information which the MSIS calls a document hierarchy. This report provides the results of that effort and describes the management system as a ''program information architecture.'' 3 refs., 3 figs

  2. Documentation for grants equal to tax model: Volume 3, Source code

    International Nuclear Information System (INIS)

    Boryczka, M.K.

    1986-01-01

    The GETT model is capable of forecasting the amount of tax liability associated with all property owned and all activities undertaken by the US Department of Energy (DOE) in site characterization and repository development. The GETT program is a user-friendly, menu-driven model developed using dBASE III/trademark/, a relational data base management system. The data base for GETT consists primarily of eight separate dBASE III/trademark/ files corresponding to each of the eight taxes (real property, personal property, corporate income, franchise, sales, use, severance, and excise) levied by State and local jurisdictions on business property and activity. Additional smaller files help to control model inputs and reporting options. Volume 3 of the GETT model documentation is the source code. The code is arranged primarily by the eight tax types. Other code files include those for JURISDICTION, SIMULATION, VALIDATION, TAXES, CHANGES, REPORTS, GILOT, and GETT. The code has been verified through hand calculations

  3. Strategy and programs of the research on high-level and long-living radioactive wastes (by right of article L542 of the environment code from December 30, 1991 law). Conjuncture document

    International Nuclear Information System (INIS)

    2003-01-01

    This document gives, in a first part, a brief insight on the main results of the researches carried out in 2002 on the management of high-level and long-living radioactive wastes according to the three research ways defined by the December 30, 1991 law: separation-transmutation, disposal in deep geologic underground, wastes conditioning and storage. The second part of the document is an executive summary of the 2003 edition of the document 'strategy and programs of the researches on the management of high-level and long-living radioactive wastes - SPR 2003'. It presents the content of the different chapters: 1 - researches methodology and implementation of coordinated studies; 2 - researches status 10 years after the enforcement of the law; 3 - the main goals and steps to reach before the 2006 date-line; 4 - the description and analysis of the programs under consideration; 5 - the coordination between French programs; 6 - the international cooperation. (J.S.)

  4. Documentation of SPECTROM-55: A finite element thermohydrogeological analysis program

    International Nuclear Information System (INIS)

    Osnes, J.D.; Ratigan, J.L.; Loken, M.C.; Parrish, D.K.

    1985-12-01

    SPECTROM-55 is a finite element computer program developed by RE/SPEC Inc. for analyses of coupled heat and fluid transfer through fully saturated porous media. The theoretical basis for the mathematical model, the implementation of the mathematical model into the computer code, the verification and validation efforts with the computer code, and the code support and continuing documentation are described in this document. The program is especially suited for analyses of the regional hydrogeology in the vicinity of a heat-generating nuclear waste repository. These applications typically involve forced and free convection in a ground-water flow system. The program provides transient or steady-state temperatures, pressures, and fluid velocities resulting from the application of a variety of initial and boundary conditions to bodies with complicated shapes. The boundary conditions include constant heat and fluid fluxes, convective heat transfer, constant temperature, and constant pressure. Initial temperatures and pressures can be specified. Composite systems of anisotropic materials, such as geologic strata, can be defined in either planar or axisymmetric configurations. Constant or varying volumetric heat generation, such as decaying heat generation from radioactive waste, can be specified

  5. Programming Entity Framework Code First

    CERN Document Server

    Lerman, Julia

    2011-01-01

    Take advantage of the Code First data modeling approach in ADO.NET Entity Framework, and learn how to build and configure a model based on existing classes in your business domain. With this concise book, you'll work hands-on with examples to learn how Code First can create an in-memory model and database by default, and how you can exert more control over the model through further configuration. Code First provides an alternative to the database first and model first approaches to the Entity Data Model. Learn the benefits of defining your model with code, whether you're working with an exis

  6. Rotor Wake/Stator Interaction Noise Prediction Code Technical Documentation and User's Manual

    Science.gov (United States)

    Topol, David A.; Mathews, Douglas C.

    2010-01-01

    This report documents the improvements and enhancements made by Pratt & Whitney to two NASA programs which together will calculate noise from a rotor wake/stator interaction. The code is a combination of subroutines from two NASA programs with many new features added by Pratt & Whitney. To do a calculation V072 first uses a semi-empirical wake prediction to calculate the rotor wake characteristics at the stator leading edge. Results from the wake model are then automatically input into a rotor wake/stator interaction analytical noise prediction routine which calculates inlet aft sound power levels for the blade-passage-frequency tones and their harmonics, along with the complex radial mode amplitudes. The code allows for a noise calculation to be performed for a compressor rotor wake/stator interaction, a fan wake/FEGV interaction, or a fan wake/core stator interaction. This report is split into two parts, the first part discusses the technical documentation of the program as improved by Pratt & Whitney. The second part is a user's manual which describes how input files are created and how the code is run.

  7. Sequence Coding and Search System Backfit Quality Assurance Program Plan

    International Nuclear Information System (INIS)

    Lovell, C.J.; Stepina, P.L.

    1985-03-01

    The Sequence Coding and Search System is a computer-based encoding system for events described in Licensee Event Reports. This data system contains LERs from 1981 to present. Backfit of the data system to include LERs prior to 1981 is required. This report documents the Quality Assurance Program Plan that EG and G Idaho, Inc. will follow while encoding 1980 LERs

  8. Defense transuranic waste program strategy document

    International Nuclear Information System (INIS)

    1982-07-01

    This document summarizes the strategy for managing transuranic (TRU) wastes generated in defense and research activities regulated by the US Department of Energy. It supercedes a document issued in July 1980. In addition to showing how current strategies of the Defense Transuranic Waste Program (DTWP) are consistent with the national objective of isolating radioactive wastes from the biosphere, this document includes information about the activities of the Transuranic Lead Organization (TLO). To explain how the DTWP strategy is implemented, this document also discusses how the TLO coordinates and integrates the six separate elements of the DTWP: (1) Waste Generation Site Activities, (2) Storage Site Activities, (3) Burial Site Activities, (4) Technology Development, (5) Transportation Development, and (6) Permanent Disposal. Storage practices for TRU wastes do not pose short-term hazards to public health and safety or to the environment. Isolation of TRU wastes in a deep-mined geologic repository is considered the most promising of the waste disposal alternatives available. This assessment is supported by the DOE Record of Decision to proceed with research and development work at the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico - a deep-mined geologic research and development project. In support of the WIPP research project and the permanent disposal of TRU waste, the DTWP strategy for the near term will concentrate on completion of procedures and the design and construction of all facilities necessary to certify newly-generated (NG) and stored TRU wastes for emplacement in the WIPP. In addition, the strategy involves evaluating alternatives for disposing of some transuranic wastes by methods which may allow for on-site disposal of these wastes and yet preserve adequate margins of safety to protect public health and the environment

  9. Guidelines and procedures for the International Code Assessment and Applications Program

    International Nuclear Information System (INIS)

    1987-04-01

    This document presents the guidelines and procedures by which the International Code Assessment and Applications Program (ICAP) will be conducted. The document summarizes the management structure of the program and the relationships between and responsibilities of the United States Nuclear Regulatory Commission (USNRC) and the international participants. The procedures for code maintenance and necessary documentation are described. Guidelines for the performance and documentation of code assessment studies are presented. An overview of an effort to quantify code uncertainty, which the ICAP supports, is included

  10. Code-Switching in Judaeo-Arabic Documents from the Cairo Geniza

    Science.gov (United States)

    Wagner, Esther-Miriam; Connolly, Magdalen

    2018-01-01

    This paper investigates code-switching and script-switching in medieval documents from the Cairo Geniza, written in Judaeo-Arabic (Arabic in Hebrew script), Hebrew, Arabic and Aramaic. Legal documents regularly show a macaronic style of Judaeo-Arabic, Aramaic and Hebrew, while in letters code-switching from Judaeo-Arabic to Hebrew is tied in with…

  11. Code assessment and applications program

    International Nuclear Information System (INIS)

    Chapman, R.L.; Hanner, O.M. Jr.; Wells, M.E.

    1979-09-01

    This document presents the results of a review and evaluation of actual and potential water hammer events in both BWR and PWR power plants. Known or suspected water hammer events were reviewed and tabulated. Possible scenarios for potentially damaging water hammer occurrences in safety-related systems were developed. The effectiveness of subsystems and design features used to prevent water hammer and the potential for water hammer in certain systems due to various initiating mechanisms were also addressed. Specific recommendations on design, operational and testing criteria, and applicant/station operator requirements were made to prevent and avoid damaging water hammer in the design of future nuclear plants

  12. Generic programming for deterministic neutron transport codes

    International Nuclear Information System (INIS)

    Plagne, L.; Poncot, A.

    2005-01-01

    This paper discusses the implementation of neutron transport codes via generic programming techniques. Two different Boltzmann equation approximations have been implemented, namely the Sn and SPn methods. This implementation experiment shows that generic programming allows us to improve maintainability and readability of source codes with no performance penalties compared to classical approaches. In the present implementation, matrices and vectors as well as linear algebra algorithms are treated separately from the rest of source code and gathered in a tool library called 'Generic Linear Algebra Solver System' (GLASS). Such a code architecture, based on a linear algebra library, allows us to separate the three different scientific fields involved in transport codes design: numerical analysis, reactor physics and computer science. Our library handles matrices with optional storage policies and thus applies both to Sn code, where the matrix elements are computed on the fly, and to SPn code where stored matrices are used. Thus, using GLASS allows us to share a large fraction of source code between Sn and SPn implementations. Moreover, the GLASS high level of abstraction allows the writing of numerical algorithms in a form which is very close to their textbook descriptions. Hence the GLASS algorithms collection, disconnected from computer science considerations (e.g. storage policy), is very easy to read, to maintain and to extend. (authors)

  13. UNSAT-H, an unsaturated soil water flow code for use at the Hanford site: code documentation

    International Nuclear Information System (INIS)

    Fayer, M.J.; Gee, G.W.

    1985-10-01

    The unsaturated soil moisture flow code, UNSAT-H, which was developed at Pacific Northwest Laboratory for assessing water movement at waste sites on the Hanford site, is documented in this report. This code is used in simulating the water dynamics of arid sites under consideration for waste disposal. The results of an example simulation of constant infiltration show excellent agreement with an analytical solution and another numerical solution, thus providing some verification of the UNSAT-H code. Areas of the code are identified for future work and include runoff, snowmelt, long-term climate and plant models, and parameter measurement. 29 refs., 7 figs., 2 tabs

  14. Argonne Code Center: compilation of program abstracts

    Energy Technology Data Exchange (ETDEWEB)

    Butler, M.K.; DeBruler, M.; Edwards, H.S.; Harrison, C. Jr.; Hughes, C.E.; Jorgensen, R.; Legan, M.; Menozzi, T.; Ranzini, L.; Strecok, A.J.

    1977-08-01

    This publication is the eleventh supplement to, and revision of, ANL-7411. It contains additional abstracts and revisions to some earlier abstracts and other pages. Sections of the complete document ANL-7411 are as follows: preface, history and acknowledgements, abstract format, recommended program package contents, program classification guide and thesaurus, and the abstract collection. (RWR)

  15. Argonne Code Center: compilation of program abstracts

    Energy Technology Data Exchange (ETDEWEB)

    Butler, M.K.; DeBruler, M.; Edwards, H.S.

    1976-08-01

    This publication is the tenth supplement to, and revision of, ANL-7411. It contains additional abstracts and revisions to some earlier abstracts and other pages. Sections of the document are as follows: preface; history and acknowledgements; abstract format; recommended program package contents; program classification guide and thesaurus; and abstract collection. (RWR)

  16. Argonne Code Center: compilation of program abstracts

    International Nuclear Information System (INIS)

    Butler, M.K.; DeBruler, M.; Edwards, H.S.; Harrison, C. Jr.; Hughes, C.E.; Jorgensen, R.; Legan, M.; Menozzi, T.; Ranzini, L.; Strecok, A.J.

    1977-08-01

    This publication is the eleventh supplement to, and revision of, ANL-7411. It contains additional abstracts and revisions to some earlier abstracts and other pages. Sections of the complete document ANL-7411 are as follows: preface, history and acknowledgements, abstract format, recommended program package contents, program classification guide and thesaurus, and the abstract collection

  17. Argonne Code Center: compilation of program abstracts

    International Nuclear Information System (INIS)

    Butler, M.K.; DeBruler, M.; Edwards, H.S.

    1976-08-01

    This publication is the tenth supplement to, and revision of, ANL-7411. It contains additional abstracts and revisions to some earlier abstracts and other pages. Sections of the document are as follows: preface; history and acknowledgements; abstract format; recommended program package contents; program classification guide and thesaurus; and abstract collection

  18. Documentation Panels Enhance Teacher Education Programs

    Science.gov (United States)

    Warash, Bobbie Gibson

    2005-01-01

    Documentation of children's projects is advantageous to their learning process and is also a good method for student teachers to observe the process of learning. Documentation panels are a unique way to help student teachers understand how children learn. Completing a panel requires a student teacher to think through a process. Teachers must learn…

  19. NASA software documentation standard software engineering program

    Science.gov (United States)

    1991-01-01

    The NASA Software Documentation Standard (hereinafter referred to as Standard) can be applied to the documentation of all NASA software. This Standard is limited to documentation format and content requirements. It does not mandate specific management, engineering, or assurance standards or techniques. This Standard defines the format and content of documentation for software acquisition, development, and sustaining engineering. Format requirements address where information shall be recorded and content requirements address what information shall be recorded. This Standard provides a framework to allow consistency of documentation across NASA and visibility into the completeness of project documentation. This basic framework consists of four major sections (or volumes). The Management Plan contains all planning and business aspects of a software project, including engineering and assurance planning. The Product Specification contains all technical engineering information, including software requirements and design. The Assurance and Test Procedures contains all technical assurance information, including Test, Quality Assurance (QA), and Verification and Validation (V&V). The Management, Engineering, and Assurance Reports is the library and/or listing of all project reports.

  20. Utilities programs for the WIMSD4 code

    International Nuclear Information System (INIS)

    Leszczynski, F.

    1990-01-01

    The WIMSD4 code is widely known around the world. For its better use, it is convenient to count with auxiliary programs. Two of these programs, developed in FORTRAN 77, in the VAX computer of the Bariloche Atomic Center, are herein presented. WINTER (Wims INTERactive) to generate input data of WIMSD4 in an interactive way, and AMICO (Anisn MIx and COndense) to deal with cross sections data of a multigroup data library and of WIMS output to be used in other programs, such as: ANISN, DOT, CITATION, DIPOBAR, etc. (Author) [es

  1. Documentation for the viscoplastic and creep program

    DEFF Research Database (Denmark)

    Bellini, Anna

    2004-01-01

    of this workpackage is to simulate creep behavior of aluminum cast samples subjected to high temperature. In this document a two-state variables unified model is applied in order to simulate creep behavior and time-dependent metallurgical changes. The fundamental assumption of the unified theory is that creep...... is run using the material data obtained through the mentioned experimental study. The results obtained for the simulation of tensile tests and of creep tests are compared with experimental curves, showing a good agreement. Moreover, the document describes the results obtained during the first...... is quite stable and convergence can be reached also with big time steps. Keywords: Viscoplasticity, creep, unified constitutive model, aluminum, high temperature....

  2. Appendix B - GPRA06 biomass program documentation

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2009-01-18

    This appendix discusses the assumptions and methods employed in the biomass benefits analysis that is part of the fiscal year 2006 GPRA benefits analysis for all of the Department of Energy’s Energy Efficiency and Renewable Energy (EERE) research and deployment programs. The biomass benefits analysis focuses on the benefits of future achievements by the program and excludes retrospective benefits and benefits resulting from industry’s own initiative and funding.

  3. Data calculation program for RELAP 5 code

    International Nuclear Information System (INIS)

    Silvestre, Larissa J.B.; Sabundjian, Gaiane

    2015-01-01

    As the criteria and requirements for a nuclear power plant are extremely rigid, computer programs for simulation and safety analysis are required for certifying and licensing a plant. Based on this scenario, some sophisticated computational tools have been used such as the Reactor Excursion and Leak Analysis Program (RELAP5), which is the most used code for the thermo-hydraulic analysis of accidents and transients in nuclear reactors. A major difficulty in the simulation using RELAP5 code is the amount of information required for the simulation of thermal-hydraulic accidents or transients. The preparation of the input data leads to a very large number of mathematical operations for calculating the geometry of the components. Therefore, a mathematical friendly preprocessor was developed in order to perform these calculations and prepare RELAP5 input data. The Visual Basic for Application (VBA) combined with Microsoft EXCEL demonstrated to be an efficient tool to perform a number of tasks in the development of the program. Due to the absence of necessary information about some RELAP5 components, this work aims to make improvements to the Mathematic Preprocessor for RELAP5 code (PREREL5). For the new version of the preprocessor, new screens of some components that were not programmed in the original version were designed; moreover, screens of pre-existing components were redesigned to improve the program. In addition, an English version was provided for the new version of the PREREL5. The new design of PREREL5 contributes for saving time and minimizing mistakes made by users of the RELAP5 code. The final version of this preprocessor will be applied to Angra 2. (author)

  4. Data calculation program for RELAP 5 code

    Energy Technology Data Exchange (ETDEWEB)

    Silvestre, Larissa J.B.; Sabundjian, Gaiane, E-mail: larissajbs@usp.br, E-mail: gdjian@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2015-07-01

    As the criteria and requirements for a nuclear power plant are extremely rigid, computer programs for simulation and safety analysis are required for certifying and licensing a plant. Based on this scenario, some sophisticated computational tools have been used such as the Reactor Excursion and Leak Analysis Program (RELAP5), which is the most used code for the thermo-hydraulic analysis of accidents and transients in nuclear reactors. A major difficulty in the simulation using RELAP5 code is the amount of information required for the simulation of thermal-hydraulic accidents or transients. The preparation of the input data leads to a very large number of mathematical operations for calculating the geometry of the components. Therefore, a mathematical friendly preprocessor was developed in order to perform these calculations and prepare RELAP5 input data. The Visual Basic for Application (VBA) combined with Microsoft EXCEL demonstrated to be an efficient tool to perform a number of tasks in the development of the program. Due to the absence of necessary information about some RELAP5 components, this work aims to make improvements to the Mathematic Preprocessor for RELAP5 code (PREREL5). For the new version of the preprocessor, new screens of some components that were not programmed in the original version were designed; moreover, screens of pre-existing components were redesigned to improve the program. In addition, an English version was provided for the new version of the PREREL5. The new design of PREREL5 contributes for saving time and minimizing mistakes made by users of the RELAP5 code. The final version of this preprocessor will be applied to Angra 2. (author)

  5. Automatic generation of data merging program codes.

    OpenAIRE

    Hyensook, Kim; Oussena, Samia; Zhang, Ying; Clark, Tony

    2010-01-01

    Data merging is an essential part of ETL (Extract-Transform-Load) processes to build a data warehouse system. To avoid rewheeling merging techniques, we propose a Data Merging Meta-model (DMM) and its transformation into executable program codes in the manner of model driven engineering. DMM allows defining relationships of different model entities and their merging types in conceptual level. Our formalized transformation described using ATL (ATLAS Transformation Language) enables automatic g...

  6. Guidelines for the documentation of digital computer programs - approved 1974

    International Nuclear Information System (INIS)

    Anon.

    1975-01-01

    This standard presents guidelines for the documentation of engineering and scientific computer programs. Good documentation promotes understanding, reduces duplication of effort, eases conversion to different computer environments and aids modification for extended applications. Good documentation is essential for implementation and effective use of programs obtained from other installations. Since the intention of this standard is to encourage better communication between the developer and user, it should be regarded as a guide rather than a set of rigid specifications. As a guide, it is sufficiently comprehensive to apply to large-scale programs intended for extensive external use. Not all features of this document are appropriate in all circumstances. In general, as the project complexity increases so does the need for more complete documentation. An organization may have special documentation requirements which supersede or extend these guidelines. This standard is a revision of ANS-STD.2-1967 and supersedes it

  7. Quench Simulation Studies: Program documentation of SPQR

    CERN Document Server

    Sonnemann, F

    2001-01-01

    Quench experiments are being performed on prototypes of the superconducting magnets and busbars to determine the adequate design and protection. Many tests can only be understood correctly with the help of quench simulations that model the thermo-hydraulic and electrodynamic processes during a quench. In some cases simulations are the only method to scale the experimental results of prototype measurements to match the situation of quenching superconducting elements in the LHC. This note introduces the theoretical quench model and the use of the simulation program SPQR (Simulation Program for Quench Research), which has been developed to compute the quench process in superconducting magnets and busbars. The model approximates the heat balance equation with the finite difference method including the temperature dependence of the material parameters. SPQR allows the simulation of longitudinal quench propagation along a superconducting cable, the transverse propagation between adjacent conductors, heat transfer i...

  8. Repository-based software engineering program: Concept document

    Science.gov (United States)

    1992-01-01

    This document provides the context for Repository-Based Software Engineering's (RBSE's) evolving functional and operational product requirements, and it is the parent document for development of detailed technical and management plans. When furnished, requirements documents will serve as the governing RBSE product specification. The RBSE Program Management Plan will define resources, schedules, and technical and organizational approaches to fulfilling the goals and objectives of this concept. The purpose of this document is to provide a concise overview of RBSE, describe the rationale for the RBSE Program, and define a clear, common vision for RBSE team members and customers. The document also provides the foundation for developing RBSE user and system requirements and a corresponding Program Management Plan. The concept is used to express the program mission to RBSE users and managers and to provide an exhibit for community review.

  9. ANS severe accident program overview & planning document

    Energy Technology Data Exchange (ETDEWEB)

    Taleyarkhan, R.P.

    1995-09-01

    The Advanced Neutron Source (ANS) severe accident document was developed to provide a concise and coherent mechanism for presenting the ANS SAP goals, a strategy satisfying these goals, a succinct summary of the work done to date, and what needs to be done in the future to ensure timely licensability. Guidance was received from various bodies [viz., panel members of the ANS severe accident workshop and safety review committee, Department of Energy (DOE) orders, Nuclear Regulatory Commission (NRC) requirements for ALWRs and advanced reactors, ACRS comments, world-wide trends] were utilized to set up the ANS-relevant SAS goals and strategy. An in-containment worker protection goal was also set up to account for the routine experimenters and other workers within containment. The strategy for achieving the goals is centered upon closing the severe accident issues that have the potential for becoming certification issues when assessed against realistic bounding events. Realistic bounding events are defined as events with an occurrency frequency greater than 10{sup {minus}6}/y. Currently, based upon the level-1 probabilistic risk assessment studies, the realistic bounding events for application for issue closure are flow blockage of fuel element coolant channels, and rapid depressurization-related accidents.

  10. Implementation of QR Code and Digital Signature to Determine the Validity of KRS and KHS Documents

    Directory of Open Access Journals (Sweden)

    Fatich Fazlur Rochman

    2017-05-01

    Full Text Available Universitas Airlangga students often find it difficult to verify the mark that came out in the Kartu Hasil Studi (KHS is called Study Result Card or courses taken in the Kartu Rencana Studi (KRS is called Study Plan Card, if there are changes to the data on the system used Universitas Airlangga. This complicated KRS and KHS verification process happened because the KRS and KHS documents that owned by student is easier to counterfeit than the data in the system. Implementation digital signature and QR Code technology as a solution that can prove the validity of KRS or KHS. The KRS and KHS validation system developed by Digital Signature and QR Code. QR Code is a type of matrix code that was developed as a code that allows its contents to be decoded at high speed while the Digital Signature has a function as a marker on the data to ensure that the data is the original data. The verification process was divided into two types are reading the Digital Signature and printing document that works by scanning the data from QR Code. The application of the system is carried out were the addition of the QR Code on KRS and KHS, required a readiness of human resources. 

  11. Planning, Conducting, and Documenting Data Analysis for Program Improvement

    Science.gov (United States)

    Winer, Abby; Taylor, Cornelia; Derrington, Taletha; Lucas, Anne

    2015-01-01

    This 2015 document was developed to help technical assistance (TA) providers and state staff define and limit the scope of data analysis for program improvement efforts, including the State Systemic Improvement Plan (SSIP); develop a plan for data analysis; document alternative hypotheses and additional analyses as they are generated; and…

  12. Nuclear Waste Management Program summary document, FY 1981

    International Nuclear Information System (INIS)

    1980-03-01

    The Nuclear Waste Management Program Summary Document outlines the operational and research and development (R and D) activities of the Office of Nuclear Waste Management (NEW) under the Assistant Secretary for Nuclear Energy, US Department of Energy (DOE). This document focuses on the current and planned activities in waste management for FY 1981. This Program Summary Document (PSD) was prepared in order to explain the Federal nuclear waste management and spent fuel storage programs to Congress and its committees and to interested members of the public, the private sector, and the research community. The national energy policy as it applies to waste management and spent fuel storage is presented first. The program strategy, structure, budget, management approach, and public participation programs are then identified. The next section describes program activities and outlines their status. Finally, the applicability of departmental policies to NEW programs is summarized, including field and regional activities, commercialization plans, and environmental and socioeconomic implications of waste management activities, and international programs. This Nuclear Waste Management Program Summary Document is meant to serve as a guide to the progress of R and D and other energy technology programs in radioactive waste management. The R and D objective is to provide the Nation with acceptable solutions to short- and long-term management problems for all forms of radioactive waste and spent fuel

  13. Nuclear Waste Management Program summary document, FY 1981

    Energy Technology Data Exchange (ETDEWEB)

    Meyers, Sheldon

    1980-03-01

    The Nuclear Waste Management Program Summary Document outlines the operational and research and development (R and D) activities of the Office of Nuclear Waste Management (NEW) under the Assistant Secretary for Nuclear Energy, US Department of Energy (DOE). This document focuses on the current and planned activities in waste management for FY 1981. This Program Summary Document (PSD) was prepared in order to explain the Federal nuclear waste management and spent fuel storage programs to Congress and its committees and to interested members of the public, the private sector, and the research community. The national energy policy as it applies to waste management and spent fuel storage is presented first. The program strategy, structure, budget, management approach, and public participation programs are then identified. The next section describes program activities and outlines their status. Finally, the applicability of departmental policies to NEW programs is summarized, including field and regional activities, commercialization plans, and environmental and socioeconomic implications of waste management activities, and international programs. This Nuclear Waste Management Program Summary Document is meant to serve as a guide to the progress of R and D and other energy technology programs in radioactive waste management. The R and D objective is to provide the Nation with acceptable solutions to short- and long-term management problems for all forms of radioactive waste and spent fuel.

  14. Instructional Coding System for Mathematics Program of Studies. MET, A Title IV-C Project.

    Science.gov (United States)

    Fairfax County Public Schools, VA. Dept. of Instructional Services.

    This document is part of the Management for Effective Teaching (MET) support kit, a pilot project designed by the Fairfax County (Virginia) Public Schools to assist elementary school teachers in planning, managing, and implementing the county's Program of Studies (POS). This document provides an alpha-numeric coding system to be used in…

  15. Coding and Billing in Surgical Education: A Systems-Based Practice Education Program.

    Science.gov (United States)

    Ghaderi, Kimeya F; Schmidt, Scott T; Drolet, Brian C

    Despite increased emphasis on systems-based practice through the Accreditation Council for Graduate Medical Education core competencies, few studies have examined what surgical residents know about coding and billing. We sought to create and measure the effectiveness of a multifaceted approach to improving resident knowledge and performance of documenting and coding outpatient encounters. We identified knowledge gaps and barriers to documentation and coding in the outpatient setting. We implemented a series of educational and workflow interventions with a group of 12 residents in a surgical clinic at a tertiary care center. To measure the effect of this program, we compared billing codes for 1 year before intervention (FY2012) to prospectively collected data from the postintervention period (FY2013). All related documentation and coding were verified by study-blinded auditors. Interventions took place at the outpatient surgical clinic at Rhode Island Hospital, a tertiary-care center. A cohort of 12 plastic surgery residents ranging from postgraduate year 2 through postgraduate year 6 participated in the interventional sequence. A total of 1285 patient encounters in the preintervention group were compared with 1170 encounters in the postintervention group. Using evaluation and management codes (E&M) as a measure of documentation and coding, we demonstrated a significant and durable increase in billing with supporting clinical documentation after the intervention. For established patient visits, the monthly average E&M code level increased from 2.14 to 3.05 (p coding and billing of outpatient clinic encounters. Using externally audited coding data, we demonstrate significantly increased rates of higher complexity E&M coding in a stable patient population based on improved documentation and billing awareness by the residents. Copyright © 2017 Association of Program Directors in Surgery. Published by Elsevier Inc. All rights reserved.

  16. "Hour of Code": Can It Change Students' Attitudes toward Programming?

    Science.gov (United States)

    Du, Jie; Wimmer, Hayden; Rada, Roy

    2016-01-01

    The Hour of Code is a one-hour introduction to computer science organized by Code.org, a non-profit dedicated to expanding participation in computer science. This study investigated the impact of the Hour of Code on students' attitudes towards computer programming and their knowledge of programming. A sample of undergraduate students from two…

  17. [Quality management and strategic consequences of assessing documentation and coding under the German Diagnostic Related Groups system].

    Science.gov (United States)

    Schnabel, M; Mann, D; Efe, T; Schrappe, M; V Garrel, T; Gotzen, L; Schaeg, M

    2004-10-01

    The introduction of the German Diagnostic Related Groups (D-DRG) system requires redesigning administrative patient management strategies. Wrong coding leads to inaccurate grouping and endangers the reimbursement of treatment costs. This situation emphasizes the roles of documentation and coding as factors of economical success. The aims of this study were to assess the quantity and quality of initial documentation and coding (ICD-10 and OPS-301) and find operative strategies to improve efficiency and strategic means to ensure optimal documentation and coding quality. In a prospective study, documentation and coding quality were evaluated in a standardized way by weekly assessment. Clinical data from 1385 inpatients were processed for initial correctness and quality of documentation and coding. Principal diagnoses were found to be accurate in 82.7% of cases, inexact in 7.1%, and wrong in 10.1%. Effects on financial returns occurred in 16%. Based on these findings, an optimized, interdisciplinary, and multiprofessional workflow on medical documentation, coding, and data control was developed. Workflow incorporating regular assessment of documentation and coding quality is required by the DRG system to ensure efficient accounting of hospital services. Interdisciplinary and multiprofessional cooperation is recognized to be an important factor in establishing an efficient workflow in medical documentation and coding.

  18. Campus Partnerships Improve Impact Documentation of Nutrition Programs

    Science.gov (United States)

    Brinkman, Patricia

    2015-01-01

    Partnerships with other campus college units can provide ways of improving Extension's impact documentation. Nutrition programs have relied upon knowledge gained and people's self report of behavior change. Partnering with the College of Nursing, student nurses provided blood screenings during the pre and 6 month follow-up of a pilot heart risk…

  19. Intrasystem Electromagnetic Compatibility Analysis Program. Volume III. Computer Program Documentation

    Science.gov (United States)

    1974-12-01

    Cor intied) PROGRAM NAME SIMBOL DEFINITION FQEPDB fep IN dB FQEPL LOWER INTERVAL BOUNDARY FREQ OF fep FQEPU UPPER INTERVAL BOUNDARY FREQ OF f .4, fep...I• TOR. VARIABLES L __G~~ NM SIMBOL DEFINITION BWFE 1 BANDWIDTH FACTOR OF EM’TR BANDWIDTH FACTOR OF RCPT EINTB INTEGRATBD MARGIN BROAD BAND COMPON

  20. Survey of particle codes in the Magnetic Fusion Energy Program

    International Nuclear Information System (INIS)

    1977-12-01

    In the spring of 1976, the Fusion Plasma Theory Branch of the Division of Magnetic Fusion Energy conducted a survey of all the physics computer codes being supported at that time. The purpose of that survey was to allow DMFE to prepare a description of the codes for distribution to the plasma physics community. This document is the first of several planned and covers those types of codes which treat the plasma as a group of particles

  1. Note related to the elaboration of a coding by key sentences for the programming of a document automatic selection system; Notice relative a l'elaboration d'un codage par phrases cles pour la programmation d'un systeme De selection automatique des documents

    Energy Technology Data Exchange (ETDEWEB)

    Leroy, A. [Commissariat a l' energie atomique et aux energies alternatives - CEA, Service de Documentation (France); Braffort, P. [Commissariat a l' energie atomique et aux energies alternatives - CEA, Departement d' Electronique (France)

    1959-07-01

    This note deals with the providing of CEA documentalists with a tool for coding studies. The authors first discuss issues related to code selection criteria (author classification, topic classification, and so on), and propose an overview and a discussion of linguistic models. They also comment how diagrams illustrating relationships between words are built up, and propose a diagram representation example which includes different concepts such as conditions, properties, object, tools or processes (for example hardness for a steel, batch processing for a condition, or sintering for a process), and also the introduction of negation. Then, the authors address how basic concepts can be highlighted, describe how key sentences can be built up, and propose an example analysis in the case of a published article dealing with nuclear reactors (in this case, the study of a liquid-metal neutron absorber for the control of a gas-cooled power reactor). Perspectives of evolution are finally discussed.

  2. An ultraviolet-visible spectrophotometer automation system. Part 3: Program documentation

    Science.gov (United States)

    Roth, G. S.; Teuschler, J. M.; Budde, W. L.

    1982-07-01

    The Ultraviolet-Visible Spectrophotometer (UVVIS) automation system accomplishes 'on-line' spectrophotometric quality assurance determinations, report generations, plot generations and data reduction for chlorophyll or color analysis. This system also has the capability to process manually entered data for the analysis of chlorophyll or color. For each program of the UVVIS system, this document contains a program description, flowchart, variable dictionary, code listing, and symbol cross-reference table. Also included are descriptions of file structures and of routines common to all automated analyses. The programs are written in Data General extended BASIC, Revision 4.3, under the RDOS operating systems, Revision 6.2. The BASIC code has been enhanced for real-time data acquisition, which is accomplished by CALLS to assembly language subroutines. Two other related publications are 'An Ultraviolet-Visible Spectrophotometer Automation System - Part I Functional Specifications,' and 'An Ultraviolet-Visible Spectrophotometer Automation System - Part II User's Guide.'

  3. Segmentation-driven compound document coding based on H.264/AVC-INTRA.

    Science.gov (United States)

    Zaghetto, Alexandre; de Queiroz, Ricardo L

    2007-07-01

    In this paper, we explore H.264/AVC operating in intraframe mode to compress a mixed image, i.e., composed of text, graphics, and pictures. Even though mixed contents (compound) documents usually require the use of multiple compressors, we apply a single compressor for both text and pictures. For that, distortion is taken into account differently between text and picture regions. Our approach is to use a segmentation-driven adaptation strategy to change the H.264/AVC quantization parameter on a macroblock by macroblock basis, i.e., we deviate bits from pictorial regions to text in order to keep text edges sharp. We show results of a segmentation driven quantizer adaptation method applied to compress documents. Our reconstructed images have better text sharpness compared to straight unadapted coding, at negligible visual losses on pictorial regions. Our results also highlight the fact that H.264/AVC-INTRA outperforms coders such as JPEG-2000 as a single coder for compound images.

  4. Standard Review Plan Maintenance Program implementing procedures document

    International Nuclear Information System (INIS)

    1996-11-01

    The implementing Procedures Document (IPD) was developed by the Inspection Program Projects Branch, Office of Nuclear Reactor Regulation, with assistance from Pacific Northwest National Laboratory, for the Standard Review Plan Maintenance Program (SRP-MP). The SRP-MP was established to maintain the Standard Review Plan (SRP) on an on-going basis. The IPD provides guidance, including an overall approach and procedures, for SRP-MP tasks. The objective of the IPD is to ensure that modifications to SRP need to reflect current NRC requirements and guidance are identified and that a consistent methodology is used to develop and revise SRP sections

  5. Computer code qualification program for the Advanced CANDU Reactor

    International Nuclear Information System (INIS)

    Popov, N.K.; Wren, D.J.; Snell, V.G.; White, A.J.; Boczar, P.G.

    2003-01-01

    Atomic Energy of Canada Ltd (AECL) has developed and implemented a Software Quality Assurance program (SQA) to ensure that its analytical, scientific and design computer codes meet the required standards for software used in safety analyses. This paper provides an overview of the computer programs used in Advanced CANDU Reactor (ACR) safety analysis, and assessment of their applicability in the safety analyses of the ACR design. An outline of the incremental validation program, and an overview of the experimental program in support of the code validation are also presented. An outline of the SQA program used to qualify these computer codes is also briefly presented. To provide context to the differences in the SQA with respect to current CANDUs, the paper also provides an overview of the ACR design features that have an impact on the computer code qualification. (author)

  6. Impact of documentation errors on accuracy of cause of death coding in an educational hospital in Southern Iran.

    Science.gov (United States)

    Haghighi, Mohammad Hosein Hayavi; Dehghani, Mohammad; Teshnizi, Saeid Hoseini; Mahmoodi, Hamid

    2014-01-01

    Accurate cause of death coding leads to organised and usable death information but there are some factors that influence documentation on death certificates and therefore affect the coding. We reviewed the role of documentation errors on the accuracy of death coding at Shahid Mohammadi Hospital (SMH), Bandar Abbas, Iran. We studied the death certificates of all deceased patients in SMH from October 2010 to March 2011. Researchers determined and coded the underlying cause of death on the death certificates according to the guidelines issued by the World Health Organization in Volume 2 of the International Statistical Classification of Diseases and Health Related Problems-10th revision (ICD-10). Necessary ICD coding rules (such as the General Principle, Rules 1-3, the modification rules and other instructions about death coding) were applied to select the underlying cause of death on each certificate. Demographic details and documentation errors were then extracted. Data were analysed with descriptive statistics and chi square tests. The accuracy rate of causes of death coding was 51.7%, demonstrating a statistically significant relationship (p=.001) with major errors but not such a relationship with minor errors. Factors that result in poor quality of Cause of Death coding in SMH are lack of coder training, documentation errors and the undesirable structure of death certificates.

  7. On the linear programming bound for linear Lee codes.

    Science.gov (United States)

    Astola, Helena; Tabus, Ioan

    2016-01-01

    Based on an invariance-type property of the Lee-compositions of a linear Lee code, additional equality constraints can be introduced to the linear programming problem of linear Lee codes. In this paper, we formulate this property in terms of an action of the multiplicative group of the field [Formula: see text] on the set of Lee-compositions. We show some useful properties of certain sums of Lee-numbers, which are the eigenvalues of the Lee association scheme, appearing in the linear programming problem of linear Lee codes. Using the additional equality constraints, we formulate the linear programming problem of linear Lee codes in a very compact form, leading to a fast execution, which allows to efficiently compute the bounds for large parameter values of the linear codes.

  8. Standard Review Plan Update and Development Program. Implementing Procedures Document

    Energy Technology Data Exchange (ETDEWEB)

    1992-05-01

    This implementing procedures document (IPD) was prepared for use in implementing tasks under the standard review plan update and development program (SRP-UDP). The IPD provides comprehensive guidance and detailed procedures for SRP-UDP tasks. The IPD is mandatory for contractors performing work for the SRP-UDP. It is guidance for the staff. At the completion of the SRP-UDP, the IPD will be revised (to remove the UDP aspects) and will replace NRR Office Letter No. 800 as long-term maintenance procedures.

  9. AECL's advanced code program

    Energy Technology Data Exchange (ETDEWEB)

    McGee, G.; Ball, J. [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada)

    2012-07-01

    This paper discusses the advanced code project at AECL.Current suite of Analytical, Scientific and Design (ASD) computer codes in use by Canadian Nuclear Power Industry is mostly developed 20 or more years ago. It is increasingly difficult to develop and maintain. It consist of many independent tools and integrated analysis is difficult, time consuming and error-prone. The objectives of this project is to demonstrate that nuclear facility systems, structures and components meet their design objectives in terms of function, cost, and safety; demonstrate that the nuclear facility meets licensing requirements in terms of consequences of off-normal events; dose to public, workers, impact on environment and demonstrate that the nuclear facility meets operational requirements with respect to on-power fuelling and outage management.

  10. Code Development and Analysis Program: developmental checkout of the BEACON/MOD2A code

    International Nuclear Information System (INIS)

    Ramsthaler, J.A.; Lime, J.F.; Sahota, M.S.

    1978-12-01

    A best-estimate transient containment code, BEACON, is being developed by EG and G Idaho, Inc. for the Nuclear Regulatory Commission's reactor safety research program. This is an advanced, two-dimensional fluid flow code designed to predict temperatures and pressures in a dry PWR containment during a hypothetical loss-of-coolant accident. The most recent version of the code, MOD2A, is presently in the final stages of production prior to being released to the National Energy Software Center. As part of the final code checkout, seven sample problems were selected to be run with BEACON/MOD2A

  11. Energy Efficiency Program Administrators and Building Energy Codes

    Science.gov (United States)

    Explore how energy efficiency program administrators have helped advance building energy codes at federal, state, and local levels—using technical, institutional, financial, and other resources—and discusses potential next steps.

  12. INL Experimental Program Roadmap for Thermal Hydraulic Code Validation

    Energy Technology Data Exchange (ETDEWEB)

    Glenn McCreery; Hugh McIlroy

    2007-09-01

    Advanced computer modeling and simulation tools and protocols will be heavily relied on for a wide variety of system studies, engineering design activities, and other aspects of the Next Generation Nuclear Power (NGNP) Very High Temperature Reactor (VHTR), the DOE Global Nuclear Energy Partnership (GNEP), and light-water reactors. The goal is for all modeling and simulation tools to be demonstrated accurate and reliable through a formal Verification and Validation (V&V) process, especially where such tools are to be used to establish safety margins and support regulatory compliance, or to design a system in a manner that reduces the role of expensive mockups and prototypes. Recent literature identifies specific experimental principles that must be followed in order to insure that experimental data meet the standards required for a “benchmark” database. Even for well conducted experiments, missing experimental details, such as geometrical definition, data reduction procedures, and manufacturing tolerances have led to poor Benchmark calculations. The INL has a long and deep history of research in thermal hydraulics, especially in the 1960s through 1980s when many programs such as LOFT and Semiscle were devoted to light-water reactor safety research, the EBRII fast reactor was in operation, and a strong geothermal energy program was established. The past can serve as a partial guide for reinvigorating thermal hydraulic research at the laboratory. However, new research programs need to fully incorporate modern experimental methods such as measurement techniques using the latest instrumentation, computerized data reduction, and scaling methodology. The path forward for establishing experimental research for code model validation will require benchmark experiments conducted in suitable facilities located at the INL. This document describes thermal hydraulic facility requirements and candidate buildings and presents examples of suitable validation experiments related

  13. From Symbolic to Substantive Documents: When Business Codes of Ethics Impact Unethical Behavior in the Workplace

    OpenAIRE

    Kaptein, S.P.

    2009-01-01

    textabstractA business code of ethics is widely regarded as an important instrument to curb unethical behavior in the workplace. However, little is empirically known about the factors that determine the impact of a code on unethical behavior. Besides the existence of a code, this study proposes five determining factors: the content of the code, the frequency of communication activities surrounding the code, the quality of the communication activities, and the embedment of the code in the orga...

  14. PERMUTATION-BASED POLYMORPHIC STEGO-WATERMARKS FOR PROGRAM CODES

    Directory of Open Access Journals (Sweden)

    Denys Samoilenko

    2016-06-01

    Full Text Available Purpose: One of the most actual trends in program code protection is code marking. The problem consists in creation of some digital “watermarks” which allow distinguishing different copies of the same program codes. Such marks could be useful for authority protection, for code copies numbering, for program propagation monitoring, for information security proposes in client-server communication processes. Methods: We used the methods of digital steganography adopted for program codes as text objects. The same-shape symbols method was transformed to same-semantic element method due to codes features which makes them different from ordinary texts. We use dynamic principle of marks forming making codes similar to be polymorphic. Results: We examined the combinatorial capacity of permutations possible in program codes. As a result it was shown that the set of 5-7 polymorphic variables is suitable for the most modern network applications. Marks creation and restoration algorithms where proposed and discussed. The main algorithm is based on full and partial permutations in variables names and its declaration order. Algorithm for partial permutation enumeration was optimized for calculation complexity. PHP code fragments which realize the algorithms were listed. Discussion: Methodic proposed in the work allows distinguishing of each client-server connection. In a case if a clone of some network resource was found the methodic could give information about included marks and thereby data on IP, date and time, authentication information of client copied the resource. Usage of polymorphic stego-watermarks should improve information security indexes in network communications.

  15. International Code Assessment and Applications Program: Annual report

    International Nuclear Information System (INIS)

    Ting, P.; Hanson, R.; Jenks, R.

    1987-03-01

    This is the first annual report of the International Code Assessment and Applications Program (ICAP). The ICAP was organized by the Office of Nuclear Regulatory Research, United States Nuclear Regulatory Commission (USNRC) in 1985. The ICAP is an international cooperative reactor safety research program planned to continue over a period of approximately five years. To date, eleven European and Asian countries/organizations have joined the program through bilateral agreements with the USNRC. Seven proposed agreements are currently under negotiation. The primary mission of the ICAP is to provide independent assessment of the three major advanced computer codes (RELAP5, TRAC-PWR, and TRAC-BWR) developed by the USNRC. However, program activities can be expected to enhance the assessment process throughout member countries. The codes were developed to calculate the reactor plant response to transients and loss-of-coolant accidents. Accurate prediction of normal and abnormal plant response using the codes enhances procedures and regulations used for the safe operation of the plant and also provides technical basis for assessing the safety margin of future reactor plant designs. The ICAP is providing required assessment data that will contribute to quantification of the code uncertainty for each code. The first annual report is devoted to coverage of program activities and accomplishments during the period between April 1985 and March 1987

  16. RunJumpCode: An Educational Game for Educating Programming

    Science.gov (United States)

    Hinds, Matthew; Baghaei, Nilufar; Ragon, Pedrito; Lambert, Jonathon; Rajakaruna, Tharindu; Houghton, Travers; Dacey, Simon

    2017-01-01

    Programming promotes critical thinking, problem solving and analytic skills through creating solutions that can solve everyday problems. However, learning programming can be a daunting experience for a lot of students. "RunJumpCode" is an educational 2D platformer video game, designed and developed in Unity, to teach players the…

  17. Epigenetic codes programming class switch recombination

    Directory of Open Access Journals (Sweden)

    Bharat eVaidyanathan

    2015-09-01

    Full Text Available Class switch recombination imparts B cells with a fitness-associated adaptive advantage during a humoral immune response by using a precision-tailored DNA excision and ligation process to swap the default constant region gene of the antibody with a new one that has unique effector functions. This secondary diversification of the antibody repertoire is a hallmark of the adaptability of B cells when confronted with environmental and pathogenic challenges. Given that the nucleotide sequence of genes during class switching remains unchanged (genetic constraints, it is logical and necessary therefore, to integrate the adaptability of B cells to an epigenetic state, which is dynamic and can be heritably modulated before, after or even during an antibody-dependent immune response. Epigenetic regulation encompasses heritable changes that affect function (phenotype without altering the sequence information embedded in a gene, and include histone, DNA and RNA modifications. Here, we review current literature on how B cells use an epigenetic code language as a means to ensure antibody plasticity in light of pathogenic insults.

  18. Interactive game programming with Python (CodeSkulptor)

    OpenAIRE

    Ajayi, Richard Olugbenga

    2014-01-01

    Over the years, several types of gaming platforms have been created to encourage a more organised and friendly atmosphere for game lovers in various works of life, culture, and environment. This thesis focuses on the concept of interactive programming using Python. It encourages the use of Python to create simple interactive games applications based on basic human concept and ideas. CodeSkulptor is a browser-based IDE programming environment and uses the Python programming language. O...

  19. LFTPLT8: plotter program for RELAP5 code

    International Nuclear Information System (INIS)

    Yamano, Kazuaki; Abe, Nobuaki; Tasaka, Kanji

    1981-02-01

    The plotter program LFTPLT8 is a new version of the LFTPLT7 developed to plot the calculated results by RELAP5 code. The RELAP5/MOD0 code has also been revised for LFTPLT8. LFTPLT8 is capable of multiple plotting of any combination of experimental data and calculated results by RELAP4J, RELAP4/MOD5, ALARM-P1, and RELAP5/MOD0. (author)

  20. Standardization of computer programs - basis of the Czechoslovak library of nuclear codes

    International Nuclear Information System (INIS)

    Gregor, M.

    1987-01-01

    A standardized form of computer code documentation has been established in the CSSR in the field of reactor safety. Structure and content of the documentation are described and codes already subject to this process are mentioned. The formation of a Czechoslovak nuclear code library and facilitated discussion of safety reports containing results of standardized codes are aimed at

  1. From Symbolic to Substantive Documents: When Business Codes of Ethics Impact Unethical Behavior in the Workplace

    NARCIS (Netherlands)

    S.P. Kaptein (Muel)

    2009-01-01

    textabstractA business code of ethics is widely regarded as an important instrument to curb unethical behavior in the workplace. However, little is empirically known about the factors that determine the impact of a code on unethical behavior. Besides the existence of a code, this study proposes five

  2. Concept document of the repository-based software engineering program: A constructive appraisal

    Science.gov (United States)

    1992-01-01

    A constructive appraisal of the Concept Document of the Repository-Based Software Engineering Program is provided. The Concept Document is designed to provide an overview of the Repository-Based Software Engineering (RBSE) Program. The Document should be brief and provide the context for reading subsequent requirements and product specifications. That is, all requirements to be developed should be traceable to the Concept Document. Applied Expertise's analysis of the Document was directed toward assuring that: (1) the Executive Summary provides a clear, concise, and comprehensive overview of the Concept (rewrite as necessary); (2) the sections of the Document make best use of the NASA 'Data Item Description' for concept documents; (3) the information contained in the Document provides a foundation for subsequent requirements; and (4) the document adequately: identifies the problem being addressed; articulates RBSE's specific role; specifies the unique aspects of the program; and identifies the nature and extent of the program's users.

  3. The linear programming bound for binary linear codes

    NARCIS (Netherlands)

    Brouwer, A.E.

    1993-01-01

    Combining Delsarte's (1973) linear programming bound with the information that certain weights cannot occur, new upper bounds for dmin (n,k), the maximum possible minimum distance of a binary linear code with given word length n and dimension k, are derived.

  4. 75 FR 24718 - Guidance for Industry on Documenting Statistical Analysis Programs and Data Files; Availability

    Science.gov (United States)

    2010-05-05

    ...] Guidance for Industry on Documenting Statistical Analysis Programs and Data Files; Availability AGENCY... documenting statistical analyses and data files submitted to the Center for Veterinary Medicine (CVM) for the... on Documenting Statistical Analysis Programs and Data Files; Availability'' giving interested persons...

  5. Quantifying the improvement in sepsis diagnosis, documentation, and coding: the marginal causal effect of year of hospitalization on sepsis diagnosis.

    Science.gov (United States)

    Jafarzadeh, S Reza; Thomas, Benjamin S; Marschall, Jonas; Fraser, Victoria J; Gill, Jeff; Warren, David K

    2016-01-01

    To quantify the coinciding improvement in the clinical diagnosis of sepsis, its documentation in the electronic health records, and subsequent medical coding of sepsis for billing purposes in recent years. We examined 98,267 hospitalizations in 66,208 patients who met systemic inflammatory response syndrome criteria at a tertiary care center from 2008 to 2012. We used g-computation to estimate the causal effect of the year of hospitalization on receiving an International Classification of Diseases, Ninth Revision, Clinical Modification discharge diagnosis code for sepsis by estimating changes in the probability of getting diagnosed and coded for sepsis during the study period. When adjusted for demographics, Charlson-Deyo comorbidity index, blood culture frequency per hospitalization, and intensive care unit admission, the causal risk difference for receiving a discharge code for sepsis per 100 hospitalizations with systemic inflammatory response syndrome, had the hospitalization occurred in 2012, was estimated to be 3.9% (95% confidence interval [CI], 3.8%-4.0%), 3.4% (95% CI, 3.3%-3.5%), 2.2% (95% CI, 2.1%-2.3%), and 0.9% (95% CI, 0.8%-1.1%) from 2008 to 2011, respectively. Patients with similar characteristics and risk factors had a higher of probability of getting diagnosed, documented, and coded for sepsis in 2012 than in previous years, which contributed to an apparent increase in sepsis incidence. Copyright © 2016 Elsevier Inc. All rights reserved.

  6. Compilation of documented computer codes applicable to environmental assessment of radioactivity releases

    International Nuclear Information System (INIS)

    Hoffman, F.O.; Miller, C.W.; Shaeffer, D.L.; Garten, C.T. Jr.; Shor, R.W.; Ensminger, J.T.

    1977-04-01

    The objective of this paper is to present a compilation of computer codes for the assessment of accidental or routine releases of radioactivity to the environment from nuclear power facilities. The capabilities of 83 computer codes in the areas of environmental transport and radiation dosimetry are summarized in tabular form. This preliminary analysis clearly indicates that the initial efforts in assessment methodology development have concentrated on atmospheric dispersion, external dosimetry, and internal dosimetry via inhalation. The incorporation of terrestrial and aquatic food chain pathways has been a more recent development and reflects the current requirements of environmental legislation and the needs of regulatory agencies. The characteristics of the conceptual models employed by these codes are reviewed. The appendixes include abstracts of the codes and indexes by author, key words, publication description, and title

  7. Hanford site guide for preparing and maintaining generator group pollution prevention program documentation

    International Nuclear Information System (INIS)

    1995-12-01

    This manual provides the necessary guidance to contractor generator groups for developing and maintaining documentation of their pollution prevention (P2) program activities. Preparation of program documentation will demonstrate compliance with contractor and U.S. Department of Energy (DOE) requirements, as well as state and federal regulations. Contractor waste generator groups are no longer required to prepare and update facility waste minimization plans. Developing and maintaining program documentation replace this requirement

  8. Programming a real code in a functional language (part 1)

    Energy Technology Data Exchange (ETDEWEB)

    Hendrickson, C.P.

    1991-09-10

    For some, functional languages hold the promise of allowing ease of programming massively parallel computers that imperative languages such as Fortran and C do not offer. At LLNL, we have initiated a project to write the physics of a major production code in Sisal, a functional language developed at LLNL in collaboration with researchers throughout the world. We are investigating the expressibility of Sisal, as well as its performance on a shared-memory multiprocessor, the Y-MP. An interesting aspect of the project is that Sisal modules can call Fortran modules, and are callable by them. This eliminates the rewriting of 80% of the production code that would not benefit from parallel execution. Preliminary results indicate that the restrictive nature of the language does not cause problems in expressing the algorithms we have chosen. Some interesting aspects of programming in a mixed functional-imperative environment have surfaced, but can be managed. 8 refs.

  9. Universal Documentation System Handbook. Volume 2: Program Requirements and Operations Requirements Documents

    Science.gov (United States)

    1979-11-01

    plane. The local horizontal plane is de- lined as a plane normal to the geocentric position vector. Boxes 11J and UJ are the angles measured east...support the program/mission. BOX 1-9 Follow instructions for Pa«« 1010. BOX 10 LOCATION: Enter the areas or locations that are to be staffed with

  10. Step by step parallel programming method for molecular dynamics code

    International Nuclear Information System (INIS)

    Orii, Shigeo; Ohta, Toshio

    1996-07-01

    Parallel programming for a numerical simulation program of molecular dynamics is carried out with a step-by-step programming technique using the two phase method. As a result, within the range of a certain computing parameters, it is found to obtain parallel performance by using the level of parallel programming which decomposes the calculation according to indices of do-loops into each processor on the vector parallel computer VPP500 and the scalar parallel computer Paragon. It is also found that VPP500 shows parallel performance in wider range computing parameters. The reason is that the time cost of the program parts, which can not be reduced by the do-loop level of the parallel programming, can be reduced to the negligible level by the vectorization. After that, the time consuming parts of the program are concentrated on less parts that can be accelerated by the do-loop level of the parallel programming. This report shows the step-by-step parallel programming method and the parallel performance of the molecular dynamics code on VPP500 and Paragon. (author)

  11. Documentation and verification of the SHAFT code; Yucca Mountain Site Characterization Project

    Energy Technology Data Exchange (ETDEWEB)

    St.John, C.M. [Agapito (J.F.T.) and Associates, Inc., Grand Junction, CO (United States)

    1991-12-01

    The SHAFT code incorporates equations to compute stresses in a shaft liner when the rock through which a shaft passes is subject to known three-dimensional states of stress or strain. The deformation modes considered are hoop deformation, axial deformation, and shear on a plane normal to the shaft axis. Interaction between the liner and the soil and rock is considered, and it is assumed that the liner is in place before loading is applied. This code is intended to be used interactively but creates a permanent record complete with necessary quality assurance information. The code has been carefully verified for the case of generalized plane strain, in which an arbitrary axial strain can be defined. It may also be used for plane stress analysis. Output is given in the form of stresses at selected sample points in the linear and the rock and a simple graphical representation of the distribution of stress through the liner. 12 figs., 13 tabs.

  12. PCRELAP5: data calculation program for RELAP 5 code

    International Nuclear Information System (INIS)

    Silvestre, Larissa Jacome Barros

    2016-01-01

    Nuclear accidents in the world led to the establishment of rigorous criteria and requirements for nuclear power plant operations by the international regulatory bodies. By using specific computer programs, simulations of various accidents and transients likely to occur at any nuclear power plant are required for certifying and licensing a nuclear power plant. Based on this scenario, some sophisticated computational tools have been used such as the Reactor Excursion and Leak Analysis Program (RELAP5), which is the most widely used code for the thermo-hydraulic analysis of accidents and transients in nuclear reactors in Brazil and worldwide. A major difficulty in the simulation by using RELAP5 code is the amount of information required for the simulation of thermal-hydraulic accidents or transients. The preparation of the input data requires a great number of mathematical operations to calculate the geometry of the components. Thus, for those calculations performance and preparation of RELAP5 input data, a friendly mathematical preprocessor was designed. The Visual Basic for Application (VBA) for Microsoft Excel demonstrated to be an effective tool to perform a number of tasks in the development of the program. In order to meet the needs of RELAP5 users, the RELAP5 Calculation Program (Programa de Calculo do RELAP5 - PCRELAP5) was designed. The components of the code were codified; all entry cards including the optional cards of each one have been programmed. In addition, an English version for PCRELAP5 was provided. Furthermore, a friendly design was developed in order to minimize the time of preparation of input data and errors committed by users. In this work, the final version of this preprocessor was successfully applied for Safety Injection System (SIS) of Angra 2. (author)

  13. FY 1987 program summary document: Office of Defense Waste and Transportation Management

    International Nuclear Information System (INIS)

    1987-04-01

    This document describes the Office of Defense Waste and Transportation Management (DWTM) Program as supported by the President's Fiscal Year (FY) 1987 Budget Request to Congress. It specifically addresses the program's organization, objectives, strategies, and plans for FY 1987

  14. Program strategy document for the Nuclear Materials Transportation Technology Center

    International Nuclear Information System (INIS)

    Jefferson, R.M.

    1979-07-01

    A multiyear program plan is presented which describes the program of the Nuclear Materials Transportation Technology Center (TIC) at Sandia Laboratories. The work element plans, along with their corresponding work breakdown structures, are presented for TTC activities in the areas of Technology and Information Center, Systems Development, Technology, and Institutional Issues for the years from 1979 to 1985

  15. Programming peptidomimetic syntheses by translating genetic codes designed de novo.

    Science.gov (United States)

    Forster, Anthony C; Tan, Zhongping; Nalam, Madhavi N L; Lin, Hening; Qu, Hui; Cornish, Virginia W; Blacklow, Stephen C

    2003-05-27

    Although the universal genetic code exhibits only minor variations in nature, Francis Crick proposed in 1955 that "the adaptor hypothesis allows one to construct, in theory, codes of bewildering variety." The existing code has been expanded to enable incorporation of a variety of unnatural amino acids at one or two nonadjacent sites within a protein by using nonsense or frameshift suppressor aminoacyl-tRNAs (aa-tRNAs) as adaptors. However, the suppressor strategy is inherently limited by compatibility with only a small subset of codons, by the ways such codons can be combined, and by variation in the efficiency of incorporation. Here, by preventing competing reactions with aa-tRNA synthetases, aa-tRNAs, and release factors during translation and by using nonsuppressor aa-tRNA substrates, we realize a potentially generalizable approach for template-encoded polymer synthesis that unmasks the substantially broader versatility of the core translation apparatus as a catalyst. We show that several adjacent, arbitrarily chosen sense codons can be completely reassigned to various unnatural amino acids according to de novo genetic codes by translating mRNAs into specific peptide analog polymers (peptidomimetics). Unnatural aa-tRNA substrates do not uniformly function as well as natural substrates, revealing important recognition elements for the translation apparatus. Genetic programming of peptidomimetic synthesis should facilitate mechanistic studies of translation and may ultimately enable the directed evolution of small molecules with desirable catalytic or pharmacological properties.

  16. Beyond the Ancestral Code: Towards a Model for Sociolinguistic Language Documentation

    Science.gov (United States)

    Childs, Tucker; Good, Jeff; Mitchell, Alice

    2014-01-01

    Most language documentation efforts focus on capturing lexico-grammatical information on individual languages. Comparatively little effort has been devoted to considering a language's sociolinguistic contexts. In parts of the world characterized by high degrees of multilingualism, questions surrounding the factors involved in language choice and…

  17. Preparation of computer codes for analyzing sensitivity coefficients of burnup characteristics (2) (Contract research, translated document)

    International Nuclear Information System (INIS)

    Hanaki, Hiroshi; Sanda, Toshio; Ohashi, Masahisa

    2008-10-01

    To develop nuclear design of LMFBR cores, they are important subjects of research and development to improve the accuracy in nuclear design of large LMFBR cores and to design highly efficient core more rationally. The adjusted nuclear cross-sections library has been made by being reflected the result of critical experiment of the JUPITER, etc. effectively as much as possible. And the distinct improvement of the accuracy in nuclear design of large LMFBR cores has been achieved. In the design of large LMFBR cores, however, it is important to accurately estimate not only nuclear characteristics, for example, reaction rate distribution and control rod worth but also burnup characteristics, for example, burnup reactivity loss, breeding ratio and so on. Therefore, it is thought to improve the prediction accuracy for burnup characteristics using many burnup data of 'Joyo' effectively. It is thought the best way to adjust cross sections using sensitivity coefficients of burnup characteristics to utilize burnup data of 'Joyo'. It is able to know the accuracy quantitatively for burnup characteristics of large LMFBR by analyzing the sensitivity coefficients. Therefore in this work computer codes for analyzing sensitivity coefficients of burnup characteristics had been prepared since 1992. In 1992 cross-section adjustment was done by using the data of 'Joyo' and the effect was studied. In this year the adequacy of the codes was studied with a view of applying of design of large LMFBR cores. The results are as follows: (1) The computer codes which could analyze sensitivity coefficients of burnup characteristics taking into consideration plural cycles and refueling were prepared, therefore it came of be able to adjust cross sections using burnup data and to estimate the accuracy for design of large LMFBR cores. The characteristics are not only burnup reactivity loss, breeding ratio but also number density, criticality, reactivity worth, reaction rate ratio, and reaction rate

  18. Documentation of probabilistic fracture mechanics codes used for reactor pressure vessels subjected to pressurized thermal shock loading: Parts 1 and 2. Final report

    International Nuclear Information System (INIS)

    Balkey, K.; Witt, F.J.; Bishop, B.A.

    1995-06-01

    Significant attention has been focused on the issue of reactor vessel pressurized thermal shock (PTS) for many years. Pressurized thermal shock transient events are characterized by a rapid cooldown at potentially high pressure levels that could lead to a reactor vessel integrity concern for some pressurized water reactors. As a result of regulatory and industry efforts in the early 1980's, a probabilistic risk assessment methodology has been established to address this concern. Probabilistic fracture mechanics analyses are performed as part of this methodology to determine conditional probability of significant flaw extension for given pressurized thermal shock events. While recent industry efforts are underway to benchmark probabilistic fracture mechanics computer codes that are currently used by the nuclear industry, Part I of this report describes the comparison of two independent computer codes used at the time of the development of the original U.S. Nuclear Regulatory Commission (NRC) pressurized thermal shock rule. The work that was originally performed in 1982 and 1983 to compare the U.S. NRC - VISA and Westinghouse (W) - PFM computer codes has been documented and is provided in Part I of this report. Part II of this report describes the results of more recent industry efforts to benchmark PFM computer codes used by the nuclear industry. This study was conducted as part of the USNRC-EPRI Coordinated Research Program for reviewing the technical basis for pressurized thermal shock (PTS) analyses of the reactor pressure vessel. The work focused on the probabilistic fracture mechanics (PFM) analysis codes and methods used to perform the PTS calculations. An in-depth review of the methodologies was performed to verify the accuracy and adequacy of the various different codes. The review was structured around a series of benchmark sample problems to provide a specific context for discussion and examination of the fracture mechanics methodology

  19. Agriculture and Food Processes Branch program summary document

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-06-01

    The work of the Agriculture and Food Processes Branch within the US DOE's Office of Industrial Programs is discussed and reviewed. The Branch is responsible for assisting the food and agricultural sectors of the economy in increasing their energy efficiency by cost sharing with industry the development and demonstration of technologies industry by itself would not develop because of a greater than normal risk factor, but have significant energy conservation benefits. This task is made more difficult by the diversity of agriculture and the food industry. The focus of the program is now on the development and demonstration of energy conservation technology in high energy use industry sectors and agricultural functions (e.g., sugar processing, meat processing, irrigation, and crop drying, high energy use functions common to many sectors of the food industry (e.g., refrigeration, drying, and evaporation), and innovative concepts (e.g., energy integrated farm systems. Specific projects within the program are summarized. (LCL)

  20. Process Document for the Conservation Competitive Bidding Pilot Program.

    Energy Technology Data Exchange (ETDEWEB)

    United States. Bonneville Power Administration.

    1990-09-01

    Bonneville Power Administration (Bonneville) is proposing to test competitive bidding for Conservation Resources to expand its existing resource acquisition capabilities. Competitive bidding may target specific types of electric end-uses or end-use sectors. It is a new acquisition approach through which Bonneville seeks to acquire resources that are not acquired through other existing or planned conservation programs. This proposal describes the conservation component of the all-source competitive acquisition approach that will be developed. It is expected that the combined resource acquisition effort will target about 100 average megawatts (aMW) as proposed in the 1990 Resource Program, although the exact amount has not yet been determined. Increasing the acquisition target will, to some extent, depend on whether the proposed pilot program is large enough to establish confidence in the approach.

  1. PBF/LOFT Lead Rod Test Program experiment predictions document

    International Nuclear Information System (INIS)

    Varacalle, D.J.; Cox, W.R.; Niebruegge, D.A.; Seiber, S.J.; Brake, T.E.; Driskell, W.E.; Nigg, D.W.; Tolman, E.L.

    1978-12-01

    The PBF/LOFT Lead Rod (LLR) Test Program is being conducted to provide experimental information on the behavior of nuclear fuel under normal and accident conditions in the Power Burst Facility (PBF) at the Idaho National Engineering Laboratory. The PBF/LLR tests are designed to simulate the test conditions for the LOFT Power Ascension Tests L2-3 through L2-5. The test program has been designed to provide a parametric evaluation of the LOFT fuel (center and peripheral modules) over a wide range of power. This report presents the experiment predictions for the three four-rod LOCA tests

  2. DOD/COCOM Water Security Program Strategy Document

    Science.gov (United States)

    2011-04-22

    treatment and disposal. DOD/COCOM Water Security Program Strategy 22 18. Toxic Minerals In regions where there are naturally occurring unsafe...surface hydrologic observations using remote sensing to provide data on precipitation, radiation, temperature, soil moisture, groundwater, snowcover...habitat alteration and aquaculture . 13. Centers for Disease Control (CDC) Works with partners throughout the nation and the world to monitor health

  3. High explosive programmed burn in the FLAG code

    Energy Technology Data Exchange (ETDEWEB)

    Mandell, D.; Burton, D.; Lund, C.

    1998-02-01

    The models used to calculate the programmed burn high-explosive lighting times for two- and three-dimensions in the FLAG code are described. FLAG uses an unstructured polyhedra grid. The calculations were compared to exact solutions for a square in two dimensions and for a cube in three dimensions. The maximum error was 3.95 percent in two dimensions and 4.84 percent in three dimensions. The high explosive lighting time model described has the advantage that only one cell at a time needs to be considered.

  4. Tank waste remediation system privatization infrastructure program requirements and document management process guide

    International Nuclear Information System (INIS)

    ROOT, R.W.

    1999-01-01

    This guide provides the Tank Waste Remediation System Privatization Infrastructure Program management with processes and requirements to appropriately control information and documents in accordance with the Tank Waste Remediation System Configuration Management Plan (Vann 1998b). This includes documents and information created by the program, as well as non-program generated materials submitted to the project. It provides appropriate approval/control, distribution and filing systems

  5. The FELIX program of experiments and code development

    International Nuclear Information System (INIS)

    Turner, L.R.

    1983-01-01

    An experimental program and test bed called FELIX (Fusion Electromagnetic Induction Experiment) which is under construction at Argonne National Laboratory is described. The facility includes the following facilities; (a) a sizable constant field, analogous to a tokamak toroidal field or the confining field of a mirror reactor, (b) a pulsed field with a sizable rate of change, analogous to a pulsed poloidal field or to the changing field of a plasma disruption, perpendicular to the constant field, and (c) a sufficiently large volume to assure that large, complex test pieces can be tested, and that the forces, torques, currents, and field distortions which are developed are large enough to be measured accurately. The development of the necessary computer codes and the experimental program are examined. (U.K.)

  6. ANS severe accident program overview ampersand planning document

    International Nuclear Information System (INIS)

    Taleyarkhan, R.P.

    1995-09-01

    The Advanced Neutron Source (ANS) severe accident document was developed to provide a concise and coherent mechanism for presenting the ANS SAP goals, a strategy satisfying these goals, a succinct summary of the work done to date, and what needs to be done in the future to ensure timely licensability. Guidance was received from various bodies [viz., panel members of the ANS severe accident workshop and safety review committee, Department of Energy (DOE) orders, Nuclear Regulatory Commission (NRC) requirements for ALWRs and advanced reactors, ACRS comments, world-wide trends] were utilized to set up the ANS-relevant SAS goals and strategy. An in-containment worker protection goal was also set up to account for the routine experimenters and other workers within containment. The strategy for achieving the goals is centered upon closing the severe accident issues that have the potential for becoming certification issues when assessed against realistic bounding events. Realistic bounding events are defined as events with an occurrency frequency greater than 10 -6 /y. Currently, based upon the level-1 probabilistic risk assessment studies, the realistic bounding events for application for issue closure are flow blockage of fuel element coolant channels, and rapid depressurization-related accidents

  7. Hanford Site guide for preparing and maintaining generator group pollution prevention program documentation

    International Nuclear Information System (INIS)

    Place, B.G.

    1998-01-01

    This document provides guidance to generator groups for preparing and maintaining documentation of Pollution Prevention Waste Minimization (P2/WMin) Program activities. The guidance is one of a hierarchical series that includes the Hanford Site Waste Minimization and Pollution Prevention Awareness Program Plan (DOE-RL, 1998a) and Prime contractor implementation plans describing programs required by Resource Conservation and Recovery Act of 1976 (RCRA) 3002(b) and 3005(h) (RCRA and EPA, 1994). Documentation guidance for the following five P2/WMin elements are discussed: Fiscal Year (FY) Goals; Budget and Staffing; Waste Minimization (WMin) Assessments (WMAs); Quarterly Pollution Prevention (P2) Reporting WMin Certification

  8. Hanford Site Guide for Preparing and Maintaining Fenerator Group Pollution Prevention Program Documentation

    International Nuclear Information System (INIS)

    PLACE, B.G.

    1999-01-01

    This document provides guidance to generator groups for preparing and maintaining documentation of Pollution Prevention/Waste Minimization (P2/WMin) Program activities. The guidance is one of a hierarchical series that includes the Hanford Site Waste Minimization and Pollution Prevention Awareness Program Plan (DOE-RL, 1998a) and Prime Contractor implementation plans describing programs required by Resource Conservation and Recovery Act of 1976 (RCRA) 3002(b) and (300501) (RCRA and EPA, 1994). Documentation guidance for the following five P2/WMin elements are discussed: Fiscal Year (FY) Goals; Budget and Staffing; Waste Minimization (WMinn ) Assessments (WMAs); Pollution Prevention (P2) Reporting; WMin Certification

  9. Documenting Program Outcomes of Relationship Education with Incarcerated Adults

    Directory of Open Access Journals (Sweden)

    Kate Taylor Harcourt

    2015-02-01

    Full Text Available The current study examined program outcomes for an understudied population of Relationship Education (RE participants: incarcerated men and women. In addition to relationship functioning, we examined a number of individual and parenting outcomes which had not previously been explored. In a sample of 453 adult inmates, we found improvements in (a trust, (b confidence in the relationship, (c intimacy, (d individual empowerment, (e conflict management, (f help-seeking attitudes, (g self-esteem, (h depression, (i global life stress, (j faulty relationship beliefs, and (k parenting efficacy. Tests of moderation by gender and race indicated minimal differences in change patterns between groups; however, we found a significant time by gender interaction on intimacy and a time by race interaction on parenting efficacy. Implications for research and practice are presented

  10. Development of an Auto-Validation Program for MARS Code Assessments

    International Nuclear Information System (INIS)

    Lee, Young Jin; Chung, Bub Dong

    2006-01-01

    MARS (Multi-dimensional Analysis of Reactor Safety) code is a best-estimate thermal hydraulic system analysis code developed at KAERI. It is important for a thermal hydraulic computer code to be assessed against theoretical and experimental data to verify and validate the performance and the integrity of the structure, models and correlations of the code. The code assessment efforts for complex thermal hydraulics code such as MARS code can be tedious, time-consuming and require large amount of human intervention in data transfer to see the results in graphic forms. Code developers produce many versions of a code during development and each version need to be verified for integrity. Thus, for MARS code developers, it is desirable to have an automatic way of carrying out the code assessment calculations. In the present work, an Auto-Validation program that carries out the code assessment efforts has been developed. The program uses the user supplied configuration file (with '.vv' extension) which contain commands to read input file, to execute the user selected MARS program, and to generate result graphs. The program can be useful if a same set of code assessments is repeated with different versions of the code. The program is written with the Delphi program language. The program runs under the Microsoft Windows environment

  11. Documentation of spectrom-32

    International Nuclear Information System (INIS)

    Callahan, G.D.; Fossum, A.F.; Svalstad, D.K.

    1989-01-01

    SPECTROM-32 is a finite element program for analyzing two-dimensional and axisymmetric inelastic thermomechanical problems related to the geological disposal of nuclear waste. The code is part of the SPECTROM series of special-purpose computer programs that are being developed by RE/SPEC Inc. to address many unique rock mechanics problems encountered in analyzing radioactive wastes stored in geologic formations. This document presents the theoretical basis for the mathematical models, the finite element formulation and solution procedure of the program, a description of the input data for the program, verification problems, and details about program support and continuing documentation. The computer code documentation is intended to satisfy the requirements and guidelines outlined in the document entitled Final Technical Position on Documentation of Computer Codes for High-Level Waste Management. The principal component models used in the program involve thermoelastic, thermoviscoelastic, thermoelastic-plastic, and thermoviscoplastic types of material behavior. Special material considerations provide for the incorporation of limited-tension material behavior and consideration of jointed material behavior. Numerous program options provide the capabilities for various boundary conditions, sliding interfaces, excavation, backfill, arbitrary initial stresses, multiple material domains, load incrementation, plotting database storage and access of results, and other features unique to the geologic disposal of radioactive wastes. Numerous verification problems that exercise many of the program options and illustrate the required data input and printed results are included in the documentation

  12. Canadian safeguards research and development in support of the IAEA program document outlining the various tasks which comprise the program

    International Nuclear Information System (INIS)

    1985-12-01

    Canada has established a safeguards research and development program, the purpose of which is to supplement the resources of the International Atomic Energy Agency. The program of support is a coordinated effort for the development and application of safeguards techniques and instruments to facilities safeguarded by the IAEA. This document sets forth those tasks which comprise the program

  13. A general multiblock Euler code for propulsion integration. Volume 1: Theory document

    Science.gov (United States)

    Chen, H. C.; Su, T. Y.; Kao, T. J.

    1991-01-01

    A general multiblock Euler solver was developed for the analysis of flow fields over geometrically complex configurations either in free air or in a wind tunnel. In this approach, the external space around a complex configuration was divided into a number of topologically simple blocks, so that surface-fitted grids and an efficient flow solution algorithm could be easily applied in each block. The computational grid in each block is generated using a combination of algebraic and elliptic methods. A grid generation/flow solver interface program was developed to facilitate the establishment of block-to-block relations and the boundary conditions for each block. The flow solver utilizes a finite volume formulation and an explicit time stepping scheme to solve the Euler equations. A multiblock version of the multigrid method was developed to accelerate the convergence of the calculations. The generality of the method was demonstrated through the analysis of two complex configurations at various flow conditions. Results were compared to available test data. Two accompanying volumes, user manuals for the preparation of multi-block grids (vol. 2) and for the Euler flow solver (vol. 3), provide information on input data format and program execution.

  14. Program strategy document for the nuclear materials. Transportation Technology Center (FY 80)

    International Nuclear Information System (INIS)

    Jefferson, R.M.

    1980-04-01

    The TTC's program is divided into four principal areas, Technology and Information Center, Systems Development, Technology, and Institutional Issues. These areas are broken into activities, elements, and subelements which are delineated in this document

  15. GetData Digitizing Program Code: Description, Testing, Training

    International Nuclear Information System (INIS)

    Taova, S.

    2013-01-01

    90 percents of compilation in our center is obtained by data digitizing. So we are rather interested in the development of different techniques of data digitizing. Plots containing a great amount of points and solid lines are most complicated for digitizing. From our point of view including to the Exfor-Digitizer procedures of automatic or semi-automatic digitizing will allow to simplify significantly this process. We managed to test some free available program codes. Program GETDATA Graph Digitizer (www.getdata- graph-digitizer.com) looks more suitable for our purposes. GetData Graph Digitizer is a program for digitizing graphs, plots and maps. Main features of GetData Graph Digitizer are: - supported graphics formats are TIFF, JPEG, BMP and PCX; - two algorithms for automatic digitizing; - convenient manual digitizing; - reorder tool for easy points reordering; - save/open workspace, which allows to save the work and return to it later; - obtained data can be exported to the clipboard; - export to the formats: TXT (text file), XLS (MS Excel), XML, DXF (AutoCAD) and EPS (PostScript). GetData Graph Digitizer includes two algorithms for automatic digitizing. Auto trace lines: This method is designed to digitize solid lines. Choose the starting point, and the program will trace the line, stopping at it's end. To trace the line use Operations =>Auto trace lines menu or context menu ('Auto trace lines' item). To choose starting point click left mouse button, or click right mouse button to additionally choose direction for line tracing. Digitize area: The second way is to set digitizing area. This method works for any type of lines, including dashed lines. Data points are set at the intersection of grid with the line. You can choose the type of grid (X grid or Y grid), and set the distance between grid lines. You can also make the grid be shifted in such a way, that it will pass through a specific X (or Y) value. To digitize area use Operations →Digitize area menu

  16. Report on a study of the feasibility of use of the COLUMN2 computer program in a probabilistic risk assessment code

    International Nuclear Information System (INIS)

    Hall, R.C.; Liew, S.K.

    1986-10-01

    This report contains the results of a feasibility study carried out on the COLUMN2 computer program to assess its potential for use in time-dependent probabilistic risk assessment code for radiological assessment purposes. COLUMN2 is a program which provides predictions of nuclide transport in a one-dimensional geosphere configuration using a simple Ksub(d) approach for sorption. A moving grid numerical solver is used and the program is therefore potentially capable of handling time-dependent parameters. The reported work covers aspects of code acquisition, loading, theory and structure, necessary code modifications and testing, the last aspect including two documented test cases from the COLUMN2 manual and verification tests derived from international comparison exercises. Recommendations are made as to the required code development of COLUMN2 in order that the code is capable of fulfilling its prime role as defined by the System Design Working Group in a pra code. (author)

  17. Spent Nuclear Fuel Project document control and Records Management Program Description

    International Nuclear Information System (INIS)

    MARTIN, B.M.

    2000-01-01

    The Spent Nuclear Fuel (SNF) Project document control and records management program, as defined within this document, is based on a broad spectrum of regulatory requirements, Department of Energy (DOE) and Project Hanford and SNF Project-specific direction and guidance. The SNF Project Execution Plan, HNF-3552, requires the control of documents and management of records under the auspices of configuration control, conduct of operations, training, quality assurance, work control, records management, data management, engineering and design control, operational readiness review, and project management and turnover. Implementation of the controls, systems, and processes necessary to ensure compliance with applicable requirements is facilitated through plans, directives, and procedures within the Project Hanford Management System (PHMS) and the SNF Project internal technical and administrative procedures systems. The documents cited within this document are those which directly establish or define the SNF Project document control and records management program. There are many peripheral documents that establish requirements and provide direction pertinent to managing specific types of documents that, for the sake of brevity and clarity, are not cited within this document

  18. Automatic Parallelization Tool: Classification of Program Code for Parallel Computing

    Directory of Open Access Journals (Sweden)

    Mustafa Basthikodi

    2016-04-01

    Full Text Available Performance growth of single-core processors has come to a halt in the past decade, but was re-enabled by the introduction of parallelism in processors. Multicore frameworks along with Graphical Processing Units empowered to enhance parallelism broadly. Couples of compilers are updated to developing challenges forsynchronization and threading issues. Appropriate program and algorithm classifications will have advantage to a great extent to the group of software engineers to get opportunities for effective parallelization. In present work we investigated current species for classification of algorithms, in that related work on classification is discussed along with the comparison of issues that challenges the classification. The set of algorithms are chosen which matches the structure with different issues and perform given task. We have tested these algorithms utilizing existing automatic species extraction toolsalong with Bones compiler. We have added functionalities to existing tool, providing a more detailed characterization. The contributions of our work include support for pointer arithmetic, conditional and incremental statements, user defined types, constants and mathematical functions. With this, we can retain significant data which is not captured by original speciesof algorithms. We executed new theories into the device, empowering automatic characterization of program code.

  19. [Prospective DRG coding : Improvement in cost-effectiveness and documentation quality of in-patient hospital care].

    Science.gov (United States)

    Geuss, S; Jungmeister, A; Baumgart, A; Seelos, R; Ockert, S

    2018-02-01

    In prospective reimbursement schemes a diagnosis-related group (DRG) is assigned to each case according to all coded diagnoses and procedures. This process can be conducted retrospectively after (DC) or prospectively during the hospitalization (PC). The use of PC offers advantages in terms of cost-effectiveness and documentation quality without impairing patient safety. A retrospective analysis including all DRG records and billing data from 2012 to 2015 of a surgical department was carried out. The use of PC was introduced into the vascular surgery unit (VS) in September 2013, while the remaining surgical units (RS) stayed with DC. Analysis focused on differences between VS and RS before and after introduction of PC. Characteristics of cost-effectiveness were earnings (EBIT-DA), length of stay (LOS), the case mix index (CMI) and the productivity in relation to the DRG benchmark (productivity index, PI). The number of recorded diagnoses/procedures (ND/NP) was an indicator for documentation quality. A total of 1703 cases with VS and 27,679 cases with RS were analyzed. After introduction of PC the EBIT-DA per case increased in VS but not in RS (+3342 Swiss francs vs. +84, respectively, p  0.05) and the LOS was more reduced in VS than in RS (-0.36 days vs. -0.03 days, p > 0.005). The PI increased in VS but decreased in RS (+0.131 vs. -0.032, p DRG benchmark, i. e. increasing the PI. The increasing ND indicates an improvement in documentation quality.

  20. Program prioritization system user requirements document for Gas Cooled Reactor Associates

    International Nuclear Information System (INIS)

    1981-01-01

    Efficient management of the national HTGR program requires the establishment of an information system that will facilitate a more rational allocation of resources and task prioritization consistent with program policies. The system described in this document provides a data analysis mechanism for processing top level summary status and planning information in a rapid, timely and selective manner. Data produced by the system can be used by management to provide a rational basis for prioritizing tasks, evaluating program changes and program planning regarding costs, schedules and overall program development logic. The purpose of this document is to delineate the program prioritization system (PPS) requirements for use as a guide to acquiring and implementing the system

  1. Omega documentation

    Energy Technology Data Exchange (ETDEWEB)

    Howerton, R.J.; Dye, R.E.; Giles, P.C.; Kimlinger, J.R.; Perkins, S.T.; Plechaty, E.F.

    1983-08-01

    OMEGA is a CRAY I computer program that controls nine codes used by LLNL Physical Data Group for: 1) updating the libraries of evaluated data maintained by the group (UPDATE); 2) calculating average values of energy deposited in secondary particles and residual nuclei (ENDEP); 3) checking the libraries for internal consistency, especially for energy conservation (GAMCHK); 4) producing listings, indexes and plots of the library data (UTILITY); 5) producing calculational constants such as group averaged cross sections and transfer matrices for diffusion and Sn transport codes (CLYDE); 6) producing and updating standard files of the calculational constants used by LLNL Sn and diffusion transport codes (NDFL); 7) producing calculational constants for Monte Carlo transport codes that use group-averaged cross sections and continuous energy for particles (CTART); 8) producing and updating standard files used by the LLNL Monte Carlo transport codes (TRTL); and 9) producing standard files used by the LANL pointwise Monte Carlo transport code MCNP (MCPOINT). The first four of these functions and codes deal with the libraries of evaluated data and the last five with various aspects of producing calculational constants for use by transport codes. In 1970 a series, called PD memos, of internal and informal memoranda was begun. These were intended to be circulated among the group for comment and then to provide documentation for later reference whenever questions arose about the subject matter of the memos. They have served this purpose and now will be drawn upon as source material for this more comprehensive report that deals with most of the matters covered in those memos.

  2. Omega documentation

    International Nuclear Information System (INIS)

    Howerton, R.J.; Dye, R.E.; Giles, P.C.; Kimlinger, J.R.; Perkins, S.T.; Plechaty, E.F.

    1983-08-01

    OMEGA is a CRAY I computer program that controls nine codes used by LLNL Physical Data Group for: 1) updating the libraries of evaluated data maintained by the group (UPDATE); 2) calculating average values of energy deposited in secondary particles and residual nuclei (ENDEP); 3) checking the libraries for internal consistency, especially for energy conservation (GAMCHK); 4) producing listings, indexes and plots of the library data (UTILITY); 5) producing calculational constants such as group averaged cross sections and transfer matrices for diffusion and Sn transport codes (CLYDE); 6) producing and updating standard files of the calculational constants used by LLNL Sn and diffusion transport codes (NDFL); 7) producing calculational constants for Monte Carlo transport codes that use group-averaged cross sections and continuous energy for particles (CTART); 8) producing and updating standard files used by the LLNL Monte Carlo transport codes (TRTL); and 9) producing standard files used by the LANL pointwise Monte Carlo transport code MCNP (MCPOINT). The first four of these functions and codes deal with the libraries of evaluated data and the last five with various aspects of producing calculational constants for use by transport codes. In 1970 a series, called PD memos, of internal and informal memoranda was begun. These were intended to be circulated among the group for comment and then to provide documentation for later reference whenever questions arose about the subject matter of the memos. They have served this purpose and now will be drawn upon as source material for this more comprehensive report that deals with most of the matters covered in those memos

  3. Documentation of Source Code.

    Science.gov (United States)

    1988-05-12

    the "load IC" menu option. A prompt will appear in the typescript window requesting the name of the knowledge base to be loaded. Enter...highlighted and then a prompt will appear in the typescript window. The prompt will be requesting the name of the file containing the message to be read in...the file name, the system will begin reading in the message. The listified message is echoed back in the typescript window. After that, the screen

  4. BLAKE - A Thermodynamics Code Based on TIGER: Users' Guide to the Revised Program

    National Research Council Canada - National Science Library

    Freedman, Eli

    1998-01-01

    .... This code, which was derived from the original version of SRI's TIGER program, is intended primarily for making calculations on the combustion products from conventional military and electrically...

  5. Antimicrobial Exposure Assessment Task Force II (AEATF II) Volume 5: Governing Document for a Multi-Year Antimicrobial Chemical Exposure Monitoring Program (interim draft document with changes)

    Science.gov (United States)

    This document describes the overall scope of the AEATF II program, demonstrates the need for additional human exposure monitoring data and explains the proposed methodology for the exposure monitoring studies proposed for conduct by the AEATF II.

  6. PC-based support programs coupled with the sets code for large fault tree analysis

    International Nuclear Information System (INIS)

    Hioki, K.; Nakai, R.

    1989-01-01

    Power Reactor and Nuclear Fuel Development Corporation (PNC) has developed four PC programs: IEIQ (Initiating Event Identification and Quantification), MODESTY (Modular Even Description for a Variety of Systems), FAUST (Fault Summary Tables Generation Program) and ETAAS (Event Tree Analysis Assistant System). These programs prepare the input data for the SETS (Set Equation Transformation System) code and construct and quantify event trees (E/Ts) using the output of the SETS code. The capability of these programs is described and some examples of the results are presented in this paper. With these PC programs and the SETS code, PSA can now be performed with more consistency and less manpower

  7. Monte Carlo codes and Monte Carlo simulator program

    International Nuclear Information System (INIS)

    Higuchi, Kenji; Asai, Kiyoshi; Suganuma, Masayuki.

    1990-03-01

    Four typical Monte Carlo codes KENO-IV, MORSE, MCNP and VIM have been vectorized on VP-100 at Computing Center, JAERI. The problems in vector processing of Monte Carlo codes on vector processors have become clear through the work. As the result, it is recognized that these are difficulties to obtain good performance in vector processing of Monte Carlo codes. A Monte Carlo computing machine, which processes the Monte Carlo codes with high performances is being developed at our Computing Center since 1987. The concept of Monte Carlo computing machine and its performance have been investigated and estimated by using a software simulator. In this report the problems in vectorization of Monte Carlo codes, Monte Carlo pipelines proposed to mitigate these difficulties and the results of the performance estimation of the Monte Carlo computing machine by the simulator are described. (author)

  8. Simplified modeling and code usage in the PASC-3 code system by the introduction of a programming environment

    International Nuclear Information System (INIS)

    Pijlgroms, B.J.; Oppe, J.; Oudshoorn, H.L.; Slobben, J.

    1991-06-01

    A brief description is given of the PASC-3 (Petten-AMPX-SCALE) Reactor Physics code system and associated UNIPASC work environment. The PASC-3 code system is used for criticality and reactor calculations and consists of a selection from the Oak Ridge National Laboratory AMPX-SCALE-3 code collection complemented with a number of additional codes and nuclear data bases. The original codes have been adapted to run under the UNIX operating system. The recommended nuclear data base is a complete 219 group cross section library derived from JEF-1 of which some benchmark results are presented. By the addition of the UNIPASC work environment the usage of the code system is greatly simplified. Complex chains of programs can easily be coupled together to form a single job. In addition, the model parameters can be represented by variables instead of literal values which enhances the readability and may improve the integrity of the code inputs. (author). 8 refs.; 6 figs.; 1 tab

  9. SLACINPT - a FORTRAN program that generates boundary data for the SLAC gun code

    International Nuclear Information System (INIS)

    Michel, W.L.; Hepburn, J.D.

    1982-03-01

    The FORTRAN program SLACINPT was written to simplify the preparation of boundary data for the SLAC gun code. In SLACINPT, the boundary is described by a sequence of straight line or arc segments. From these, the program generates the individual boundary mesh point data, required as input by the SLAC gun code

  10. 77 FR 11785 - Energy Conservation Program: Public Meeting and Availability of the Framework Document for High...

    Science.gov (United States)

    2012-02-28

    ... standards for high-intensity discharge (HID) lamps. Accordingly, DOE will hold a public meeting to discuss..._standards/commercial/high_intensity_discharge_lamps.html . DATES: The Department will hold a public meeting... Technologies Program, Mailstop EE-2J, Framework Document for High-Intensity Discharge Lamps, EERE-2010-BT-STD...

  11. A Case for Dynamic Reverse-code Generation to Debug Non-deterministic Programs

    Directory of Open Access Journals (Sweden)

    Jooyong Yi

    2013-09-01

    Full Text Available Backtracking (i.e., reverse execution helps the user of a debugger to naturally think backwards along the execution path of a program, and thinking backwards makes it easy to locate the origin of a bug. So far backtracking has been implemented mostly by state saving or by checkpointing. These implementations, however, inherently do not scale. Meanwhile, a more recent backtracking method based on reverse-code generation seems promising because executing reverse code can restore the previous states of a program without state saving. In the literature, there can be found two methods that generate reverse code: (a static reverse-code generation that pre-generates reverse code through static analysis before starting a debugging session, and (b dynamic reverse-code generation that generates reverse code by applying dynamic analysis on the fly during a debugging session. In particular, we espoused the latter one in our previous work to accommodate non-determinism of a program caused by e.g., multi-threading. To demonstrate the usefulness of our dynamic reverse-code generation, this article presents a case study of various backtracking methods including ours. We compare the memory usage of various backtracking methods in a simple but nontrivial example, a bounded-buffer program. In the case of non-deterministic programs such as this bounded-buffer program, our dynamic reverse-code generation outperforms the existing backtracking methods in terms of memory efficiency.

  12. The LIDES Coding Manual: A Document for Preparing and Analyzing Language Interaction Data Version 1.1--July 1999.

    Science.gov (United States)

    Barnett, Ruthanna; Codo, Eva; Eppler, Eva; Forcadell, Montse; Gardner-Chloros, Penelope; van Hout, Roeland; Moyer, Melissa; Torras, Maria Carme; Turell, Maria Teresa; Sebba, Mark; Starren, Marianne; Wensing, Sietse

    2000-01-01

    This manual is designed to help researchers new to the work of transcription and coding bilingual data or for individuals who have done familiar work but have a new set of data waiting to be transcribed and coded. Describes step-by-step a way of carrying out the transcription and coding that provides many useful facilities and makes it possible to…

  13. Program information architecture/document hierarchy. [Information Management Systems, it's components and rationale

    Energy Technology Data Exchange (ETDEWEB)

    Woods, T.W.

    1991-09-01

    The Nuclear Waste Management System (NWMS) Management Systems Improvement Strategy (MSIS) (DOE 1990) requires that the information within the computer program and information management system be ordered into a precedence hierarchy for consistency. Therefore, the US Department of Energy (DOE). Office of Civilian Radioactive Waste Management (OCRWM) requested Westinghouse Hanford Company to develop a plan for NWMS program information which the MSIS calls a document hierarchy. This report provides the results of that effort and describes the management system as a program information architecture.'' 3 refs., 3 figs.

  14. Assessment model validity document. NAMMU: A program for calculating groundwater flow and transport through porous media

    International Nuclear Information System (INIS)

    Cliffe, K.A.; Morris, S.T.; Porter, J.D.

    1998-05-01

    NAMMU is a computer program for modelling groundwater flow and transport through porous media. This document provides an overview of the use of the program for geosphere modelling in performance assessment calculations and gives a detailed description of the program itself. The aim of the document is to give an indication of the grounds for having confidence in NAMMU as a performance assessment tool. In order to achieve this the following topics are discussed. The basic premises of the assessment approach and the purpose of and nature of the calculations that can be undertaken using NAMMU are outlined. The concepts of the validation of models and the considerations that can lead to increased confidence in models are described. The physical processes that can be modelled using NAMMU and the mathematical models and numerical techniques that are used to represent them are discussed in some detail. Finally, the grounds that would lead one to have confidence that NAMMU is fit for purpose are summarised

  15. Detonation of high explosives in Lagrangian hydrodynamic codes using the programmed burn technique

    International Nuclear Information System (INIS)

    Berger, M.E.

    1975-09-01

    Two initiation methods were developed for improving the programmed burn technique for detonation of high explosives in smeared-shock Lagrangian hydrodynamic codes. The methods are verified by comparing the improved programmed burn with existing solutions in one-dimensional plane, converging, and diverging geometries. Deficiencies in the standard programmed burn are described. One of the initiation methods has been determined to be better for inclusion in production hydrodynamic codes

  16. Measuring coding intensity in the Medicare Advantage program.

    Science.gov (United States)

    Kronick, Richard; Welch, W Pete

    2014-01-01

    In 2004, Medicare implemented a system of paying Medicare Advantage (MA) plans that gave them greater incentive than fee-for-service (FFS) providers to report diagnoses. Risk scores for all Medicare beneficiaries 2004-2013 and Medicare Current Beneficiary Survey (MCBS) data, 2006-2011. Change in average risk score for all enrollees and for stayers (beneficiaries who were in either FFS or MA for two consecutive years). Prevalence rates by Hierarchical Condition Category (HCC). Each year the average MA risk score increased faster than the average FFS score. Using the risk adjustment model in place in 2004, the average MA score as a ratio of the average FFS score would have increased from 90% in 2004 to 109% in 2013. Using the model partially implemented in 2014, the ratio would have increased from 88% to 102%. The increase in relative MA scores appears to largely reflect changes in diagnostic coding, not real increases in the morbidity of MA enrollees. In survey-based data for 2006-2011, the MA-FFS ratio of risk scores remained roughly constant at 96%. Intensity of coding varies widely by contract, with some contracts coding very similarly to FFS and others coding much more intensely than the MA average. Underpinning this relative growth in scores is particularly rapid relative growth in a subset of HCCs. Medicare has taken significant steps to mitigate the effects of coding intensity in MA, including implementing a 3.4% coding intensity adjustment in 2010 and revising the risk adjustment model in 2013 and 2014. Given the continuous relative increase in the average MA risk score, further policy changes will likely be necessary.

  17. The Analysis of Heterogeneous Text Documents with the Help of the Computer Program NUD*IST

    Directory of Open Access Journals (Sweden)

    Christine Plaß

    2000-12-01

    Full Text Available On the basis of a current research project we discuss the use of the computer program NUD*IST for the analysis and archiving of qualitative documents. Our project examines the social evaluation of spectacular criminal offenses and we identify, digitize and analyze documents from the entire 20th century. Since public and scientific discourses are examined, the data of the project are extraordinarily heterogeneous: scientific publications, court records, newspaper reports, and administrative documents. We want to show how to transfer general questions into a systematic categorization with the assistance of NUD*IST. Apart from the functions, possibilities and limitations of the application of NUD*IST, concrete work procedures and difficulties encountered are described. URN: urn:nbn:de:0114-fqs0003211

  18. Documentation of spectrom-41

    International Nuclear Information System (INIS)

    Svalstad, D.K.

    1989-01-01

    SPECTROM-41 is a finite element heat transfer computer program developed to analyze thermal problems related to nuclear waste disposal. The code is part of the SPECTROM (Special Purpose Engineering Codes for Thermal/ROck Mechanics) series of special purpose finite element programs that are continually being developed by RE/SPEC Inc. (RSI) to address the many unique formations. This document presents the theoretical basis for the mathematical model, the finite element formulation of the program, and a description of the input data for the program, along with details about program support and continuing documentation. The documentation is intended to satisfy the requirements and guidelines outlined in NUREG-0856. The principal component model used in the programs based on Fourier's law of conductance. Numerous program options provide the capability of considering various boundary conditions, material stratification and anisotropy, and time-dependent heat generation that are characteristic of problems involving the disposal of nuclear waste in geologic formation. Numerous verification problems are included in the documentation in addition to highlights of past and ongoing verification and validation efforts. A typical repository problem is solving using SPECTROM-41 to demonstrate the use of the program in addressing problems related to the disposal of nuclear waste

  19. FLUKA A multi-particle transport code (program version 2005)

    CERN Document Server

    Ferrari, A; Fassò, A; Ranft, Johannes

    2005-01-01

    This report describes the 2005 version of the Fluka particle transport code. The first part introduces the basic notions, describes the modular structure of the system, and contains an installation and beginner’s guide. The second part complements this initial information with details about the various components of Fluka and how to use them. It concludes with a detailed history and bibliography.

  20. User's guide to GASPAR code (a computer program for calculating radiation exposure to man from routine air releases of nuclear reactor effluents). Technical report

    International Nuclear Information System (INIS)

    Eckerman, K.F.; Congel, F.J.; Roecklein, A.K.; Pasciak, W.J.

    1980-06-01

    The document is a user's guide for the GASPAR code, a computer program written for the evaluation of radiological impacts due to the release of radioactive material to the atmosphere during normal operation of light water reactors. The GASPAR code implements the radiological impact models of NRC Regulatory Guide 1.109, Revision 1, for atmospheric releases. The code is currently used by NRC in reactor licensing evaluations to estimate (1) the collective or population dose to the population within a 50-mile radius of a facility, (2) the total collective dose to the U.S. population, and (3) the maximum individual doses at selected locations in the vicinity of the plant

  1. Alternative Renewable Biomass Tracking Program Document under the Renewable Fuel Standard Program

    Science.gov (United States)

    The approval letters that EPA approves a company's biomass tracking program meeting all the requirements outlined in 40 CFR part 80.1454, including elements determined necessary to achieve the level of quality assurance required under the regulation list.

  2. Document Models

    Directory of Open Access Journals (Sweden)

    A.A. Malykh

    2017-08-01

    Full Text Available In this paper, the concept of locally simple models is considered. Locally simple models are arbitrarily complex models built from relatively simple components. A lot of practically important domains of discourse can be described as locally simple models, for example, business models of enterprises and companies. Up to now, research in human reasoning automation has been mainly concentrated around the most intellectually intensive activities, such as automated theorem proving. On the other hand, the retailer business model is formed from ”jobs”, and each ”job” can be modelled and automated more or less easily. At the same time, the whole retailer model as an integrated system is extremely complex. In this paper, we offer a variant of the mathematical definition of a locally simple model. This definition is intended for modelling a wide range of domains. Therefore, we also must take into account the perceptual and psychological issues. Logic is elitist, and if we want to attract to our models as many people as possible, we need to hide this elitism behind some metaphor, to which ’ordinary’ people are accustomed. As such a metaphor, we use the concept of a document, so our locally simple models are called document models. Document models are built in the paradigm of semantic programming. This allows us to achieve another important goal - to make the documentary models executable. Executable models are models that can act as practical information systems in the described domain of discourse. Thus, if our model is executable, then programming becomes redundant. The direct use of a model, instead of its programming coding, brings important advantages, for example, a drastic cost reduction for development and maintenance. Moreover, since the model is well and sound, and not dissolved within programming modules, we can directly apply AI tools, in particular, machine learning. This significantly expands the possibilities for automation and

  3. Generation of Efficient High-Level Hardware Code from Dataflow Programs

    OpenAIRE

    Siret , Nicolas; Wipliez , Matthieu; Nezan , Jean François; Palumbo , Francesca

    2012-01-01

    High-level synthesis (HLS) aims at reducing the time-to-market by providing an automated design process that interprets and compiles high-level abstraction programs into hardware. However, HLS tools still face limitations regarding the performance of the generated code, due to the difficulties of compiling input imperative languages into efficient hardware code. Moreover the hardware code generated by the HLS tools is usually target-dependant and at a low level of abstraction (i.e. gate-level...

  4. RECON: a computer program for analyzing repository economics. Documentation and user's manual

    International Nuclear Information System (INIS)

    Clark, L.L.; Cole, B.M.; McNair, G.W.; Schutz, M.E.

    1983-05-01

    From 1981 through 1983 the Pacific Northwest Laboratory has been developing a computer model named RECON to calculate repository costs from parametric data input. The objective of the program has been to develop the capability to evalute the effect on costs of changes in repository design parameters and operating scenario assumptions. This report documents the development of the model through March of 1983. Included in the report are: (1) descriptions of model development and the underlying equations, assumptions and definitions; (2) descriptions of data input either using card images or an interactive data input program; and (3) detailed listings of the program and definitions of program variables. Cost estimates generated using the model have been verified against independent estimates and good agreement has been obtained

  5. RECON: a computer program for analyzing repository economics. Documentation and user's manual. Revision 1

    International Nuclear Information System (INIS)

    Clark, L.L.; Schutz, M.E.; Luksic, A.T.

    1985-07-01

    From 1981 through 1984 the Pacific Northwest Laboratory has been developing a computer model named RECON to calculate repository costs from parametric data input. The objective of the program has been to develop the capability to evaluate the effect on costs of changes in repository design parameters and operating scenario assumptions. This report documents the development of the model through September of 1984. Included in the report are: (1) descriptions of model development and the underlying equations, assumptions and definitions; (2) descriptions of data input using either card images or an interactive data input program; and (3) detailed listings of the program and definitions of program variables. Cost estimates generated using the model have been verified against independent estimates and good agreement has been obtained. 2 refs

  6. The standard calibration instrument automation system for the atomic absorption spectrophotometer. Part 3: Program documentation

    Science.gov (United States)

    Ryan, D. P.; Roth, G. S.

    1982-04-01

    Complete documentation of the 15 programs and 11 data files of the EPA Atomic Absorption Instrument Automation System is presented. The system incorporates the following major features: (1) multipoint calibration using first, second, or third degree regression or linear interpolation, (2) timely quality control assessments for spiked samples, duplicates, laboratory control standards, reagent blanks, and instrument check standards, (3) reagent blank subtraction, and (4) plotting of calibration curves and raw data peaks. The programs of this system are written in Data General Extended BASIC, Revision 4.3, as enhanced for multi-user, real-time data acquisition. They run in a Data General Nova 840 minicomputer under the operating system RDOS, Revision 6.2. There is a functional description, a symbol definitions table, a functional flowchart, a program listing, and a symbol cross reference table for each program. The structure of every data file is also detailed.

  7. RGENDF - An interface program between the NJOY code and codes using multigroup cross-sections

    International Nuclear Information System (INIS)

    Chalhoub, E.S.; Anaf, J.

    1988-02-01

    An interface program for reformatting multigroup cross-section libraries generated by NJOY into ENDF/B-V format and the EXPANDA, PFCOND and COMPAR input formats is presented. (author). 7 refs, 1 fig., 1 tab

  8. Process Model Improvement for Source Code Plagiarism Detection in Student Programming Assignments

    Science.gov (United States)

    Kermek, Dragutin; Novak, Matija

    2016-01-01

    In programming courses there are various ways in which students attempt to cheat. The most commonly used method is copying source code from other students and making minimal changes in it, like renaming variable names. Several tools like Sherlock, JPlag and Moss have been devised to detect source code plagiarism. However, for larger student…

  9. Automated Source Code Analysis to Identify and Remove Software Security Vulnerabilities: Case Studies on Java Programs

    OpenAIRE

    Natarajan Meghanathan

    2013-01-01

    The high-level contribution of this paper is to illustrate the development of generic solution strategies to remove software security vulnerabilities that could be identified using automated tools for source code analysis on software programs (developed in Java). We use the Source Code Analyzer and Audit Workbench automated tools, developed by HP Fortify Inc., for our testing purposes. We present case studies involving a file writer program embedded with features for password validation, and ...

  10. PENNON: A code for convex nonlinear and semidefinite programming

    Czech Academy of Sciences Publication Activity Database

    Kočvara, Michal; Stingl, M.

    2003-01-01

    Roč. 18, č. 3 (2003), s. 317-333 ISSN 1055-6788 R&D Projects: GA ČR GA201/00/0080 Grant - others:BMBF(DE) 03ZOM3ER Institutional research plan: CEZ:AV0Z1075907 Keywords : convex programming * semidefinite programming * large-scale problems Subject RIV: BB - Applied Statistics, Operational Research Impact factor: 0.306, year: 2003

  11. International Code Assessment and Applications Program: Summary of code assessment studies concerning RELAP5/MOD2, RELAP5/MOD3, and TRAC-B

    International Nuclear Information System (INIS)

    Schultz, R.R.

    1993-12-01

    Members of the International Code Assessment Program (ICAP) have assessed the US Nuclear Regulatory Commission (USNRC) advanced thermal-hydraulic codes over the past few years in a concerted effort to identify deficiencies, to define user guidelines, and to determine the state of each code. The results of sixty-two code assessment reviews, conducted at INEL, are summarized. Code deficiencies are discussed and user recommended nodalizations investigated during the course of conducting the assessment studies and reviews are listed. All the work that is summarized was done using the RELAP5/MOD2, RELAP5/MOD3, and TRAC-B codes

  12. Object-Oriented Programming in the Development of Containment Analysis Code

    International Nuclear Information System (INIS)

    Han, Tae Young; Hong, Soon Joon; Hwang, Su Hyun; Lee, Byung Chul; Byun, Choong Sup

    2009-01-01

    After the mid 1980s, the new programming concept, Object-Oriented Programming (OOP), was introduced and designed, which has the features such as the information hiding, encapsulation, modularity and inheritance. These offered much more convenient programming paradigm to code developers. The OOP concept was readily developed into the programming language as like C++ in the 1990s and is being widely used in the modern software industry. In this paper, we show that the OOP concept is successfully applicable to the development of safety analysis code for containment and propose the more explicit and easy OOP design for developers

  13. U.S. Department of Energy, Carlsbad Area Office quality assurance program document. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-04-01

    Mission of the Carlsbad Area Office (CAO) is to protect human health and the environment by opening and operating the Waste Isolation Pilot Plant (WIPP) for safe disposal of TRU waste, and establishing an effective system for management of TRU waste from generation to disposal. To help in fulfilling this mission and to ensure that risks and environmental impacts are identified and minimized, and that safety, reliability, and performance are optimized, CAO`s policy is to establish and maintain an effective quality assurance (QA) program that supports compliance with applicable Federal, State, and local regulations, and DOE orders and requirements. This document establishes QA program requirements for all programs, projects, and activities sponsored by CAO.

  14. Lex genetica: the law and ethics of programming biological code.

    Science.gov (United States)

    Burk, Dan L

    2002-01-01

    Recent advances in genetic engineering now allow the design of programmable biological artifacts. Such programming may include usage constraints that will alter the balance of ownership and control for biotechnology products. Similar changes have been analyzed in the context of digital content management systems, and while this previous work is useful in analyzing issues related to biological programming, the latter technology presents new conceptual problems that require more comprehensive evaluation of the interplay between law and technologically embedded values. In particular, the ability to embed contractual terms in technological artifacts now requires a re-examination of disclosure and consent in transactions involving such artifacts.

  15. UNSAT-H Version 1.0: unsaturated flow code documentation and applications for the Hanford Site

    International Nuclear Information System (INIS)

    Fayer, M.J.; Gee, G.W.; Jones, T.L.

    1986-08-01

    Waste mangement practices at the Hanford Site have relied havily on near-surface burial. Predicting the future performance of any burial site in terms of the migration of buried contaminants requires a model capable of simulating water flow in the unsaturated soils above the buried waste. The model currently being developed to meet this need is UNSAT-H, which was developed at Pacific Northwest Laboratory for assessing the water dynamics of near-surface waste-disposal sites at the Hanfrod Site. The code will primarily be used to predict deep drainage (i.e., recharge) as a function of environmental conditions such as climate, soil type, and vegetation. UNSAT-H will also simulate various waste-management practices such as placing surface barriers over waste sites. UNSAT-H is a one-dimensional model that simulates the dynamics processes of infiltration, drainage, redistribution, surface evaporation, and uptake of water from soil by plants. UNSAT-H is designed to utilize two auxiliary codes. These codes are DATAINH, which is used to process the input data, and DATAOUT, which is used to process the UNSAT-H output. Operation of the code requires three separate steps. First, the problem to be simulated must be conceptualized in terms of boundary conditions, available data, and soil properties. Next, the data must be correctly formatted for input. Finally, the unput data must be processed, UNSAT-H run, and the output data processed for analysis. This report includes three examples of code use. In the first example, a benchmark test case is run in which the results of UNSAT-H simulations of infiltration are compared with an analytical solution and a numerical solution. The comparisons show excellent agreement for the specific test case, and this agreement provides vertification of the infiltration portion of the UNSAT-H code. The other two examples of code use are a simulation of a layered soil and one of plant transpiration

  16. Electronic document management system analysis report and system plan for the Environmental Restoration Program

    International Nuclear Information System (INIS)

    Frappaolo, C.

    1995-09-01

    Lockheed Martin Energy Systems, Inc. (LMES) has established and maintains Document Management Centers (DMCs) to support Environmental Restoration Program (ER) activities undertaken at three Oak Ridge facilities: Oak Ridge National Laboratory, Oak Ridge K-25 Site, Oak Ridge Y-12 Plant; and two sister sites: Portsmouth Gaseous Diffusion Plant in Portsmouth, Ohio, and Paducah Gaseous Diffusion Plant in Paducah, Kentucky. The role of the DMCs is to receive, store, retrieve, and properly dispose of records. In an effort to make the DMCs run more efficiently and to more proactively manage the records' life cycles from cradle to grave, ER has decided to investigate ways in which Electronic Document Management System (EDMS) technologies can be used to redefine the DMCs and their related processes. Specific goals of this study are tightening control over the ER documents, establishing and enforcing record creation and retention procedures, speeding up access to information, and increasing the accessibility of information. A working pilot of the solution is desired within the next six months. Based on a series of interviews conducted with personnel from each of the DMCs, key management, and individuals representing related projects, it is recommended that ER utilize document management, full-text retrieval, and workflow technologies to improve and automate records management for the ER program. A phased approach to solution implementation is suggested starting with the deployment of an automated storage and retrieval system at Portsmouth. This should be followed with a roll out of the system to the other DMCs, the deployment of a workflow-enabled authoring system at Portsmouth, and a subsequent roll out of this authoring system to the other sites

  17. Python Source Code Plagiarism Attacks on Introductory Programming Course Assignments

    Science.gov (United States)

    Karnalim, Oscar

    2017-01-01

    This paper empirically enlists Python plagiarism attacks that have been found on Introductory Programming course assignments for undergraduate students. According to our observation toward 400 plagiarism-suspected cases, there are 35 plagiarism attacks that have been conducted by students. It starts with comment & whitespace modification as…

  18. Atlas C++ Coding Standard Specification

    CERN Document Server

    Albrand, S; Barberis, D; Bosman, M; Jones, B; Stavrianakou, M; Arnault, C; Candlin, D; Candlin, R; Franck, E; Hansl-Kozanecka, Traudl; Malon, D; Qian, S; Quarrie, D; Schaffer, R D

    2001-01-01

    This document defines the ATLAS C++ coding standard, that should be adhered to when writing C++ code. It has been adapted from the original "PST Coding Standard" document (http://pst.cern.ch/HandBookWorkBook/Handbook/Programming/programming.html) CERN-UCO/1999/207. The "ATLAS standard" comprises modifications, further justification and examples for some of the rules in the original PST document. All changes were discussed in the ATLAS Offline Software Quality Control Group and feedback from the collaboration was taken into account in the "current" version.

  19. Program Management at the National Nuclear Security Administration Office of Defense Nuclear Security: A Review of Program Management Documents and Underlying Processes

    International Nuclear Information System (INIS)

    Madden, Michael S.

    2010-01-01

    The scope of this paper is to review the National Nuclear Security Administration Office of Defense Nuclear Security (DNS) program management documents and to examine the underlying processes. The purpose is to identify recommendations for improvement and to influence the rewrite of the DNS Program Management Plan (PMP) and the documentation supporting it. As a part of this process, over 40 documents required by DNS or its stakeholders were reviewed. In addition, approximately 12 other documents produced outside of DNS and its stakeholders were reviewed in an effort to identify best practices. The complete list of documents reviewed is provided as an attachment to this paper.

  20. Use of Data to Develop a Code Blue Training Program

    Science.gov (United States)

    2017-01-28

    training program and create a sense of urgency for change. 3. Describe methods for linking learning objectives to performance gaps utilizing high...IMSH2017 .. .... _ . \\ "~ - ’ Enlisting Buy-In • Garner Leadership Support \\ ’(C>’>f ,... ... ,. -- ~ • Create a sense of urgency - I {’ . J...Include Data • ve1lows: Detail oriented; enjoy structure; punctual https://www.paceorg.com/ Creating a Sense of Urgency ... http

  1. IAEA program for the preparation of safety codes and guides for nuclear power plants

    International Nuclear Information System (INIS)

    1975-01-01

    On the 13th of September, 1974, the IAEA Governors' Council has given its consent to the programme for the establishment of safety codes and guides (annex VII to IAEA document G.C. (XVIII/526)). The programme envisages the establishment of one code of practice for each of the issues governmental organization, siting, design, operation and quality assurance and also of about 50 safety guides between 1975 and 1980. These codes will contain the minimum requirements for the safety of the nuclear power stations, their systems and components. The guides will recommend methods to achieve the aims stated in the codes. It is the purpose of these IAEA activities to provide recommendations and guiding rules which may serve as standards for the assessment of the safety of nuclear power stations for all nations which may become participants in the peaceful use of nuclear energy within the next few years. (orig./AK) [de

  2. TMAP/Mod 1: Tritium Migration Analysis Program code description and user's manual

    International Nuclear Information System (INIS)

    Merrill, B.J.; Jones, J.L.; Holland, D.F.

    1986-01-01

    The Tritium Migration Analysis Program (TMAP) has been developed by the Fusion Safety Program of EG and G Idaho, Inc., at the Idaho National Engineering Laboratory (INEL) as a safety analysis code to analyze tritium loss from fusion systems during normal operation and under accident conditions. TMAP is a one-dimensional code that determines tritium movement and inventories in a system of interconnected enclosures and wall structures. In addition, the thermal response of structures is modeled to provide temperature information required for calculations of tritium movement. The program is written in FORTRAN 4 and has been implemented on the National Magnetic Fusion Energy Computing Center (NMFECC)

  3. Remodularizing Java Programs for Improved Locality of Feature Implementations in Source Code

    DEFF Research Database (Denmark)

    Olszak, Andrzej; Jørgensen, Bo Nørregaard

    2011-01-01

    Explicit traceability between features and source code is known to help programmers to understand and modify programs during maintenance tasks. However, the complex relations between features and their implementations are not evident from the source code of object-oriented Java programs....... Consequently, the implementations of individual features are difficult to locate, comprehend, and modify in isolation. In this paper, we present a novel remodularization approach that improves the representation of features in the source code of Java programs. Both forward- and reverse restructurings...... are supported through on-demand bidirectional restructuring between feature-oriented and object-oriented decompositions. The approach includes a feature location phase based of tracing program execution, a feature representation phase that reallocates classes into a new package structure based on single...

  4. Orbitmpi Documentation

    International Nuclear Information System (INIS)

    Lowe, Lisa L.

    2000-01-01

    Orbitmpi is a parallelized version of Roscoe White's Orbit code. The code has been parallelized using MPI, which makes it portable to many types of machines. The guidelines used for the parallelization were to increase code performance with minimal changes to the code's original structure. This document gives a general description of how the parallel sections of the code run. It discusses the changes made to the original code and comments on the general procedure for future additions to Orbitmpi, as well as describing the effects of a parallelized random number generator on the code's output. Finally, the scaling results from Hecate and from Puffin are presented. Hecate is a 64-processor Origin 2000 machine, with MIPS R12000 processors and 16GB of memory, and Puffin is a PC cluster with 9 dual-processor 450 MHz Pentium III (18 processors max.), with 100Mbits ethernet communication

  5. Summary Report for ASC L2 Milestone #4782: Assess Newly Emerging Programming and Memory Models for Advanced Architectures on Integrated Codes

    Energy Technology Data Exchange (ETDEWEB)

    Neely, J. R. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Hornung, R. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Black, A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Robinson, P. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2014-09-29

    This document serves as a detailed companion to the powerpoint slides presented as part of the ASC L2 milestone review for Integrated Codes milestone #4782 titled “Assess Newly Emerging Programming and Memory Models for Advanced Architectures on Integrated Codes”, due on 9/30/2014, and presented for formal program review on 9/12/2014. The program review committee is represented by Mike Zika (A Program Project Lead for Kull), Brian Pudliner (B Program Project Lead for Ares), Scott Futral (DEG Group Lead in LC), and Mike Glass (Sierra Project Lead at Sandia). This document, along with the presentation materials, and a letter of completion signed by the review committee will act as proof of completion for this milestone.

  6. Identification and Analysis of Critical Gaps in Nuclear Fuel Cycle Codes Required by the SINEMA Program

    International Nuclear Information System (INIS)

    Miron, Adrian; Valentine, Joshua; Christenson, John; Hawwari, Majd; Bhatt, Santosh; Dunzik-Gougar, Mary Lou; Lineberry, Michael

    2009-01-01

    The current state of the art in nuclear fuel cycle (NFC) modeling is an eclectic mixture of codes with various levels of applicability, flexibility, and availability. In support of the advanced fuel cycle systems analyses, especially those by the Advanced Fuel Cycle Initiative (AFCI), University of Cincinnati in collaboration with Idaho State University carried out a detailed review of the existing codes describing various aspects of the nuclear fuel cycle and identified the research and development needs required for a comprehensive model of the global nuclear energy infrastructure and the associated nuclear fuel cycles. Relevant information obtained on the NFC codes was compiled into a relational database that allows easy access to various codes' properties. Additionally, the research analyzed the gaps in the NFC computer codes with respect to their potential integration into programs that perform comprehensive NFC analysis.

  7. Identification and Analysis of Critical Gaps in Nuclear Fuel Cycle Codes Required by the SINEMA Program

    Energy Technology Data Exchange (ETDEWEB)

    Adrian Miron; Joshua Valentine; John Christenson; Majd Hawwari; Santosh Bhatt; Mary Lou Dunzik-Gougar: Michael Lineberry

    2009-10-01

    The current state of the art in nuclear fuel cycle (NFC) modeling is an eclectic mixture of codes with various levels of applicability, flexibility, and availability. In support of the advanced fuel cycle systems analyses, especially those by the Advanced Fuel Cycle Initiative (AFCI), Unviery of Cincinnati in collaboration with Idaho State University carried out a detailed review of the existing codes describing various aspects of the nuclear fuel cycle and identified the research and development needs required for a comprehensive model of the global nuclear energy infrastructure and the associated nuclear fuel cycles. Relevant information obtained on the NFC codes was compiled into a relational database that allows easy access to various codes' properties. Additionally, the research analyzed the gaps in the NFC computer codes with respect to their potential integration into programs that perform comprehensive NFC analysis.

  8. Shader programming for computational arts and design: A comparison between creative coding frameworks

    OpenAIRE

    Gomez, Andres Felipe; Colubri, Andres; Charalambos, Jean Pierre

    2016-01-01

    We describe an Application Program Interface (API) that facilitates the use of GLSL shaders in computational design, interactive arts, and data visualization. This API was first introduced in the version 2.0 of Processing, a programming language and environment widely used for teaching and production in the context of media arts and design, and has been recently completed in the 3.0 release. It aims to incorporate low-level shading programming into code-based design, by int...

  9. Contributions of the ORNL piping program to nuclear piping design codes and standards

    International Nuclear Information System (INIS)

    Moore, S.E.

    1975-11-01

    The ORNL Piping Program was conceived and established to develop basic information on the structural behavior of nuclear power plant piping components and to prepare this information in forms suitable for use in design analysis and codes and standards. One of the objectives was to develop and qualify stress indices and flexibility factors for direct use in Code-prescribed design analysis methods. Progress in this area is described

  10. Description of computer code PRINS, Program for Interpreting Gamma Spectra, developed at ENEA

    Energy Technology Data Exchange (ETDEWEB)

    Borsari, R. [ENEA, Centro Ricerche `E. Clementel`, Bologna (Italy). Dip. Energia

    1995-11-01

    The computer code PRINS, program for interpreting gamma Spectra, has been developed in collaboration with CENG/SECC (Centre Etude Nucleaire Grenoble / Service Etude Comportement du Combustible). Later it has been updated and improved at ENEA. Properties of the PRINS code are: (1) A powerful algorithm to locate the peaks; (2) An accurate evaluation of the errors; (3) Possibility of an automatic channels-energy calibration.

  11. Description of computer code PRINS, Program for Interpreting Gamma Spectra, developed at ENEA

    International Nuclear Information System (INIS)

    Borsari, R.

    1995-12-01

    The computer code PRINS, PRogram for INterpreting gamma Spectra, has been developed in collaboration with CENG/SECC (Centre Etude Nucleaire Grenoble / Service Etude Comportement du Combustible). Later it has been updated and improved at ENEA. Properties of the PRINS code are: I) A powerful algorithm to locate the peaks; 2) An accurate evaluation of the errors; 3) Possibility of an automatic channels-energy calibration

  12. Federal Logistics Information System (FLIS) Procedures Manual. Volume 8. Document Identifier Code Input/Output Formats (Fixed Length)

    Science.gov (United States)

    1994-07-01

    REQUIRED MIX OF SEGMENTS OR INDIVIDUAL DATA ELEMENTS TO BE EXTRACTED. IN SEGMENT R ON AN INTERROGATION TRANSACTION (LTI), DATA RECORD NUMBER (DRN 0950) ONLY...and zation and Marketing input DICs. insert the Continuation Indicator Code (DRN 8555) in position 80 of this record. Maximum of OF The assigned NSN...for Procurement KFR, File Data Minus Security Classified Characteristics Data KFC 8.5-2 DoD 4100.39-M Volume 8 CHAPTER 5 ALPHABETIC INDEX OF DIC

  13. Annual coded wire tag program, Washington: Missing production groups. Annual report for 1998

    International Nuclear Information System (INIS)

    Byrne, J.; Fuss, H.

    1999-01-01

    The Bonneville Power Administration (BPA) funds the ''Annual Coded Wire Tag Program--Missing Production Groups for Columbia River Hatcheries'' project. The WDFW project has three main objectives: (1) coded-wire tag at least one production group of each species at each Columbia Basin hatchery to enable evaluation of survival and catch distribution over time, (2) recover coded-wire tags from the snouts of fish tagged under objective 1 and estimate survival, contribution, and stray rates for each group, and (3) report the findings under objective 2 for all broods of chinook, and coho released from WDFW Columbia Basin hatcheries

  14. AutoBayes/CC: Combining Program Synthesis with Automatic Code Certification: System Description

    Science.gov (United States)

    Whalen, Michael; Schumann, Johann; Fischer, Bernd; Clancy, Daniel (Technical Monitor)

    2002-01-01

    Code certification is a lightweight approach to formally demonstrate software quality. It concentrates on aspects of software quality that can be defined and formalized via properties, e.g., operator safety or memory safety. Its basic idea is to require code producers to provide formal proofs that their code satisfies these quality properties. The proofs serve as certificates which can be checked independently, by the code consumer or by certification authorities, e.g., the FAA. It is the idea underlying such approaches as proof-carrying code [6]. Code certification can be viewed as a more practical version of traditional Hoare-style program verification. The properties to be verified are fairly simple and regular so that it is often possible to use an automated theorem prover to automatically discharge all emerging proof obligations. Usually, however, the programmer must still splice auxiliary annotations (e.g., loop invariants) into the program to facilitate the proofs. For complex properties or larger programs this quickly becomes the limiting factor for the applicability of current certification approaches.

  15. User Guide and Documentation for Five MODFLOW Ground-Water Modeling Utility Programs

    Science.gov (United States)

    Banta, Edward R.; Paschke, Suzanne S.; Litke, David W.

    2008-01-01

    This report documents five utility programs designed for use in conjunction with ground-water flow models developed with the U.S. Geological Survey's MODFLOW ground-water modeling program. One program extracts calculated flow values from one model for use as input to another model. The other four programs extract model input or output arrays from one model and make them available in a form that can be used to generate an ArcGIS raster data set. The resulting raster data sets may be useful for visual display of the data or for further geographic data processing. The utility program GRID2GRIDFLOW reads a MODFLOW binary output file of cell-by-cell flow terms for one (source) model grid and converts the flow values to input flow values for a different (target) model grid. The spatial and temporal discretization of the two models may differ. The four other utilities extract selected 2-dimensional data arrays in MODFLOW input and output files and write them to text files that can be imported into an ArcGIS geographic information system raster format. These four utilities require that the model cells be square and aligned with the projected coordinate system in which the model grid is defined. The four raster-conversion utilities are * CBC2RASTER, which extracts selected stress-package flow data from a MODFLOW binary output file of cell-by-cell flows; * DIS2RASTER, which extracts cell-elevation data from a MODFLOW Discretization file; * MFBIN2RASTER, which extracts array data from a MODFLOW binary output file of head or drawdown; and * MULT2RASTER, which extracts array data from a MODFLOW Multiplier file.

  16. Summary of computational support and general documentation for computer code (GENTREE) used in Office of Nuclear Waste Isolation Pilot Salt Site Selection Project

    International Nuclear Information System (INIS)

    Beatty, J.A.; Younker, J.L.; Rousseau, W.F.; Elayat, H.A.

    1983-01-01

    A Decision Tree Computer Model was adapted for the purposes of a Pilot Salt Site Selection Project conducted by the Office of Nuclear Waste Isolation (ONWI). A deterministic computer model was developed to structure the site selection problem with submodels reflecting the five major outcome categories (Cost, Safety, Delay, Environment, Community Impact) to be evaluated in the decision process. Time-saving modifications were made in the tree code as part of the effort. In addition, format changes allowed retention of information items which are valuable in directing future research and in isolation of key variabilities in the Site Selection Decision Model. The deterministic code was linked to the modified tree code and the entire program was transferred to the ONWI-VAX computer for future use by the ONWI project

  17. NRC review of Electric Power Research Institute's Advanced Light Reactor Utility Requirements Document - Program summary, Project No. 669

    International Nuclear Information System (INIS)

    1992-08-01

    The staff of the US Nuclear Regulatory Commission has prepared Volume 1 of a safety evaluation report (SER), ''NRC Review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document -- Program Summary,'' to document the results of its review of the Electric Power Research Institute's ''Advanced Light Water Reactor Utility Requirements Document.'' This SER provides a discussion of the overall purpose and scope of the Requirements Document, the background of the staff's review, the review approach used by the staff, and a summary of the policy and technical issues raised by the staff during its review

  18. ExactPack Documentation

    Energy Technology Data Exchange (ETDEWEB)

    Singleton, Robert Jr. [Los Alamos National Laboratory; Israel, Daniel M. [Los Alamos National Laboratory; Doebling, Scott William [Los Alamos National Laboratory; Woods, Charles Nathan [Los Alamos National Laboratory; Kaul, Ann [Los Alamos National Laboratory; Walter, John William Jr [Los Alamos National Laboratory; Rogers, Michael Lloyd [Los Alamos National Laboratory

    2016-05-09

    For code verification, one compares the code output against known exact solutions. There are many standard test problems used in this capacity, such as the Noh and Sedov problems. ExactPack is a utility that integrates many of these exact solution codes into a common API (application program interface), and can be used as a stand-alone code or as a python package. ExactPack consists of python driver scripts that access a library of exact solutions written in Fortran or Python. The spatial profiles of the relevant physical quantities, such as the density, fluid velocity, sound speed, or internal energy, are returned at a time specified by the user. The solution profiles can be viewed and examined by a command line interface or a graphical user interface, and a number of analysis tools and unit tests are also provided. We have documented the physics of each problem in the solution library, and provided complete documentation on how to extend the library to include additional exact solutions. ExactPack’s code architecture makes it easy to extend the solution-code library to include additional exact solutions in a robust, reliable, and maintainable manner.

  19. Utility residential new construction programs: Going beyond the code. A report from the Database on Energy Efficiency Programs (DEEP) Project

    Energy Technology Data Exchange (ETDEWEB)

    Vine, E.

    1995-08-01

    Based on an evaluation of 10 residential new construction programs, primarily sponsored by investor-owned utilities in the United States, we find that many of these programs are in dire straits and are in danger of being discontinued because current inclusion of only direct program effects leads to the conclusion that they are not cost-effective. We believe that the cost-effectiveness of residential new construction programs can be improved by: (1) promoting technologies and advanced building design practices that significantly exceed state and federal standards; (2) reducing program marketing costs and developing more effective marketing strategies; (3) recognizing the role of these programs in increasing compliance with existing state building codes; and (4) allowing utilities to obtain an ``energy-savings credit`` from utility regulators for program spillover (market transformation) impacts. Utilities can also leverage their resources in seizing these opportunities by forming strong and trusting partnerships with the building community and with local and state government.

  20. Delay-Aware Program Codes Dissemination Scheme in Internet of Everything

    Directory of Open Access Journals (Sweden)

    Yixuan Xu

    2016-01-01

    Full Text Available Due to recent advancements in big data, connection technologies, and smart devices, our environment is transforming into an “Internet of Everything” (IoE environment. These smart devices can obtain new or special functions by reprogramming: upgrade their soft systems through receiving new version of program codes. However, bulk codes dissemination suffers from large delay, energy consumption, and number of retransmissions because of the unreliability of wireless links. In this paper, a delay-aware program dissemination (DAPD scheme is proposed to disseminate program codes with fast, reliable, and energy-efficient style. We observe that although total energy is limited in wireless sensor network, there exists residual energy in nodes deployed far from the base station. Therefore, DAPD scheme improves the performance of bulk codes dissemination through the following two aspects. (1 Due to the fact that a high transmitting power can significantly improve the quality of wireless links, transmitting power of sensors with more residual energy is enhanced to improve link quality. (2 Due to the fact that performance of correlated dissemination tends to degrade in a highly dynamic environment, link correlation is autonomously updated in DAPD during codes dissemination to maintain improvements brought by correlated dissemination. Theoretical analysis and experimental results show that, compared with previous work, DAPD scheme improves the dissemination performance in terms of completion time, transmission cost, and the efficiency of energy utilization.

  1. Annual coded wire tag program (Washington) missing production groups : annual report 2000; ANNUAL

    International Nuclear Information System (INIS)

    Dammers, Wolf; Mills, Robin D.

    2002-01-01

    The Bonneville Power Administration (BPA) funds the ''Annual Coded-wire Tag Program - Missing Production Groups for Columbia River Hatcheries'' project. The Washington Department of Fish and Wildlife (WDFW), Oregon Department of Fish and Wildlife (ODFW) and the United States Fish and Wildlife Service (USFWS) all operate salmon and steelhead rearing programs in the Columbia River basin. The intent of the funding is to coded-wire tag at least one production group of each species at each Columbia Basin hatchery to provide a holistic assessment of survival and catch distribution over time and to meet various measures of the Northwest Power Planning Council's (NWPPC) Fish and Wildlife Program. The WDFW project has three main objectives: (1) coded-wire tag at least one production group of each species at each Columbia Basin hatchery to enable evaluation of survival and catch distribution over time, (2) recover coded-wire tags from the snouts of fish tagged under objective 1 and estimate survival, contribution, and stray rates for each group, and (3) report the findings under objective 2 for all broods of chinook, and coho released from WDFW Columbia Basin hatcheries. Objective 1 for FY-00 was met with few modifications to the original FY-00 proposal. Under Objective 2, snouts containing coded-wire tags that were recovered during FY-00 were decoded. Under Objective 3, this report summarizes available recovery information through 2000 and includes detailed information for brood years 1989 to 1994 for chinook and 1995 to 1997 for coho

  2. The Teaching of the Code of Ethics and Standard Practices for Texas Educator Preparation Programs

    Science.gov (United States)

    Davenport, Marvin; Thompson, J. Ray; Templeton, Nathan R.

    2015-01-01

    The purpose of this descriptive quantitative research study was to answer three basic informational questions: (1) To what extent ethics training, as stipulated in Texas Administrative Code Chapter 247, was included in the EPP curriculum; (2) To what extent Texas public universities with approved EPP programs provided faculty opportunities for…

  3. Towards provably correct code generation for a hard real-time programming language

    DEFF Research Database (Denmark)

    Fränzle, Martin; Müller-Olm, Markus

    1994-01-01

    This paper sketches a hard real-time programming language featuring operators for expressing timeliness requirements in an abstract, implementation-independent way and presents parts of the design and verification of a provably correct code generator for that language. The notion of implementation...

  4. Functions of Arabic-English Code-Switching: Sociolinguistic Insights from a Study Abroad Program

    Science.gov (United States)

    Al Masaeed, Khaled

    2013-01-01

    This sociolinguistic study examines the functions and motivations of code-switching, which is used here to mean the use of more than one language in the same conversation. The conversations studied here take place in a very particular context: one-on-one speaking sessions in a study abroad program in Morocco where English is the L1 and Arabic the…

  5. Assessment of Programming Language Learning Based on Peer Code Review Model: Implementation and Experience Report

    Science.gov (United States)

    Wang, Yanqing; Li, Hang; Feng, Yuqiang; Jiang, Yu; Liu, Ying

    2012-01-01

    The traditional assessment approach, in which one single written examination counts toward a student's total score, no longer meets new demands of programming language education. Based on a peer code review process model, we developed an online assessment system called "EduPCR" and used a novel approach to assess the learning of computer…

  6. Hydride heat pump. Volume I. Users manual for HYCSOS system design program. [HYCSOS code

    Energy Technology Data Exchange (ETDEWEB)

    Gorman, R.; Moritz, P.

    1978-05-01

    A method for the design and costing of a metal hydride heat pump for residential use and a computer program, HYCSOS, which automates that method are described. The system analyzed is one in which a metal hydride heat pump can provide space heating and space cooling powered by energy from solar collectors and electric power generated from solar energy. The principles and basic design of the system are presented, and the computer program is described giving detailed design and performance equations used in the program. The operation of the program is explained, and a sample run is presented. This computer program is part of an effort to design, cost, and evaluate a hydride heat pump for residential use. The computer program is written in standard Fortran IV and was run on a CDC Cyber 74 and Cyber 174 computer. A listing of the program is included as an appendix. This report is Volume 1 of a two-volume document.

  7. Family physicians' suggestions to improve the documentation, coding, and billing system: a study from the residency research network of Texas.

    Science.gov (United States)

    Young, Richard A; Bayles, Bryan; Hill, Jason H; Kumar, Kaparabonya A; Burge, Sandra

    2014-06-01

    The study's aim was to ascertain family physicians' suggestions on how to improve the commonly used US evaluation and management (E/M) rules for primary care. A companion paper published in Family Medicine's May 2014 journal describes our study methods (Fam Med 2014;46(5):378-84). Study subjects supported preserving the overall SOAP note structure. They especially suggested eliminating bullet counting in the E/M rules. For payment reform, respondents stated that brief or simple work should be paid less than long or complex work, and that family physicians should be paid for important tasks they currently are not, such as spending extra time with patients, phone and email clinical encounters, and extra paperwork. Subjects wanted shared savings when their decisions and actions created system efficiencies and savings. Some supported recent payment reforms such as monthly retainer fees and pay-for-performance bonuses. Others expressed skepticism about the negative consequences of each. Aligned incentives among all stakeholders was another common theme. Family physicians wanted less burdensome documentation requirements. They wanted to be paid more for complex work and work that does not include traditional face-to-face clinic visits, and they wanted the incentives of other stakeholders in the health care systems to be aligned with their priorities.

  8. Beyond the "Code": A Guide to the Description and Documentation of Biodiversity in Ciliated Protists (Alveolata, Ciliophora).

    Science.gov (United States)

    Warren, Alan; Patterson, David J; Dunthorn, Micah; Clamp, John C; Achilles-Day, Undine E M; Aescht, Erna; Al-Farraj, Saleh A; Al-Quraishy, Saleh; Al-Rasheid, Khaled; Carr, Martin; Day, John G; Dellinger, Marc; El-Serehy, Hamed A; Fan, Yangbo; Gao, Feng; Gao, Shan; Gong, Jun; Gupta, Renu; Hu, Xiaozhong; Kamra, Komal; Langlois, Gaytha; Lin, Xiaofeng; Lipscomb, Diana; Lobban, Christopher S; Luporini, Pierangelo; Lynn, Denis H; Ma, Honggang; Macek, Miroslav; Mackenzie-Dodds, Jacqueline; Makhija, Seema; Mansergh, Robert I; Martín-Cereceda, Mercedes; McMiller, Nettie; Montagnes, David J S; Nikolaeva, Svetlana; Ong'ondo, Geoffrey Odhiambo; Pérez-Uz, Blanca; Purushothaman, Jasmine; Quintela-Alonso, Pablo; Rotterová, Johana; Santoferrara, Luciana; Shao, Chen; Shen, Zhuo; Shi, Xinlu; Song, Weibo; Stoeck, Thorsten; La Terza, Antonietta; Vallesi, Adriana; Wang, Mei; Weisse, Thomas; Wiackowski, Krzysztof; Wu, Lei; Xu, Kuidong; Yi, Zhenzhen; Zufall, Rebecca; Agatha, Sabine

    2017-07-01

    Recent advances in molecular technology have revolutionized research on all aspects of the biology of organisms, including ciliates, and created unprecedented opportunities for pursuing a more integrative approach to investigations of biodiversity. However, this goal is complicated by large gaps and inconsistencies that still exist in the foundation of basic information about biodiversity of ciliates. The present paper reviews issues relating to the taxonomy of ciliates and presents specific recommendations for best practice in the observation and documentation of their biodiversity. This effort stems from a workshop that explored ways to implement six Grand Challenges proposed by the International Research Coordination Network for Biodiversity of Ciliates (IRCN-BC). As part of its commitment to strengthening the knowledge base that supports research on biodiversity of ciliates, the IRCN-BC proposes to populate The Ciliate Guide, an online database, with biodiversity-related data and metadata to create a resource that will facilitate accurate taxonomic identifications and promote sharing of data. © 2017 The Authors Journal of Eukaryotic Microbiology published by Wiley Periodicals, Inc. on behalf of International Society of Protistologists.

  9. Development of An Automatic Verification Program for Thermal-hydraulic System Codes

    Energy Technology Data Exchange (ETDEWEB)

    Lee, J. Y.; Ahn, K. T.; Ko, S. H.; Kim, Y. S.; Kim, D. W. [Pusan National University, Busan (Korea, Republic of); Suh, J. S.; Cho, Y. S.; Jeong, J. J. [System Engineering and Technology Co., Daejeon (Korea, Republic of)

    2012-05-15

    As a project activity of the capstone design competitive exhibition, supported by the Education Center for Green Industry-friendly Fusion Technology (GIFT), we have developed a computer program which can automatically perform non-regression test, which is needed repeatedly during a developmental process of a thermal-hydraulic system code, such as the SPACE code. A non-regression test (NRT) is an approach to software testing. The purpose of the non-regression testing is to verify whether, after updating a given software application (in this case, the code), previous software functions have not been compromised. The goal is to prevent software regression, whereby adding new features results in software bugs. As the NRT is performed repeatedly, a lot of time and human resources will be needed during the development period of a code. It may cause development period delay. To reduce the cost and the human resources and to prevent wasting time, non-regression tests need to be automatized. As a tool to develop an automatic verification program, we have used Visual Basic for Application (VBA). VBA is an implementation of Microsoft's event-driven programming language Visual Basic 6 and its associated integrated development environment, which are built into most Microsoft Office applications (In this case, Excel)

  10. Development of An Automatic Verification Program for Thermal-hydraulic System Codes

    International Nuclear Information System (INIS)

    Lee, J. Y.; Ahn, K. T.; Ko, S. H.; Kim, Y. S.; Kim, D. W.; Suh, J. S.; Cho, Y. S.; Jeong, J. J.

    2012-01-01

    As a project activity of the capstone design competitive exhibition, supported by the Education Center for Green Industry-friendly Fusion Technology (GIFT), we have developed a computer program which can automatically perform non-regression test, which is needed repeatedly during a developmental process of a thermal-hydraulic system code, such as the SPACE code. A non-regression test (NRT) is an approach to software testing. The purpose of the non-regression testing is to verify whether, after updating a given software application (in this case, the code), previous software functions have not been compromised. The goal is to prevent software regression, whereby adding new features results in software bugs. As the NRT is performed repeatedly, a lot of time and human resources will be needed during the development period of a code. It may cause development period delay. To reduce the cost and the human resources and to prevent wasting time, non-regression tests need to be automatized. As a tool to develop an automatic verification program, we have used Visual Basic for Application (VBA). VBA is an implementation of Microsoft's event-driven programming language Visual Basic 6 and its associated integrated development environment, which are built into most Microsoft Office applications (In this case, Excel)

  11. EGS code system: computer programs for the Monte Carlo simulation of electromagnetic cascade showers. Version 3

    International Nuclear Information System (INIS)

    Ford, R.L.; Nelson, W.R.

    1978-06-01

    A code to simulate almost any electron--photon transport problem conceivable is described. The report begins with a lengthy historical introduction and a description of the shower generation process. Then the detailed physics of the shower processes and the methods used to simulate them are presented. Ideas of sampling theory, transport techniques, particle interactions in general, and programing details are discussed. Next, EGS calculations and various experiments and other Monte Carlo results are compared. The remainder of the report consists of user manuals for EGS, PEGS, and TESTSR codes; options, input specifications, and typical output are included. 38 figures, 12 tables

  12. Software Quality and Security in Teachers' and Students' Codes When Learning a New Programming Language

    Directory of Open Access Journals (Sweden)

    Arnon Hershkovitz

    2015-09-01

    Full Text Available In recent years, schools (as well as universities have added cyber security to their computer science curricula. This topic is still new for most of the current teachers, who would normally have a standard computer science background. Therefore the teachers are trained and then teaching their students what they have just learned. In order to explore differences in both populations’ learning, we compared measures of software quality and security between high-school teachers and students. We collected 109 source files, written in Python by 18 teachers and 31 students, and engineered 32 features, based on common standards for software quality (PEP 8 and security (derived from CERT Secure Coding Standards. We use a multi-view, data-driven approach, by (a using hierarchical clustering to bottom-up partition the population into groups based on their code-related features and (b building a decision tree model that predicts whether a student or a teacher wrote a given code (resulting with a LOOCV kappa of 0.751. Overall, our findings suggest that the teachers’ codes have a better quality than the students’ – with a sub-group of the teachers, mostly males, demonstrate better coding than their peers and the students – and that the students’ codes are slightly better secured than the teachers’ codes (although both populations show very low security levels. The findings imply that teachers might benefit from their prior knowledge and experience, but also emphasize the lack of continuous involvement of some of the teachers with code-writing. Therefore, findings shed light on computer science teachers as lifelong learners. Findings also highlight the difference between quality and security in today’s programming paradigms. Implications for these findings are discussed.

  13. A program for undergraduate research into the mechanisms of sensory coding and memory decay

    Energy Technology Data Exchange (ETDEWEB)

    Calin-Jageman, R J

    2010-09-28

    This is the final technical report for this DOE project, entitltled "A program for undergraduate research into the mechanisms of sensory coding and memory decay". The report summarizes progress on the three research aims: 1) to identify phyisological and genetic correlates of long-term habituation, 2) to understand mechanisms of olfactory coding, and 3) to foster a world-class undergraduate neuroscience program. Progress on the first aim has enabled comparison of learning-regulated transcripts across closely related learning paradigms and species, and results suggest that only a small core of transcripts serve truly general roles in long-term memory. Progress on the second aim has enabled testing of several mutant phenotypes for olfactory behaviors, and results show that responses are not fully consistent with the combinitoral coding hypothesis. Finally, 14 undergraduate students participated in this research, the neuroscience program attracted extramural funding, and we completed a successful summer program to enhance transitions for community-college students into 4-year colleges to persue STEM fields.

  14. Annual coded wire tag program (Washington) missing production groups: annual report for 1997; ANNUAL

    International Nuclear Information System (INIS)

    Byrne, J.; Fuss, H.; Ashbrook, C.

    1998-01-01

    The Bonneville Power Administration (BPA) funds the ''Annual Coded Wire Tag Program - Missing Production Groups for Columbia River Hatcheries'' project. The Washington Department of Fish and Wildlife (WDFW), Oregon Department of Fish and Wildlife (ODFW) and the United States Fish and Wildlife Service (USFWS) all operate salmon and steelhead rearing programs in the Columbia River basin. The intent of the funding is to coded-wire tag at least one production group of each species at each Columbia Basin hatchery to provide a holistic assessment of survival and catch distribution over time and to meet various measures of the Northwest Power Planning Councils (NWPPC) Fish and Wildlife Program. The WDFW project has three main objectives: (1) coded-wire tag at least one production group of each species at each Columbia Basin hatchery to enable evaluation of survival and catch distribution over time, (2) recover coded-wire tags from the snouts of fish tagged under objective 1 and estimate survival, contribution, and stray rates for each group, and (3) report the findings under objective 2 for all broods of chinook, and coho released from WDFW Columbia Basin hatcheries. Objective 1 for FY-97 was met with few modifications to the original FY-97 proposal. Under Objective 2, snouts containing coded-wire tags that were recovered during FY-97 were decoded. Under Objective 3, survival, contribution and stray rate estimates for the 1991-96 broods of chinook and 1993-96 broods of coho have not been made because recovery data for 1996-97 fisheries and escapement are preliminary. This report summarizes recovery information through 1995

  15. Safeguarding critical e-documents implementing a program for securing confidential information assets

    CERN Document Server

    Smallwood, Robert F

    2012-01-01

    Practical, step-by-step guidance for corporations, universities and government agencies to protect and secure confidential documents and business records Managers and public officials are looking for technology and information governance solutions to "information leakage" in an understandable, concise format. Safeguarding Critical E-Documents provides a road map for corporations, governments, financial services firms, hospitals, law firms, universities and other organizations to safeguard their internal electronic documents and private communications.Provides practical, step-by-step guidance o

  16. Construction of Fixed Rate Non-Binary WOM Codes Based on Integer Programming

    Science.gov (United States)

    Fujino, Yoju; Wadayama, Tadashi

    In this paper, we propose a construction of non-binary WOM (Write-Once-Memory) codes for WOM storages such as flash memories. The WOM codes discussed in this paper are fixed rate WOM codes where messages in a fixed alphabet of size $M$ can be sequentially written in the WOM storage at least $t^*$-times. In this paper, a WOM storage is modeled by a state transition graph. The proposed construction has the following two features. First, it includes a systematic method to determine the encoding regions in the state transition graph. Second, the proposed construction includes a labeling method for states by using integer programming. Several novel WOM codes for $q$ level flash memories with 2 cells are constructed by the proposed construction. They achieve the worst numbers of writes $t^*$ that meet the known upper bound in many cases. In addition, we constructed fixed rate non-binary WOM codes with the capability to reduce ICI (inter cell interference) of flash cells. One of the advantages of the proposed construction is its flexibility. It can be applied to various storage devices, to various dimensions (i.e, number of cells), and various kind of additional constraints.

  17. Energy Efficiency/Renewable Energy Programs in State Implementation Plans - Guidance Documents

    Science.gov (United States)

    final document that provides guidance to States and local areas on quantifying and including emission reductions from energy efficiency and renewable energy measures in State Implementation Plans (SIPS).

  18. DOG -II input generator program for DOT3.5 code

    International Nuclear Information System (INIS)

    Hayashi, Katsumi; Handa, Hiroyuki; Yamada, Koubun; Kamogawa, Susumu; Takatsu, Hideyuki; Koizumi, Kouichi; Seki, Yasushi

    1992-01-01

    DOT3.5 is widely used for radiation transport analysis of fission reactors, fusion experimental facilities and particle accelerators. We developed the input generator program for DOT3.5 code in aim to prepare input data effectively. Formar program DOG was developed and used internally in Hitachi Engineering Company. In this new version DOG-II, limitation for R-Θ geometry was removed. All the input data is created by interactive method in front of color display without using DOT3.5 manual. Also the geometry related input are easily created without calculation of precise curved mesh point. By using DOG-II, reliable input data for DOT3.5 code is obtained easily and quickly

  19. Computer Program of SIE ASME-NH (Revision 1.0) Code

    Energy Technology Data Exchange (ETDEWEB)

    Koo, Gyeong Hoi; Lee, J. H

    2008-01-15

    In this report, the SIE ASME (Structural Integrity Evaluations by ASME-NH) (Revision 1.0), which has a computerized implementation of ASME Pressure Vessels and Piping Code Section III Subsection NH rules, is developed to apply to the next generation reactor design subjecting to the elevated temperature operations over 500 .deg. C and over 30 years design lifetime, and the user's manual for this program is described in detail.

  20. Computer Program of SIE ASME-NH (Revision 1.0) Code

    International Nuclear Information System (INIS)

    Koo, Gyeong Hoi; Lee, J. H.

    2008-01-01

    In this report, the SIE ASME (Structural Integrity Evaluations by ASME-NH) (Revision 1.0), which has a computerized implementation of ASME Pressure Vessels and Piping Code Section III Subsection NH rules, is developed to apply to the next generation reactor design subjecting to the elevated temperature operations over 500 .deg. C and over 30 years design lifetime, and the user's manual for this program is described in detail

  1. Development and implementation of documents control and records management system for KNPP units 5 and 6 modernization program

    International Nuclear Information System (INIS)

    Manchev, B.L.; Ilieva, M.; Nenkova, B. G. . E-mail of corresponding author: ilieva@riskeng.bg; Ilieva, M.)

    2005-01-01

    It was proposed to KNPP to develop and implement a Dcuments Control and Records Management System for an efficient and effective Configuration Management (CM) Program. It will provide reasonable assurance that consistency among design requirements, physical configuration and facility documentation is established and maintained during the Modernization Program and throughout the life of KNPP Units 5 and 6. The fully implemented CM Program will consider and track the modifications resulting from the Units 5 and 6 Modernization Program and will be consistent with internationally recognized principles and customized to fit within the KNPP organizational structure and philosophy (ANSI/NIRMA CM 1.0 - 2000, Configuration Management Of Nuclear Facilities). Development and implementation phase of Documents Control and Records Management System and SmartDoc information system, as well as ideas for further development are presented in this report. (author)

  2. FTC advertising substantiation program. Household products manufacturers. Documentation of Toshiba America, Inc

    Energy Technology Data Exchange (ETDEWEB)

    1978-01-01

    The report contains documentation in support of claims that the Toshiba Microwave Oven can cook any and all types of food satisfactorily with a 75% savings in energy usage and cost, regardless of the size of a household. (Portions of this document are not fully legible) (Color illustrations reproduced in black and white)

  3. FTC advertising substantiation program. Household products manufacturers. Documentation of Hakuhodo Advertising America, Inc

    Energy Technology Data Exchange (ETDEWEB)

    1978-01-01

    The report contains documentation in support of claims that the Toshiba Microwave Oven can cook any and all types of food satisfactorily with a 75% savings in energy usage and cost, regardless of the size of a household. (Portions of this document are not fully legible)

  4. 75 FR 9607 - National Protection and Programs Directorate; Guidance Document Request and Evaluation

    Science.gov (United States)

    2010-03-03

    ... information for continuous improvement to its documents. Guidance document request forms and evaluation forms... Request (ICR) to the Office of Management and Budget (OMB) for review and clearance in accordance with the... will be accepted until May 3, 2010. This process is conducted in accordance with 5 CFR 1320.1...

  5. Responding to the Effects of Extreme Heat: Baltimore City's Code Red Program.

    Science.gov (United States)

    Martin, Jennifer L

    2016-01-01

    Heat response plans are becoming increasingly more common as US cities prepare for heat waves and other effects of climate change. Standard elements of heat response plans exist, but plans vary depending on geographic location and distribution of vulnerable populations. Because heat events vary over time and affect populations differently based on vulnerability, it is difficult to compare heat response plans and evaluate responses to heat events. This article provides an overview of the Baltimore City heat response plan, the Code Red program, and discusses the city's response to the 2012 Ohio Valley/Mid Atlantic Derecho, a complex heat event. Challenges with and strategies for evaluating the program are reviewed and shared.

  6. POSSIBILITIES OF CREATIVE URBAN DEVELOPMENT AND CREATIVE FUTURE OF BUDAPEST ACCORDING TO THE NEW PROGRAMMING REGULATIONS AND DOCUMENTS

    OpenAIRE

    Szilágyi, Anna

    2013-01-01

    In the next programming period, starting in 2014, European cities face the challenge to become SMART cities focusing on sustainability, competitiveness and liveability. Does culture play a key role in this process, and if so, is the European Union aware of its importance? Do programming documents for the next period for Budapest express a recognizable will of the decision makers to transform the city to a Central-European creative capital? In my study, I examine the concepts and regulations o...

  7. "I Like to Plan Events": A Document Analysis of Essays Written by Applicants to a Public Relations Program

    Science.gov (United States)

    Taylor, Ronald E.

    2016-01-01

    A document analysis of 249 essays written during a 5-year period by applicants to a public relations program at a major state university in the southeast suggests that there are enduring reasons why students choose to major in public relations. Public relations is described as a major that allows for and encourages creative expression and that…

  8. Development of a computer program to support an efficient non-regression test of a thermal-hydraulic system code

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jun Yeob; Jeong, Jae Jun [School of Mechanical Engineering, Pusan National University, Busan (Korea, Republic of); Suh, Jae Seung [System Engineering and Technology Co., Daejeon (Korea, Republic of); Kim, Kyung Doo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-10-15

    During the development process of a thermal-hydraulic system code, a non-regression test (NRT) must be performed repeatedly in order to prevent software regression. The NRT process, however, is time-consuming and labor-intensive. Thus, automation of this process is an ideal solution. In this study, we have developed a program to support an efficient NRT for the SPACE code and demonstrated its usability. This results in a high degree of efficiency for code development. The program was developed using the Visual Basic for Applications and designed so that it can be easily customized for the NRT of other computer codes.

  9. Development and application of the PCRELAP5 - Data Calculation Program for RELAP 5 Code

    International Nuclear Information System (INIS)

    Silvestre, Larissa J.B.; Sabundjian, Gaianê

    2017-01-01

    Nuclear accidents in the world led to the establishment of rigorous criteria and requirements for nuclear power plant operations by the international regulatory bodies. By using specific computer programs, simulations of various accidents and transients likely to occur at any nuclear power plant are required for certifying and licensing a nuclear power plant. Some sophisticated computational tools have been used such as the Reactor Excursion and Leak Analysis Program (RELAP5), which is the most widely used code for the thermo-hydraulic analysis of accidents and transients in nuclear reactors in Brazil and worldwide. A major difficulty in the simulation by using RELAP5 code is the amount of information required for the simulation of thermal-hydraulic accidents or transients. Thus, for those calculations performance and preparation of RELAP5 input data, a friendly mathematical preprocessor was designed. The Visual Basic for Application (VBA) for Microsoft Excel demonstrated to be an effective tool to perform a number of tasks in the development of the program. In order to meet the needs of RELAP5 users, the RELAP5 Calculation Program (Programa de Cálculo do RELAP5 – PCRELAP5) was designed. The components of the code were codified; all entry cards including the optional cards of each one have been programmed. An English version for PCRELAP5 was provided. Furthermore, a friendly design was developed in order to minimize the time of preparation of input data and errors committed by users. The final version of this preprocessor was successfully applied for Safety Injection System (SIS) of Angra-2. (author)

  10. Development and application of the PCRELAP5 - Data Calculation Program for RELAP 5 Code

    Energy Technology Data Exchange (ETDEWEB)

    Silvestre, Larissa J.B.; Sabundjian, Gaianê, E-mail: larissajbs@usp.br, E-mail: gdjian@ipen.br [Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN-SP), São Paulo, SP (Brazil)

    2017-07-01

    Nuclear accidents in the world led to the establishment of rigorous criteria and requirements for nuclear power plant operations by the international regulatory bodies. By using specific computer programs, simulations of various accidents and transients likely to occur at any nuclear power plant are required for certifying and licensing a nuclear power plant. Some sophisticated computational tools have been used such as the Reactor Excursion and Leak Analysis Program (RELAP5), which is the most widely used code for the thermo-hydraulic analysis of accidents and transients in nuclear reactors in Brazil and worldwide. A major difficulty in the simulation by using RELAP5 code is the amount of information required for the simulation of thermal-hydraulic accidents or transients. Thus, for those calculations performance and preparation of RELAP5 input data, a friendly mathematical preprocessor was designed. The Visual Basic for Application (VBA) for Microsoft Excel demonstrated to be an effective tool to perform a number of tasks in the development of the program. In order to meet the needs of RELAP5 users, the RELAP5 Calculation Program (Programa de Cálculo do RELAP5 – PCRELAP5) was designed. The components of the code were codified; all entry cards including the optional cards of each one have been programmed. An English version for PCRELAP5 was provided. Furthermore, a friendly design was developed in order to minimize the time of preparation of input data and errors committed by users. The final version of this preprocessor was successfully applied for Safety Injection System (SIS) of Angra-2. (author)

  11. Guidance document for revision of DOE Order 5820.2A, Radioactive Waste Technical Support Program

    International Nuclear Information System (INIS)

    Kudera, D.E.; McMurtrey, C.D.; Meagher, B.G.

    1993-04-01

    This document provides guidance for the revision of DOE Order 5820.2A, ''Radioactive Waste Management.'' Technical Working Groups have been established and are responsible for writing the revised order. The Technical Working Groups will use this document as a reference for polices and procedures that have been established for the revision process. The overall intent of this guidance is to outline how the order will be revised and how the revision process will be managed. In addition, this document outlines technical issues considered for inclusion by a Department of Energy Steering Committee

  12. Gravity inversion code

    International Nuclear Information System (INIS)

    Burkhard, N.R.

    1979-01-01

    The gravity inversion code applies stabilized linear inverse theory to determine the topography of a subsurface density anomaly from Bouguer gravity data. The gravity inversion program consists of four source codes: SEARCH, TREND, INVERT, and AVERAGE. TREND and INVERT are used iteratively to converge on a solution. SEARCH forms the input gravity data files for Nevada Test Site data. AVERAGE performs a covariance analysis on the solution. This document describes the necessary input files and the proper operation of the code. 2 figures, 2 tables

  13. MCNP code

    International Nuclear Information System (INIS)

    Cramer, S.N.

    1984-01-01

    The MCNP code is the major Monte Carlo coupled neutron-photon transport research tool at the Los Alamos National Laboratory, and it represents the most extensive Monte Carlo development program in the United States which is available in the public domain. The present code is the direct descendent of the original Monte Carlo work of Fermi, von Neumaum, and Ulam at Los Alamos in the 1940s. Development has continued uninterrupted since that time, and the current version of MCNP (or its predecessors) has always included state-of-the-art methods in the Monte Carlo simulation of radiation transport, basic cross section data, geometry capability, variance reduction, and estimation procedures. The authors of the present code have oriented its development toward general user application. The documentation, though extensive, is presented in a clear and simple manner with many examples, illustrations, and sample problems. In addition to providing the desired results, the output listings give a a wealth of detailed information (some optional) concerning each state of the calculation. The code system is continually updated to take advantage of advances in computer hardware and software, including interactive modes of operation, diagnostic interrupts and restarts, and a variety of graphical and video aids

  14. MINI-TRAC code: a driver program for assessment of constitutive equations of two-fluid model

    International Nuclear Information System (INIS)

    Akimoto, Hajime; Abe, Yutaka; Ohnuki, Akira; Murao, Yoshio

    1991-05-01

    MINI-TRAC code, a driver program for assessment of constitutive equations of two-fluid model, has been developed to perform assessment and improvement of constitutive equations of two-fluid model widely and efficiently. The MINI-TRAC code uses one-dimensional conservation equations for mass, momentum and energy based on the two-fluid model. The code can work on a personal computer because it can be operated with a core memory size less than 640 KB. The MINI-TRAC code includes constitutive equations of TRAC-PF1/MOD1 code, TRAC-BF1 code and RELAP5/MOD2 code. The code is modulated so that one can easily change constitutive equations to perform a test calculation. This report is a manual of the MINI-TRAC code. The basic equations, numerics, constitutive, equations included in the MINI-TRAC code will be described. The user's manual such as input description will be presented. The program structure and contents of main variables will also be mentioned in this report. (author)

  15. PARMILA documentation

    International Nuclear Information System (INIS)

    Merson, J.L.

    1990-01-01

    The Los Alamos National Laboratory has produced a new manual for the program PARMILA. This paper is about that manual and includes only a small amount of material on the code itself. The manual is both a users and reference manual and will be of help to a programmer who needs to modify the code, though perhaps not as much help as would be desired. PARMILA has been in use for more than 20 years. It is widely used and there are many versions. The name PARMILA is an acronym for Phase And Radial Motion In Linear Accelerators, (or, more recently, ... in Ion Linear Accelerators). The code is a drift-tube linac ion beam dynamics code and does multiparticle simulations. A very good description of one version of the code was given in 1988 by G.P. Boicourt, coauthor of the manual being described. Here the author will briefly describe the codes functions, referring the reader to the earlier report for further detail. This paper provides a description of a users and reference manual for the AT-6 version of the code PARMILA

  16. SASWeave: Literate Programming Using SAS

    DEFF Research Database (Denmark)

    Lenth, Russell V; Højsgaard, Søren

    2007-01-01

    SASweave is a collection of scripts that allow one to embed SAS code into a LATEX document, and automatically incorporate the results as well. SASweave is patterned after Sweave, which does the same thing for code written in R. In fact, a document may contain both SAS and R code. Besides...... the convenience of being able to easily incorporate SAS examples in a document, SASweave facilitates the concept of "literate programming": having code, documentation, and results packaged together. Among other things, this helps to ensure that the SAS output in the document is in concordance with the code...

  17. Computer programs in BASIC language for atomic absorption flame spectroscopy. Part 2. Documentation

    International Nuclear Information System (INIS)

    Boyle, W.G. Jr.

    1977-01-01

    There are three computer programs, written in the BASIC language, used for taking data from an atomic absorption spectrophotometer operating in the flame mode. The programs are divided into logical sections, and these have been flow-charted. The general features, the structure, the order of subroutines and functions, and the storage of data are discussed. In addition, variables are listed and defined, and a complete listing of each program with a symbol occurrence table is provided

  18. Battelle integrity of nuclear piping program. Summary of results and implications for codes/standards

    International Nuclear Information System (INIS)

    Miura, Naoki

    2005-01-01

    The BINP(Battelle Integrity of Nuclear Piping) program was proposed by Battelle to elaborate pipe fracture evaluation methods and to improve LBB and in-service flaw evaluation criteria. The program has been conducted from October 1998 to September 2003. In Japan, CRIEPI participated in the program on behalf of electric utilities and fabricators to catch up the technical backgrounds for possible future revision of LBB and in-service flaw evaluation standards and to investigate the issues needed to be reflected to current domestic standards. A series of the results obtained from the program has been well utilized for the new LBB Regulatory Guide Program by USNRC and for proposal of revised in-service flaw evaluation criteria to the ASME Code Committee. The results were assessed whether they had implications for the existing or future domestic standards. As a result, the impact of many of these issues, which were concerned to be adversely affected to LBB approval or allowable flaw sizes in flaw evaluation criteria, was found to be relatively minor under actual plant conditions. At the same time, some issues that needed to be resolved to address advanced and rational standards in the future were specified. (author)

  19. Coding a Weather Model: DOE-FIU Science & Technology Workforce Development Program.

    Energy Technology Data Exchange (ETDEWEB)

    Bradley, Jon David [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2017-12-01

    DOE Fellow, Andres Cremisini, completed a 10-week internship with Sandia National Laboratories (SNL) in Albuquerque, New Mexico. Under the management of Kristopher Klingler and the mentorship of Jon Bradley, he was tasked with conceiving and coding a realistic weather model for use in physical security applications. The objective was to make a weather model that could use real data to accurately predict wind and precipitation conditions at any location of interest on the globe at any user-determined time. The intern received guidance on software design, the C++ programming language and clear communication of project goals and ongoing progress. In addition, Mr. Cremisini was given license to structure the program however he best saw fit, an experience that will benefit ongoing research endeavors.

  20. Documenting Instructional Practices in a Literacy-infused Arts Program: Respecting Pedagogues from the Community

    Science.gov (United States)

    Brooks, Wanda; Smith, Michael W.

    2013-01-01

    This study examines the instructional practices around literacy that characterized the work of a community based arts program designed for urban adolescents. Two primary sources of data were collected: field notes on approximately 35 hours of instruction spread across seven months and interviews with the program's staff and students. Four…

  1. Computer Programs in Marine Science: Key to Oceanographic Records Documentation No. 5.

    Science.gov (United States)

    Firestone, Mary A.

    Presented are abstracts of 700 computer programs in marine science. The programs listed are categorized under a wide range of headings which include physical oceanography, chemistry, coastal and estuarine processes, biology, pollution, air-sea interaction and heat budget, navigation and charting, curve fitting, and applied mathematics. The…

  2. Testing and documentation of programs used to transform climatological precipitation data to a geographically gridded format

    International Nuclear Information System (INIS)

    Fox, T.D.

    1979-01-01

    A procedure was developed for converting climatological hourly precipitation data into a form suitable for input to regional atmospheric transport and removal models. The procedure involves a rearrangement of the original data by date rather than by station, followed by the use of a spatial averaging scheme to interpolate data from randomly spaced stations to a regularly spaced grid. The procedure has been tested and documented for general use

  3. Development of a Wrapper Object, TRelap, for RELAP5 Code for Use in Object Oriented Programs

    International Nuclear Information System (INIS)

    Lee, Young Jin

    2008-01-01

    TRelap object class has been developed to enable object oriented programming techniques to be used where functionality of the RELAP5 thermal hydraulic system analysis code is needed. The TRelap is an object front for Dynamic Link Library (DLL) manifestation of the Relap5 code, Relap5.dll. In making the Relap5.dll, the top most structure of the RELAP5 was altered to enable the external calling procedures to control and the access the memory. The alteration was performed in such a way to allow the entire 'fa' and the f tb' memory spaces to be accessible to the calling procedure. Thus, any variable contained within the 'fa' array such as the parameters for the components, volumes, junctions, and heat structures can be accessed by the external calling procedure through TRelap. Various methods and properties to control the RELAP5 calculation and to access and manipulate the variables are built into the TRelap to enable easy manipulation. As a verification effort, a simple program was written to demonstrate the capability of the TRelap

  4. JUSTICE DISCRETIONARY GRANTS: Byrne Program and Violence Against Women Office Grant Monitoring Should Be Better Documented

    National Research Council Canada - National Science Library

    2001-01-01

    ...) Byrne Program and the Violence Against Women Office (VAWO) within OJP. Between fiscal years 1997 and 2000, Byrne and VAWO discretionary grant awards grew, in constant 2000 dollars, about 85 percent...

  5. CDC 7600 LTSS programming stratagens: preparing your first production code for the Livermore Timesharing System

    International Nuclear Information System (INIS)

    Fong, K.W.

    1977-01-01

    This report deals with some techniques in applied programming using the Livermore Timesharing System (LTSS) on the CDC 7600 computers at the National Magnetic Fusion Energy Computer Center (NMFECC) and the Lawrence Livermore Laboratory Computer Center (LLLCC or Octopus network). This report is based on a document originally written specifically about the system as it is implemented at NMFECC but has been revised to accommodate differences between LLLCC and NMFECC implementations. Topics include: maintaining programs, debugging, recovering from system crashes, and using the central processing unit, memory, and input/output devices efficiently and economically. Routines that aid in these procedures are mentioned. The companion report, UCID-17556, An LTSS Compendium, discusses the hardware and operating system and should be read before reading this report

  6. Software documentation and user's manual for fish-impingement sampling design and estimation method computer programs

    International Nuclear Information System (INIS)

    Murarka, I.P.; Bodeau, D.J.

    1977-11-01

    This report contains a description of three computer programs that implement the theory of sampling designs and the methods for estimating fish-impingement at the cooling-water intakes of nuclear power plants as described in companion report ANL/ES-60. Complete FORTRAN listings of these programs, named SAMPLE, ESTIMA, and SIZECO, are given and augmented with examples of how they are used

  7. Documentation and analysis of the Schlumberger interactive 1-D inversion program slumb

    Energy Technology Data Exchange (ETDEWEB)

    Sandberg, S.

    1979-09-01

    This computer program is designed to accept field data from a Schlumberger resistivity array and invert it in terms of a one-dimensional layered geoelectrical model. Because the inverse problem is non-linear, an initial guess model is required. This input model can be obtained by traditional curve matching, or by repeated use of a forward algorithm. This program was written in FORTRAN V and developed on a UNIVAC 1108 computer.

  8. Thermochemistry in BWR. An overview of applications of program codes and databases

    International Nuclear Information System (INIS)

    Hermansson, H-P.; Becker, R.

    2010-01-01

    The Swedish work on thermodynamics of metal-water systems relevant to BWR conditions has been ongoing since the 70ies, and at present time a compilation and adaptation of codes and thermodynamic databases are in progress. In the previous work, basic thermodynamic data were compiled for parts of the system Fe-Cr-Ni-Co-Zn-S-H 2 O at 25-300 °C. Since some thermodynamic information necessary for temperature extrapolations of data up to 300 °C was not published in the earlier works, these data have now been partially recalculated. This applies especially to the parameters of the HKF-model, which are used to extrapolate the thermodynamic data for ionic and neutral aqua species from 25 °C to BWR temperatures. Using the completed data, e.g. the change in standard Gibbs energy (ΔG 0 ) and the equilibrium constant (log K) can be calculated for further applications at BWR/LWR conditions. In addition a computer program is currently being developed at Studsvik for the calculation of equilibrium conductivity in high temperature water. The program is intended for PWR applications, but can also be applied to BWR environment. Data as described above will be added to the database of this program. It will be relatively easy to further develop the program e.g. to calculate Pourbaix diagrams, and these graphs could then be calculated at any temperature. This means that there will be no limitation to the temperatures and total concentrations (usually 10 -6 to 10 -8 mol/kg) as reported in earlier work. It is also easy to add a function generating ΔG 0 and log K values at selected temperatures. One of the fundamentals for this work was also to overview and collect publicly available thermodynamic program codes and databases of relevance for BWR conditions found in open sources. The focus has been on finding already done compilations and reviews, and some 40 codes and 15 databases were found. Codes and data-bases are often integrated and such a package is often developed for

  9. Texas geothermal R D and D program planning support document. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Davis, R.J.; Conover, M.F.; Keeney, R.C.; Personett, M.L.; Richmann, D.L.

    1981-08-28

    Program planning support was provided by; developing a geothermal RD and D program structure, characterizing the status of geothermal RD and D through review of literature and interaction with the geothermal research community, developing a candidate list of future Texas geothermal projects, and prioritizing the candidate projects based on appropriate evaluation criteria. The method used to perform this study and the results thereof are presented. Summary reviews of selected completed and ongoing projects and summary descriptions and evaluations of the candidate RD and D projects ar provided. A brief discussion emerging federal RD and D policies is presented. References and independent project rankings by three of the GRP members are included. (MHR)

  10. LUMIS: Land Use Management and Information Systems; coordinate oriented program documentation

    Science.gov (United States)

    1976-01-01

    An integrated geographic information system to assist program managers and planning groups in metropolitan regions is presented. The series of computer software programs and procedures involved in data base construction uses the census DIME file and point-in-polygon architectures. The system is described in two parts: (1) instructions to operators with regard to digitizing and editing procedures, and (2) application of data base construction algorithms to achieve map registration, assure the topological integrity of polygon files, and tabulate land use acreages within administrative districts.

  11. Description of ground motion data processing codes: Volume 3

    International Nuclear Information System (INIS)

    Sanders, M.L.

    1988-02-01

    Data processing codes developed to process ground motion at the Nevada Test Site for the Weapons Test Seismic Investigations Project are used today as part of the program to process ground motion records for the Nevada Nuclear Waste Storage Investigations Project. The work contained in this report documents and lists codes and verifies the ''PSRV'' code. 39 figs

  12. Mathematical description and program documentation for CLASSY, an adaptive maximum likelihood clustering method

    Science.gov (United States)

    Lennington, R. K.; Rassbach, M. E.

    1979-01-01

    Discussed in this report is the clustering algorithm CLASSY, including detailed descriptions of its general structure and mathematical background and of the various major subroutines. The report provides a development of the logic and equations used with specific reference to program variables. Some comments on timing and proposed optimization techniques are included.

  13. AdvoCasey: Documenting Programs That Work for Kids and Families, 1999-2000.

    Science.gov (United States)

    AdvoCasey, 2000

    2000-01-01

    This periodical provides accessible, in-depth profiles of programs and policies that have made measurable differences in the lives of children and families. A particular focus is on initiatives that have helped reform child-serving institutions and systems and that have strengthened the physical infrastructure, economic vitality, and social fabric…

  14. Mesoscale storm and dry period parameters from hourly precipitation data: program documentation

    Energy Technology Data Exchange (ETDEWEB)

    Thorp, J.M.

    1984-09-01

    Wet deposition of airborne chemical pollutants occurs primarily from precipitation. Precipitation rate, amount, duration, and location are important meteorological factors to be considered when attempting to understand the relationship of precipitation to pollutant deposition. The Pacific Northwest Laboratory (PNL) has conducted studies and experiments in numerous locations to collect data that can be incorporated into theories and models that attempt to describe the complex relationship between precipitation occurrence and chemical wet desposition. Model development often requires the use of average rather than random condition as input. To provide mean values of storm parameters, the task, Climatological Analysis of Mesoscale Storms, was created as a facet of the Environmental Protection Agency's related-service project, Precipitation Scavenging Module Development. Within this task computer programs have been developed at PNL which incorporate hourly precipitation data from National Weather Service stations to calculate mean values and frequency distributions of precipitation periods and of the interspersed dry periods. These programs have been written with a degree of flexibiity that will allow user modification for applications to different, but similar, analyses. This report describes in detail the rationale and operation of the two computer programs which produce the tables of average and frequency distributions of storm and dry period parameters from the precipitation data. A listing of the programs and examples of the generated output are included in the appendices. 3 references, 3 figures, 6 tables.

  15. Tourist Affiliate Program while Using Online Booking System with Possibility of Entering B2B Code

    Directory of Open Access Journals (Sweden)

    Slivar Iva

    2008-01-01

    Full Text Available Affiliate marketing programs are one of the most powerful tools for online marketing since the merchant presenting a product or a service decides on the commissioning model and the commission is granted only if the desired results have been reached. Affiliate marketing is based offline as much as tourism itself and it relies on the commission that tourist companies pay to their partners (affiliates who bring new guests. This paper will present the basics of how online affiliate programs work, benefits they bring and steps for their further implementation. It will explain in detail how to establish an affiliate program for dynamic web pages which use online booking system platforms that offer a possibility of entering a B2B code. Special attention will be paid to SEO (Search Engine Optimisation. It will also present results of a research on Croatian hotels web pages and the implementation of the online booking system and affiliate programs. Having in mind the insufficient deployment of online potentials, the aim of the paper is to stress the need for setting up an effective method of monitoring changes and updates in the online world as well as implementing new promotional possibilities, all aimed at increasing sales. The goal of the paper is to explore advantages and disadvantages of the affiliate program as a new sales channel and promote the possibility to implement it in one of the biggest Croatian hotel companies, Maistra d.d. Rovinj. Along with methods of data acquiring and different techniques of creative thinking, the following scientific research methods were also used: statistic, historic, descriptive, comparison, interview, analysis and synthesis, induction and deduction.

  16. Ces-VP: consultation expert system for vector programming of nuclear codes

    International Nuclear Information System (INIS)

    Fujisaki, Masahide; Makino, Mitsuhiro; Ishiguro, Misako

    1988-08-01

    Ces-VP is a prototype rule-based expert system for consulting the vector programming, based on the knowledge of vectorization of nuclear codes at JAERI during these 10 years. Experts in vectorization can restructure nuclear codes with high performance on vector processors, since they have know-how for choosing the best technique among a lot of techniques that were acquired from the experience of vectorization in the past. Frequency in trial and error will be reduced if a beginner can easily use the know-how of experts. In this report, at first the contents of Ces-VP and its intention are shown. Then, the method for acquiring the know-how of vectorization and the method for making rules from the know-how are described. The outline of Ces-VP implemented on Fujitsu expert tool ESHELL is described. Finally, the availability of Ces-VP is evaluated from the data gathered from practical use and its present problems are discussed. (author)

  17. Implementation of Neutronics Analysis Code using the Features of Object Oriented Programming via Fortran90/95

    Energy Technology Data Exchange (ETDEWEB)

    Han, Tae Young; Cho, Beom Jin [KEPCO Nuclear Fuel, Daejeon (Korea, Republic of)

    2011-05-15

    The object-oriented programming (OOP) concept was radically established after 1990s and successfully involved in Fortran 90/95. The features of OOP are such as the information hiding, encapsulation, modularity and inheritance, which lead to producing code that satisfy three R's: reusability, reliability and readability. The major OOP concepts, however, except Module are not mainly used in neutronics analysis codes even though the code was written by Fortran 90/95. In this work, we show that the OOP concept can be employed to develop the neutronics analysis code, ASTRA1D (Advanced Static and Transient Reactor Analyzer for 1-Dimension), via Fortran90/95 and those can be more efficient and reasonable programming methods

  18. Assessment model validity document - HYDRASTAR. A stochastic continuum program for groundwater flow

    Energy Technology Data Exchange (ETDEWEB)

    Gylling, B. [Kemakta Konsult AB, Stockholm (Sweden); Eriksson, Lars [Equa Simulation AB, Sundbyberg (Sweden)

    2001-12-01

    The prevailing document addresses validation of the stochastic continuum model HYDRASTAR designed for Monte Carlo simulations of groundwater flow in fractured rocks. Here, validation is defined as a process to demonstrate that a model concept is fit for its purpose. Preferably, the validation is carried out by comparison of model predictions with independent field observations and experimental measurements. In addition, other sources can also be used to confirm that the model concept gives acceptable results. One method is to compare results with the ones achieved using other model concepts for the same set of input data. Another method is to compare model results with analytical solutions. The model concept HYDRASTAR has been used in several studies including performance assessments of hypothetical repositories for spent nuclear fuel. In the performance assessments, the main tasks for HYDRASTAR have been to calculate groundwater travel time distributions, repository flux distributions, path lines and their exit locations. The results have then been used by other model concepts to calculate the near field release and far field transport. The aim and framework for the validation process includes describing the applicability of the model concept for its purpose in order to build confidence in the concept. Preferably, this is made by comparisons of simulation results with the corresponding field experiments or field measurements. Here, two comparisons with experimental results are reported. In both cases the agreement was reasonably fair. In the broader and more general context of the validation process, HYDRASTAR results have been compared with other models and analytical solutions. Commonly, the approximation calculations agree well with the medians of model ensemble results. Additional indications that HYDRASTAR is suitable for its purpose were obtained from the comparisons with results from other model concepts. Several verification studies have been made for

  19. ARDISC (Argonne Dispersion Code): computer programs to calculate the distribution of trace element migration in partially equilibrating media

    International Nuclear Information System (INIS)

    Strickert, R.; Friedman, A.M.; Fried, S.

    1979-04-01

    A computer program (ARDISC, the Argonne Dispersion Code) is described which simulates the migration of nuclides in porous media and includes first order kinetic effects on the retention constants. The code allows for different absorption and desorption rates and solves the coupled migration equations by arithmetic reiterations. Input data needed are the absorption and desorption rates, equilibrium surface absorption coefficients, flow rates and volumes, and media porosities

  20. Corporate Social Responsibility programs of Big Food in Australia: a content analysis of industry documents.

    Science.gov (United States)

    Richards, Zoe; Thomas, Samantha L; Randle, Melanie; Pettigrew, Simone

    2015-12-01

    To examine Corporate Social Responsibility (CSR) tactics by identifying the key characteristics of CSR strategies as described in the corporate documents of selected 'Big Food' companies. A mixed methods content analysis was used to analyse the information contained on Australian Big Food company websites. Data sources included company CSR reports and web-based content that related to CSR initiatives employed in Australia. A total of 256 CSR activities were identified across six organisations. Of these, the majority related to the categories of environment (30.5%), responsibility to consumers (25.0%) or community (19.5%). Big Food companies appear to be using CSR activities to: 1) build brand image through initiatives associated with the environment and responsibility to consumers; 2) target parents and children through community activities; and 3) align themselves with respected organisations and events in an effort to transfer their positive image attributes to their own brands. Results highlight the type of CSR strategies Big Food companies are employing. These findings serve as a guide to mapping and monitoring CSR as a specific form of marketing. © 2015 Public Health Association of Australia.

  1. A Hyperbolic Ontology Visualization Tool for Model Application Programming Interface Documentation

    Science.gov (United States)

    Hyman, Cody

    2011-01-01

    Spacecraft modeling, a critically important portion in validating planned spacecraft activities, is currently carried out using a time consuming method of mission to mission model implementations and integration. A current project in early development, Integrated Spacecraft Analysis (ISCA), aims to remedy this hindrance by providing reusable architectures and reducing time spent integrating models with planning and sequencing tools. The principle objective of this internship was to develop a user interface for an experimental ontology-based structure visualization of navigation and attitude control system modeling software. To satisfy this, a number of tree and graph visualization tools were researched and a Java based hyperbolic graph viewer was selected for experimental adaptation. Early results show promise in the ability to organize and display large amounts of spacecraft model documentation efficiently and effectively through a web browser. This viewer serves as a conceptual implementation for future development but trials with both ISCA developers and end users should be performed to truly evaluate the effectiveness of continued development of such visualizations.

  2. Detailed requirements document for common software of shuttle program information management system

    Science.gov (United States)

    Everette, J. M.; Bradfield, L. D.; Horton, C. L.

    1975-01-01

    Common software was investigated as a method for minimizing development and maintenance cost of the shuttle program information management system (SPIMS) applications while reducing the time-frame of their development. Those requirements satisfying these criteria are presented along with the stand-alone modules which may be used directly by applications. The SPIMS applications operating on the CYBER 74 computer, are specialized information management systems which use System 2000 as a data base manager. Common software provides the features to support user interactions on a CRT terminal using form input and command response capabilities. These features are available as subroutines to the applications.

  3. Multi-Year Program Plan - Building Regulatory Programs

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2010-10-01

    This document presents DOE’s multi-year plan for the three components of the Buildings Regulatory Program: Appliance and Equipment Efficiency Standards, ENERGY STAR, and the Building Energy Codes Program. This document summarizes the history of these programs, the mission and goals of the programs, pertinent statutory requirements, and DOE’s 5-year plan for moving forward.

  4. Documentation of COMRAD program (= Comprehensive System for Interactive Planning in Radiation Therapy)

    International Nuclear Information System (INIS)

    Pfister, G.; Friedlein, H.P.

    1984-05-01

    COMRAD is a radiotherapy planning program for calculating dose distribution in two- and three-dimensional patient geometries with coplanar or non-coplanar fields. The program was developed at the IBM Scientific Center Heidelberg and extended for applications in neutron therapy at the IKE by integration of the neutron dose formula and further specification options. These modifications were necessary for an accurate determination of inhomogeneities in neutron therapy and for neutron kerma calculations. Administrative data, e.g. patient name and number, date, doctor and physicist appear on all printed dose distributions. The treatment data comprise the therapy unit in use, specifications of the radiation field (radiation axis, source/skin distance, portal size, rotation parameters), dose specifications, and field specifications. The location and orientation of the planar cuts through the patient (windows) into which dose distributions shall be calculated can be set at will. The same applies to the density of the raster points at which dose values shall be computed. (orig./HP) [de

  5. RFQ simulation code

    International Nuclear Information System (INIS)

    Lysenko, W.P.

    1984-04-01

    We have developed the RFQLIB simulation system to provide a means to systematically generate the new versions of radio-frequency quadrupole (RFQ) linac simulation codes that are required by the constantly changing needs of a research environment. This integrated system simplifies keeping track of the various versions of the simulation code and makes it practical to maintain complete and up-to-date documentation. In this scheme, there is a certain standard version of the simulation code that forms a library upon which new versions are built. To generate a new version of the simulation code, the routines to be modified or added are appended to a standard command file, which contains the commands to compile the new routines and link them to the routines in the library. The library itself is rarely changed. Whenever the library is modified, however, this modification is seen by all versions of the simulation code, which actually exist as different versions of the command file. All code is written according to the rules of structured programming. Modularity is enforced by not using COMMON statements, simplifying the relation of the data flow to a hierarchy diagram. Simulation results are similar to those of the PARMTEQ code, as expected, because of the similar physical model. Different capabilities, such as those for generating beams matched in detail to the structure, are available in the new code for help in testing new ideas in designing RFQ linacs

  6. Implementation and evaluation of a simulation curriculum for paediatric residency programs including just-in-time in situ mock codes.

    Science.gov (United States)

    Sam, Jonathan; Pierse, Michael; Al-Qahtani, Abdullah; Cheng, Adam

    2012-02-01

    To develop, implement and evaluate a simulation-based acute care curriculum in a paediatric residency program using an integrated and longitudinal approach. Curriculum framework consisting of three modular, year-specific courses and longitudinal just-in-time, in situ mock codes. Paediatric residency program at BC Children's Hospital, Vancouver, British Columbia. The three year-specific courses focused on the critical first 5 min, complex medical management and crisis resource management, respectively. The just-in-time in situ mock codes simulated the acute deterioration of an existing ward patient, prepared the actual multidisciplinary code team, and primed the surrounding crisis support systems. Each curriculum component was evaluated with surveys using a five-point Likert scale. A total of 40 resident surveys were completed after each of the modular courses, and an additional 28 surveys were completed for the overall simulation curriculum. The highest Likert scores were for hands-on skill stations, immersive simulation environment and crisis resource management teaching. Survey results also suggested that just-in-time mock codes were realistic, reinforced learning, and prepared ward teams for patient deterioration. A simulation-based acute care curriculum was successfully integrated into a paediatric residency program. It provides a model for integrating simulation-based learning into other training programs, as well as a model for any hospital that wishes to improve paediatric resuscitation outcomes using just-in-time in situ mock codes.

  7. Development of application program and building database to increase facilities for using the radiation effect assessment computer codes

    International Nuclear Information System (INIS)

    Hyun Seok Ko; Young Min Kim; Suk-Hoon Kim; Dong Hoon Shin; Chang-Sun Kang

    2005-01-01

    The current radiation effect assessment system is required the skillful technique about the application for various code and high level of special knowledge classified by field. Therefore, as a matter of fact, it is very difficult for the radiation users' who don't have enough special knowledge to assess or recognize the radiation effect properly. For this, we already have developed the five Computer codes(windows-based), that is the radiation effect assessment system, in radiation utilizing field including the nuclear power generation. It needs the computer program that non-specialist can use the five computer codes to have already developed with ease. So, we embodied the A.I-based specialist system that can infer the assessment system by itself, according to the characteristic of given problem. The specialist program can guide users, search data, inquire of administrator directly. Conceptually, with circumstance which user to apply the five computer code may encounter actually, we embodied to consider aspects as follows. First, the accessibility of concept and data to need must be improved. Second, the acquirement of reference theory and use of corresponding computer code must be easy. Third, Q and A function needed for solution of user's question out of consideration previously. Finally, the database must be renewed continuously. Actually, to express this necessity, we develop the client program to organize reference data, to build the access methodology(query) about organized data, to load the visible expression function of searched data. And It is embodied the instruction method(effective theory acquirement procedure and methodology) to acquire the theory referring the five computer codes. It is developed the data structure access program(DBMS) to renew continuously data with ease. For Q and A function, it is embodied the Q and A board within client program because the user of client program can search the content of question and answer. (authors)

  8. Nuclear model codes available at the Nuclear Energy Agency Computer Program Library (NEA-CPL)

    International Nuclear Information System (INIS)

    Sartori, E.; Garcia Viedma, L. de

    1976-01-01

    This paper briefly outlines the objectives of the NEA-CPL and its activities in the field of Nuclear Model Computer Codes. A short description of the computer codes available from the CPL in this field is also presented. (author)

  9. 75 FR 19944 - International Code Council: The Update Process for the International Codes and Standards

    Science.gov (United States)

    2010-04-16

    ... documents from ICC's Chicago District Office: International Code Council, 4051 W Flossmoor Road, Country... Energy Conservation Code. International Existing Building Code. International Fire Code. International...

  10. Horonobe Underground Research Laboratory project investigation program for the 2007 fiscal year (Translated document)

    International Nuclear Information System (INIS)

    Matsui, Hiroya; Nakayama, Masashi; Sanada, Hiroyuki; Yamaguchi, Takehiro

    2008-09-01

    As past of the research and development program on the geological disposal of high-level radioactive waste (HLW), the Horonobe Underground Research Center, a division of the Japan Atomic Energy Agency (JAEA), is implementing the Horonobe Underground Research Laboratory Project (Horonobe URL Project) with the aim at investigating sedimentary rock formations. According to the research plan described in the Midterm Plan of JAEA, geological investigations are to be carried out during the drilling of a shaft down to intermediate depth, while research and development in the areas of engineering technology and safety assessment are to be promoted by collaboration with other research organizations. The results of the R and D activities will be systematized as a 'knowledge base' that supports a wide range of arguments related to the safety of geological disposal. The Horonobe URL Project is planned to extend over a period of 20 years. The investigations will be conducted in three phases, namely 'Phase 1: Surface-based investigations', 'Phase 2: Construction phase' (investigations during construction of the underground facilities) and 'Phase 3: Operation phase' (research in the underground facilities). This report summarizes the investigation program for the 2007 fiscal year (2007/2008), the third year of the Phase 2 investigations. In the 2007 fiscal year, investigations in geoscientific research', including 'development of techniques for investigating the geological environment', 'development of techniques for use in the deep underground environment' and 'studies on the long-term stability of the geological environment', is continuously carried out. Investigations in 'research and development on geological disposal technology', including improving the reliability of disposal technologies' and 'enhancement of safety assessment methodologies' are also continuously carried out. Construction of the underground facilities is ongoing at the Ventilation Shaft and the East Shaft

  11. Quality assurance program for environmental assessment of Savannah River Plant waste sites: Environmental information document

    International Nuclear Information System (INIS)

    Looney, B.B.; King, C.M.; Stephenson, D.E.

    1987-03-01

    Forty-eight locations were identified that received a variety of radioactive and nonradioactive constituents during the past 35 years including surface impoundments and shallow land burial facilities. Detailed environmental assessments of existing waste disposal areas, as well as new waste disposal techniques and disposition of tritiated water, were completed to air in an evaluation of the low level, mixed and hazardous waste management activities. These assessments result in estimation of risk, or residual risk, posed by each disposal area to various receptors as a function of waste management alternative. For example, at existing waste sites, the closure actions evaluated were waste removal and closure, no waste removal and closure, and no action; several pathways/receptors were considered, including groundwater to river, groundwater to well, atmospheric transport, occupational exposure, direct exposure, and contamination followed by ingestion of crops and meat. Modeling of chemical transport in a variety of media was an integral part of the assessment process. The quality of the models used and the application of these models were assured by an explicit quality assurance program

  12. [Programs for optimizing the use of antibiotics (PROA) in Spanish hospitals: GEIH-SEIMC, SEFH and SEMPSPH consensus document].

    Science.gov (United States)

    Rodríguez-Baño, Jesús; Paño-Pardo, José Ramón; Alvarez-Rocha, Luis; Asensio, Angel; Calbo, Esther; Cercenado, Emilia; Cisneros, José Miguel; Cobo, Javier; Delgado, Olga; Garnacho-Montero, José; Grau, Santiago; Horcajada, Juan Pablo; Hornero, Ana; Murillas-Angoiti, Javier; Oliver, Antonio; Padilla, Belén; Pasquau, Juan; Pujol, Miquel; Ruiz-Garbajosa, Patricia; San Juan, Rafael; Sierra, Rafael

    2012-01-01

    The antimicrobial agents are unique drugs for several reasons. First, their efficacy is higher than other drugs in terms of reduction of morbidity and mortality. Also, antibiotics are the only group of drugs associated with ecological effects, because their administration may contribute to the emergence and spread of microbial resistance. Finally, they are used by almost all medical specialties. Appropriate use of antimicrobials is very complex because of the important advances in the management of infectious diseases and the spread of antibiotic resistance. Thus, the implementation of programs for optimizing the use of antibiotics in hospitals (called PROA in this document) is necessary. This consensus document defines the objectives of the PROA (namely, to improve the clinical results of patients with infections, to minimise the adverse events associated to the use of antimicrobials including the emergence and spread of antibiotic resistance, and to ensure the use of the most cost-efficacious treatments), and provides recommendations for the implementation of these programs in Spanish hospitals. The key aspects of the recommendations are as follows. Multidisciplinary antibiotic teams should be formed, under the auspices of the Infection Committees. The PROA need to be considered as part of institutional programs and the strategic objectives of the hospital. The PROA should include specific objectives based on measurable indicators, and activities aimed at improving the use of antimicrobials, mainly through educational activities and interventions based more on training activities directed to prescribers than just on restrictive measures. Copyright © 2011 Elsevier España, S.L. All rights reserved.

  13. Inclusion of Students with Special Education Needs in French as a Second Language Programs: A Review of Canadian Policy and Resource Documents

    Science.gov (United States)

    Muhling, Stefanie; Mady, Callie

    2017-01-01

    This article describes a document analysis of policy and resource documents pertaining to inclusion of students with special education needs (SSEN) in Canadian French as a Second Language (FSL) programs. By recognizing gaps and acknowledging advancements, we aim to inform current implementation and future development of inclusive policy. Document…

  14. A fast reactor transient analysis methodology for PCs: Volume 3, LTC program manual of the QuickBASIC code

    International Nuclear Information System (INIS)

    Ott, K.O.; Chung, L.

    1992-06-01

    This manual augments the detailed manual of the GW-BASIC version of the LTC code for an application in QuickBASIC. As most of the GW-BASIC coding of this program for ''LMR Transient Calculations'' is compatible with QuickBASIC, this manual pertains primarily to the required changes, such as the handling of input and output. The considerable reduction in computation time achieved by this conversion is demonstrated for two sample problems, using a variety of hardware and execution options. The revised code is listed. Although the severe storage limitations of GW-BASIC no longer apply, the LOF transient path has not been completed in this QuickBASIC code. Its advantages are thus primarily in the much faster running time for TOP and LOHS transients. For the fastest PC hardware (486) and execution option the computation time is reduced by a factor of 124 compared to GW-BASIC on a 386/20

  15. Automatic coding method of the ACR Code

    International Nuclear Information System (INIS)

    Park, Kwi Ae; Ihm, Jong Sool; Ahn, Woo Hyun; Baik, Seung Kook; Choi, Han Yong; Kim, Bong Gi

    1993-01-01

    The authors developed a computer program for automatic coding of ACR(American College of Radiology) code. The automatic coding of the ACR code is essential for computerization of the data in the department of radiology. This program was written in foxbase language and has been used for automatic coding of diagnosis in the Department of Radiology, Wallace Memorial Baptist since May 1992. The ACR dictionary files consisted of 11 files, one for the organ code and the others for the pathology code. The organ code was obtained by typing organ name or code number itself among the upper and lower level codes of the selected one that were simultaneous displayed on the screen. According to the first number of the selected organ code, the corresponding pathology code file was chosen automatically. By the similar fashion of organ code selection, the proper pathologic dode was obtained. An example of obtained ACR code is '131.3661'. This procedure was reproducible regardless of the number of fields of data. Because this program was written in 'User's Defined Function' from, decoding of the stored ACR code was achieved by this same program and incorporation of this program into program in to another data processing was possible. This program had merits of simple operation, accurate and detail coding, and easy adjustment for another program. Therefore, this program can be used for automation of routine work in the department of radiology

  16. Reactor Vessel External Cooling for Corium Retention SULTAN Experimental Program and Modelling with CATHARE Code

    International Nuclear Information System (INIS)

    Rouge, S.; Dor, I.; Geffraye, G.

    1999-01-01

    In case of severe accident, a molten pool may form at the bottom of the lower head, and some pessimistic scenarios estimate that heat fluxes up to 1.5 MW/m 2 should be transferred through the vessel wall. An efficient, though completely passive, removal of heat flux during a long time is necessary to prevent total wall ablation, and a possible solution is to flood the cavity with water and establish boiling in natural convection. High heat exchanges are expected, especially if the system design (deflector along the vessel, riser...) emphasize water natural circulation, but are unfortunately limited by the critical heat flux phenomena (CHF). CHF data are very scarce in the adequate range of hydraulic and geometric parameters and are clearly dependent of the system effect in natural convection. The system effect can both modify flow velocity and two phase flow regimes, counter-current phenomena and flow static or dynamic instabilities. The SULTAN experimental program purpose was of two kinds, increasing CHF data for realistic situations, and improving the modeling of large 3D two phase flow circuits in natural convection. The CATHARE thermal-hydraulic code is used for interpreting the data and for extrapolation to real geometry. As a first step, a one-dimensional model is used. It is shown that some closure laws have to be improved. Reasonable predictions may be obtained but, for some test conditions, multi-dimensional effects such as recirculation appear to be dominant. Therefore the 3-dimensional module of CATHARE is also used to investigate these effects. This model well predicts qualitatively the existence and the development of a 2-phase layer along the heated wall as well as the existence of a recirculation zone. But modelling problems still require further development as part of a long term program for a better prediction of multi-dimensional two-phase flows

  17. Antimicrobial Exposure Assessment Task Force II (AEATF II) Volume 5: Governing Document for a Multi-Year Antimicrobial Chemical Exposure Monitoring Program (interim draft document)

    Science.gov (United States)

    Describes the overall scope of the AEATF II program, demonstrates the need for additional human exposure monitoring data and explains the proposed methodology for the exposure monitoring studies proposed for conduct by the AEATF II.

  18. Application of CAMP code to analysis of debris coolability experiments in ALPHA program

    International Nuclear Information System (INIS)

    Maruyama, Yu; Moriyama, Kiyofumi; Park, Hyun-Sun; Yang, Yanhua; Sugimoto, Jun

    1999-01-01

    An analytical code for thermo-fluid dynamics of a molten debris, CAMP, was applied to the analysis of the ex-vessel and in-vessel debris coolability experiments performed in ALPHA program. The analysis on the ex-vessel debris coolability experiments, where water was added onto a layer of thermite melt, indicated that the upper surface of the melt was remained molten during a period when melt eruptions followed by a mild steam explosion were observed. This might imply that a coarse mixing between the melt and the overlying water could have been formed if a sufficient force was generated at the interface between the two fluids. In the analysis of the in-vessel debris coolability experiments, where an aluminum oxide (Al 2 O 3 ) melt was poured into a water-filled lower head experimental vessel, a temperature increase at the outer surface of the vessel was qualitatively reproduced when a gap was assumed to be at the interface between the solidified Al 2 O 3 and the vessel wall. (author)

  19. The development of depletion program coupled with Monte Carlo computer code

    International Nuclear Information System (INIS)

    Nguyen Kien Cuong; Huynh Ton Nghiem; Vuong Huu Tan

    2015-01-01

    The paper presents the development of depletion code for light water reactor coupled with MCNP5 code called the MCDL code (Monte Carlo Depletion for Light Water Reactor). The first order differential depletion system equations of 21 actinide isotopes and 50 fission product isotopes are solved by the Radau IIA Implicit Runge Kutta (IRK) method after receiving neutron flux, reaction rates in one group energy and multiplication factors for fuel pin, fuel assembly or whole reactor core from the calculation results of the MCNP5 code. The calculation for beryllium poisoning and cooling time is also integrated in the code. To verify and validate the MCDL code, high enriched uranium (HEU) and low enriched uranium (LEU) fuel assemblies VVR-M2 types and 89 fresh HEU fuel assemblies, 92 LEU fresh fuel assemblies cores of the Dalat Nuclear Research Reactor (DNRR) have been investigated and compared with the results calculated by the SRAC code and the MCNP R EBUS linkage system code. The results show good agreement between calculated data of the MCDL code and reference codes. (author)

  20. Report number codes

    Energy Technology Data Exchange (ETDEWEB)

    Nelson, R.N. (ed.)

    1985-05-01

    This publication lists all report number codes processed by the Office of Scientific and Technical Information. The report codes are substantially based on the American National Standards Institute, Standard Technical Report Number (STRN)-Format and Creation Z39.23-1983. The Standard Technical Report Number (STRN) provides one of the primary methods of identifying a specific technical report. The STRN consists of two parts: The report code and the sequential number. The report code identifies the issuing organization, a specific program, or a type of document. The sequential number, which is assigned in sequence by each report issuing entity, is not included in this publication. Part I of this compilation is alphabetized by report codes followed by issuing installations. Part II lists the issuing organization followed by the assigned report code(s). In both Parts I and II, the names of issuing organizations appear for the most part in the form used at the time the reports were issued. However, for some of the more prolific installations which have had name changes, all entries have been merged under the current name.

  1. Report number codes

    International Nuclear Information System (INIS)

    Nelson, R.N.

    1985-05-01

    This publication lists all report number codes processed by the Office of Scientific and Technical Information. The report codes are substantially based on the American National Standards Institute, Standard Technical Report Number (STRN)-Format and Creation Z39.23-1983. The Standard Technical Report Number (STRN) provides one of the primary methods of identifying a specific technical report. The STRN consists of two parts: The report code and the sequential number. The report code identifies the issuing organization, a specific program, or a type of document. The sequential number, which is assigned in sequence by each report issuing entity, is not included in this publication. Part I of this compilation is alphabetized by report codes followed by issuing installations. Part II lists the issuing organization followed by the assigned report code(s). In both Parts I and II, the names of issuing organizations appear for the most part in the form used at the time the reports were issued. However, for some of the more prolific installations which have had name changes, all entries have been merged under the current name

  2. Comment response document for the Secretary of Energy's ''Report to Congress on Reassessment of the Civilian Radioactive Waste Management Program''

    International Nuclear Information System (INIS)

    1990-11-01

    On November 29, 1989, the Secretary of Energy published his ''Report to Congress on the Reassessment of the Civilian Radioactive Waste Management Program'' (Report), and sent copies to numerous interested parties for their review and comment. This document summarizes comments received on the Report and presents the DOE's current responses to those comments as a basis for further discussions. Included as appendixes are a list of commenters, a crosswalk showing where each comment is addressed, the comment letters themselves with specific comments delineated, and the DOE's response to those letters. Twenty-five individuals or organizations submitted comments on the Report. The DOE identified 130 individual comments and classified them into the following seven categories: Management, Institutional, Regulatory, Transportation, Monitored Retrievable Storage, Scheduling, and Yucca Mountain. For the responses, comments were than grouped into more specific topics under each of the major headings. The DOE attempted to respond to all comments

  3. The role of a certified calibration laboratory in a station's measuring and test equipment calibration, repair, and documentation program

    International Nuclear Information System (INIS)

    Ebenstreit, K.; MacIntosh, N.

    1995-01-01

    This paper outlines the role of a Certified Calibration Laboratory in- ensuring that the requirements of Measuring and Test Equipment calibration, identification, and traceability are met and documented. The Nuclear environment is one which is subject to influences from numerous 'quality agents'. One of the fields which comes under the scrutiny of the quality agents is that of equipment calibration and repair (both field components and M and TE). There is a responsibility to produce a superior product for the Ontario Consumer. The maintenance and calibration of Station Systems and their components have a direct impact on this output. The Measuring and Test Equipment element in each of these needs can be addressed by having a defined group of Maintenance Staff to execute a Measuring and Test Equipment Program which meets specific parameters. (author)

  4. LISA. A code for safety assessment in nuclear waste disposals program description and user guide

    International Nuclear Information System (INIS)

    Saltelli, A.; Bertozzi, G.; Stanners, D.A.

    1984-01-01

    The code LISA (Long term Isolation Safety Assessment), developed at the Joint Research Centre, Ispra is a useful tool in the analysis of the hazard due to the disposal of nuclear waste in geological formations. The risk linked to preestablished release scenarios is assessed by the code in terms of dose rate to a maximum exposed individual. The various submodels in the code simulate the system of barriers -both natural and man made- which are interposed between the contaminants and man. After a description of the code features a guide for the user is supplied and then a test case is presented

  5. WIPP documentation plan

    International Nuclear Information System (INIS)

    Plung, D.L.; Montgomery, T.T.; Glasstetter, S.R.

    1986-01-01

    In support of the programs at the Waste Isolation Pilot Plant (WIPP), the Publications and Procedures Section developed a documentation plan that provides an integrated document hierarchy; further, this plan affords several unique features: 1) the format for procedures minimizes the writing responsibilities of the technical staff and maximizes use of the writing and editing staff; 2) review cycles have been structured to expedite the processing of documents; and 3) the numbers of documents needed to support the program have been appreciably reduced

  6. Detecting Source Code Plagiarism on .NET Programming Languages using Low-level Representation and Adaptive Local Alignment

    Directory of Open Access Journals (Sweden)

    Oscar Karnalim

    2017-01-01

    Full Text Available Even though there are various source code plagiarism detection approaches, only a few works which are focused on low-level representation for deducting similarity. Most of them are only focused on lexical token sequence extracted from source code. In our point of view, low-level representation is more beneficial than lexical token since its form is more compact than the source code itself. It only considers semantic-preserving instructions and ignores many source code delimiter tokens. This paper proposes a source code plagiarism detection which rely on low-level representation. For a case study, we focus our work on .NET programming languages with Common Intermediate Language as its low-level representation. In addition, we also incorporate Adaptive Local Alignment for detecting similarity. According to Lim et al, this algorithm outperforms code similarity state-of-the-art algorithm (i.e. Greedy String Tiling in term of effectiveness. According to our evaluation which involves various plagiarism attacks, our approach is more effective and efficient when compared with standard lexical-token approach.

  7. MVP/GMVP Version 3. General purpose Monte Carlo codes for neutron and photon transport calculations based on continuous energy and multigroup methods (Translated document)

    International Nuclear Information System (INIS)

    Nagaya, Yasunobu; Okumura, Keisuke; Sakurai, Takeshi; Mori, Takamasa

    2017-03-01

    In order to realize fast and accurate Monte Carlo simulation of neutron and photon transport problems, two Monte Carlo codes MVP (continuous-energy method) and GMVP (multigroup method) have been developed at Japan Atomic Energy Agency. The codes have adopted a vectorized algorithm and have been developed for vector-type supercomputers. They also support parallel processing with a standard parallelization library MPI and thus a speed-up of Monte Carlo calculations can be achieved on general computing platforms. The first and second versions of the codes were released in 1994 and 2005, respectively. They have been extensively improved and new capabilities have been implemented. The major improvements and new capabilities are as follows: (1) perturbation calculation for effective multiplication factor, (2) exact resonant elastic scattering model, (3) calculation of reactor kinetics parameters, (4) photo-nuclear model, (5) simulation of delayed neutrons, (6) generation of group constants. This report describes the physical model, geometry description method used in the codes, new capabilities and input instructions. (author)

  8. The Evolution of a Coding Schema in a Paced Program of Research

    Science.gov (United States)

    Winters, Charlene A.; Cudney, Shirley; Sullivan, Therese

    2010-01-01

    A major task involved in the management, analysis, and integration of qualitative data is the development of a coding schema to facilitate the analytic process. Described in this paper is the evolution of a coding schema that was used in the analysis of qualitative data generated from online forums of middle-aged women with chronic conditions who…

  9. The Live Coding of Slub - Art Oriented Programming as Media Critique

    DEFF Research Database (Denmark)

    Andersen, Christian Ulrik

    2007-01-01

    Computer art is often associated with computer-generated expressions (digital audio/images in music, video, stage design, etc.). In recent computer art, however, the code-text itself – not the generated output – has become the artwork (Perl Poetry, ASCII Art, obfuscated code, etc.). This paper wi...

  10. Application of software quality assurance to a specific scientific code development task

    International Nuclear Information System (INIS)

    Dronkers, J.J.

    1986-03-01

    This paper describes an application of software quality assurance to a specific scientific code development program. The software quality assurance program consists of three major components: administrative control, configuration management, and user documentation. The program attempts to be consistent with existing local traditions of scientific code development while at the same time providing a controlled process of development

  11. Annual Coded Wire Tag Program; Oregon Missing Production Groups, 1995 Annual Report.

    Energy Technology Data Exchange (ETDEWEB)

    Garrison, Robert L.; Mallette, Christine; Lewis, Mark A.

    1995-12-01

    Bonneville Power Administration is the funding source for the Oregon Department of Fish and Wildlife`s Annual Coded Wire Tag Program - Oregon Missing Production Groups Project. Tule brood fall chinook were caught primarily in the British Columbia, Washington and northern Oregon ocean commercial fisheries. The up-river bright fall chinook contributed primarily to the Alaska and British Columbia ocean commercial fisheries and the Columbia River gillnet fishery. Contribution of Rogue fall chinook released in the lower Columbia River system occurred primarily in the Oregon ocean commercial and Columbia river gillnet fisheries Willamette spring chinook salmon contributed primarily to the Alaska and British Columbia ocean commercial, Oregon freshwater sport and Columbia River gillnet fisheries. Restricted ocean sport and commercial fisheries limited contribution of the Columbia coho released in the Umatilla River that survived at an average rate of 1.05% and contributed primarily to the Washington, Oregon and California ocean sport and commercial fisheries and the Columbia River gillnet fishery. The 1987 to 1991 brood years of coho released in the Yakima River survived at an average rate of 0.64% and contributed primarily to the Washington, Oregon and California ocean sport and commercial fisheries and the Columbia River gillnet fishery. Survival rates of salmon and steelhead are influenced, not only by factors in the hatchery, disease, density, diet and size and time of release, but also by environmental factors in the river and ocean. These environmental factors are controlled by large scale weather patterns such as El Nino over which man has no influence. Man could have some influence over river flow conditions, but political and economic pressures generally out weigh the biological needs of the fish.

  12. Development of a Wrapper Object for MARS TH Systems Code and Its Applications in Object Oriented Programs

    International Nuclear Information System (INIS)

    Park, Sun Byung; Lee, Young Jin; Kim, Hyong Chol; Han, Sam Hee; Kim, Hyun Jik

    2013-01-01

    TMARS is written for the object pascal program language, and 'wraps' the Dynamic Link Library (DLL) manifestation of the MARS-KS code written in Fortran 90. TMARS behaves as a true object and it can be instantiated, inherited, and its methods overloaded. The functionality of TMARS was verified and demonstrated using two programs built under object oriented program environment. One is a text based program for reviewing the data interface of TMARS, and the other is a graphic intensive prototype NPA program for testing the overall performance of TMARS. The prototype NPA was also used to assess the real-time capability of TMARS. The demonstration programs show that application of TMARS is straight forward and that its functions facilitate easy application developments. TMARS, a wrapper object class encapsulating the calculation functions of MARS-KS code, was successfully developed and verification of its functionality was carried out using custom made programs. The verification results show that TMARS is capable of providing reliable TH calculation results and sufficient performance to realize real time calculations

  13. Preprocessor for RELAP5 code, nuclear reactor thermal hydraulics accident analysis program, using Microsoft MS-EXCEL tool

    International Nuclear Information System (INIS)

    Biaty, Patricia Andrea Paladino; Sabundjian, Gaiane

    2005-01-01

    The thermal hydraulic study in accidents and transients analyses in nuclear power plants is realized with some special tools. These programs use the best estimate analyses and have been developed to simulate accidents and transients in Pressurized Water Reactors (PWR) and auxiliary systems. The RELAP5 code has been used as tool to licensing the nuclear facilities in our country, which is the objective of this study. The main problem when RELAP5 code is used is a lot of information necessary to simulate thermal hydraulic accidents. Moreover, there is the necessity of a reasonable amount of mathematical operations to calculation of the geometry of the components existents. Therefore, in order to facilitate the manipulation of this information, it is necessary the developing a friendly preprocessor for attainment of the mathematical calculations for RELAP5 code. One of the tools used for some of these calculations is the MS-EXCEL, which will be used in this work. (author)

  14. Linking data repositories - an illustration of agile data curation principles through robust documentation and multiple application programming interfaces

    Science.gov (United States)

    Benedict, K. K.; Servilla, M. S.; Vanderbilt, K.; Wheeler, J.

    2015-12-01

    The growing volume, variety and velocity of production of Earth science data magnifies the impact of inefficiencies in data acquisition, processing, analysis, and sharing workflows, potentially to the point of impairing the ability of researchers to accomplish their desired scientific objectives. The adaptation of agile software development principles (http://agilemanifesto.org/principles.html) to data curation processes has significant potential to lower barriers to effective scientific data discovery and reuse - barriers that otherwise may force the development of new data to replace existing but unusable data, or require substantial effort to make data usable in new research contexts. This paper outlines a data curation process that was developed at the University of New Mexico that provides a cross-walk of data and associated documentation between the data archive developed by the Long Term Ecological Research (LTER) Network Office (PASTA - http://lno.lternet.edu/content/network-information-system) and UNM's institutional repository (LoboVault - http://repository.unm.edu). The developed automated workflow enables the replication of versioned data objects and their associated standards-based metadata between the LTER system and LoboVault - providing long-term preservation for those data/metadata packages within LoboVault while maintaining the value-added services that the PASTA platform provides. The relative ease with which this workflow was developed is a product of the capabilities independently developed on both platforms - including the simplicity of providing a well-documented application programming interface (API) for each platform enabling scripted interaction and the use of well-established documentation standards (EML in the case of PASTA, Dublin Core in the case of LoboVault) by both systems. These system characteristics, when combined with an iterative process of interaction between the Data Curation Librarian (on the LoboVault side of the process

  15. 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

  16. PEAR code review

    International Nuclear Information System (INIS)

    De Wit, R.; Jamieson, T.; Lord, M.; Lafortune, J.F.

    1997-07-01

    As a necessary component in the continuous improvement and refinement of methodologies employed in the nuclear industry, regulatory agencies need to periodically evaluate these processes to improve confidence in results and ensure appropriate levels of safety are being achieved. The independent and objective review of industry-standard computer codes forms an essential part of this program. To this end, this work undertakes an in-depth review of the computer code PEAR (Public Exposures from Accidental Releases), developed by Atomic Energy of Canada Limited (AECL) to assess accidental releases from CANDU reactors. PEAR is based largely on the models contained in the Canadian Standards Association (CSA) N288.2-M91. This report presents the results of a detailed technical review of the PEAR code to identify any variations from the CSA standard and other supporting documentation, verify the source code, assess the quality of numerical models and results, and identify general strengths and weaknesses of the code. The version of the code employed in this review is the one which AECL intends to use for CANDU 9 safety analyses. (author)

  17. Validation of the REL2005 code package on Gd-poisoned PWR type assemblies through the CAMELEON experimental program

    International Nuclear Information System (INIS)

    Blaise, Patrick; Vidal, Jean-Francois; Santamarina, Alain

    2009-01-01

    This paper details the validation of Gd-poisoned 17x17 PWR lattices, through several configurations of the CAMELEON experimental program, by using the newly qualified REL2005 French code package. After a general presentation of the CAMELEON program that took place in the EOLE critical Facility in Cadarache, one describes the new REL2005 code package relying on the deterministic transport code APOLLO2.8 based on characteristics method (MOC), and its new CEA2005 library based on the latest JEFF-3.1.1 nuclear data evaluation. For critical masses, the average Calculation-to-Experiment C/E's on the k eff are (136 ± 80) pcm and (300 ± 76) pcm for the reference 281 groups MOC and optimized 26 groups MOC schemes respectively. These values include also a drastic improvement of about 250 pcm due to the change in the library from JEF2.2 to JEFF3.1. For pin-by-pin radial power distributions, reference and REL2005 results are very close, with maximum discrepancies of the order of 2%, i.e., in the experimental uncertainty limits. The Optimized REL2005 code package allows to predict the reactivity worth of the Gd-clusters (averaged on 9 experimental configurations) to be C/E Δρ(Gd clusters) = +1.3% ± 2.3%. (author)

  18. Description of the THYDE-P code

    International Nuclear Information System (INIS)

    Asahi, Yoshiro

    1978-07-01

    This paper is a preliminary report about the methods and the models applied to a computer code named THYDE-P which is concerned with thermal-hydraulic transients of a PWR plant following a large or small area break of a primary coolant system pipe, generally referred to as a loss-of-coolant accident (LOCA). The THYDE-P code deals not only with blowdown phase, but also with reflooding phase. What characterizes the THYDE-P code is its entirely new model for the primary loop network. The code user information and the programming detail are not included in this report, but in a future documentation. (auth.)

  19. Lessons learned from new construction utility demand side management programs and their implications for implementing building energy codes

    Energy Technology Data Exchange (ETDEWEB)

    Wise, B.K.; Hughes, K.R.; Danko, S.L.; Gilbride, T.L.

    1994-07-01

    This report was prepared for the US Department of Energy (DOE) Office of Codes and Standards by the Pacific Northwest Laboratory (PNL) through its Building Energy Standards Program (BESP). The purpose of this task was to identify demand-side management (DSM) strategies for new construction that utilities have adopted or developed to promote energy-efficient design and construction. PNL conducted a survey of utilities and used the information gathered to extrapolate lessons learned and to identify evolving trends in utility new-construction DSM programs. The ultimate goal of the task is to identify opportunities where states might work collaboratively with utilities to promote the adoption, implementation, and enforcement of energy-efficient building energy codes.

  20. From Algorithmic Black Boxes to Adaptive White Boxes: Declarative Decision-Theoretic Ethical Programs as Codes of Ethics

    OpenAIRE

    van Otterlo, Martijn

    2017-01-01

    Ethics of algorithms is an emerging topic in various disciplines such as social science, law, and philosophy, but also artificial intelligence (AI). The value alignment problem expresses the challenge of (machine) learning values that are, in some way, aligned with human requirements or values. In this paper I argue for looking at how humans have formalized and communicated values, in professional codes of ethics, and for exploring declarative decision-theoretic ethical programs (DDTEP) to fo...

  1. Developmental programming of long non-coding RNAs during postnatal liver maturation in mice.

    Directory of Open Access Journals (Sweden)

    Lai Peng

    Full Text Available The liver is a vital organ with critical functions in metabolism, protein synthesis, and immune defense. Most of the liver functions are not mature at birth and many changes happen during postnatal liver development. However, it is unclear what changes occur in liver after birth, at what developmental stages they occur, and how the developmental processes are regulated. Long non-coding RNAs (lncRNAs are involved in organ development and cell differentiation. Here, we analyzed the transcriptome of lncRNAs in mouse liver from perinatal (day -2 to adult (day 60 by RNA-Sequencing, with an attempt to understand the role of lncRNAs in liver maturation. We found around 15,000 genes expressed, including about 2,000 lncRNAs. Most lncRNAs were expressed at a lower level than coding RNAs. Both coding RNAs and lncRNAs displayed three major ontogenic patterns: enriched at neonatal, adolescent, or adult stages. Neighboring coding and non-coding RNAs showed the trend to exhibit highly correlated ontogenic expression patterns. Gene ontology (GO analysis revealed that some lncRNAs enriched at neonatal ages have their neighbor protein coding genes also enriched at neonatal ages and associated with cell proliferation, immune activation related processes, tissue organization pathways, and hematopoiesis; other lncRNAs enriched at adolescent ages have their neighbor protein coding genes associated with different metabolic processes. These data reveal significant functional transition during postnatal liver development and imply the potential importance of lncRNAs in liver maturation.

  2. Simulation model for wind energy storage systems. Volume III. Program descriptions. [SIMWEST CODE

    Energy Technology Data Exchange (ETDEWEB)

    Warren, A.W.; Edsinger, R.W.; Burroughs, J.D.

    1977-08-01

    The effort developed a comprehensive computer program for the modeling of wind energy/storage systems utilizing any combination of five types of storage (pumped hydro, battery, thermal, flywheel and pneumatic). An acronym for the program is SIMWEST (Simulation Model for Wind Energy Storage). The level of detail of SIMWEST is consistent with a role of evaluating the economic feasibility as well as the general performance of wind energy systems. The software package consists of two basic programs and a library of system, environmental, and load components. Volume III, the SIMWEST program description contains program descriptions, flow charts and program listings for the SIMWEST Model Generation Program, the Simulation program, the File Maintenance program and the Printer Plotter program. Volume III generally would not be required by SIMWEST user.

  3. Documenting Employee Conduct

    Science.gov (United States)

    Dalton, Jason

    2009-01-01

    One of the best ways for a child care program to lose an employment-related lawsuit is failure to document the performance of its employees. Documentation of an employee's performance can provide evidence of an employment-related decision such as discipline, promotion, or discharge. When properly implemented, documentation of employee performance…

  4. Pembuatan Kakas Pendeteksi Unused Method pada Kode Program PHP dengan Framework CodeIgniter Menggunakan Call Graph

    Directory of Open Access Journals (Sweden)

    Divi Galih Prasetyo Putri

    2014-03-01

    Full Text Available Proses evolusi dan perawatan dari sebuah sistem merupakan proses yang sangat penting dalam rekayasa perangkat lunak tidak terkecuali pada aplikasi web. Pada proses ini kebanyakan pengembang tidak lagi berpatokan pada rancangan sistem. Hal ini menyebabkan munculnya unused method. Bagian-bagian program ini tidak lagi terpakai namun masih berada dalam sistem. Keadaan ini meningkatkan kompleksitas dan mengurangi tingkat understandability sistem. Guna mendeteksi adanya unused method pada progam diperlukan teknik untuk melakukan code analysis. Teknik static analysis yang digunakan memanfaatkan call graph yang dibangun dari kode program untuk mengetahui adanya unused method. Call graph dibangun berdasarkan pemanggilan antar method. Aplikasi ini mendeteksi unused method pada kode program PHP yang dibangun menggunakan framework CodeIgniter. Kode program sebagai inputan diurai kedalam bentuk Abstract Syntax Tree (AST yang kemudian dimanfaatkan untuk melakukan analisis terhadap kode program. Proses analisis tersebut kemudian menghasilkan sebuah call graph. Dari call graph yang dihasilkan dapat dideteksi method-method mana saja yang tidak berhasil ditelusuri dan tergolong kedalam unused method. Kakas telah diuji coba pada 5 aplikasi PHP dengan hasil  rata-rata nilai presisi sistem sebesar 0.749 dan recall sebesar 1.

  5. Registration document 2005; Document de reference 2005

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    This reference document of Gaz de France provides information and data on the Group activities in 2005: financial informations, business, activities, equipments factories and real estate, trade, capital, organization charts, employment, contracts and research programs. (A.L.B.)

  6. FERRET data analysis code

    International Nuclear Information System (INIS)

    Schmittroth, F.

    1979-09-01

    A documentation of the FERRET data analysis code is given. The code provides a way to combine related measurements and calculations in a consistent evaluation. Basically a very general least-squares code, it is oriented towards problems frequently encountered in nuclear data and reactor physics. A strong emphasis is on the proper treatment of uncertainties and correlations and in providing quantitative uncertainty estimates. Documentation includes a review of the method, structure of the code, input formats, and examples

  7. Evaluating the ONEBFP transport code for possible use in the proton radiography program. Final report, Task 47

    International Nuclear Information System (INIS)

    Marr, D.R.; Prael, R.E.; Adams, K.J.

    1996-10-01

    This is notification of the completion of Task 47 and a summary of the fulfillment of the requirements thereof. Deliverables for Task 47 include the data test files and a final report. The test files have been delivered to the customer and the attached paper satisfies the requirements for a final report. Detail on the completion of each of the subtasks described in the Statement of Work follow. The author repeats the complete list of subtasks for Task 47: (1) The software engineer will modify the ONEBFP code to generate a logarithmic distribution of discrete angles and an associated set of quadrature weights; (2) The software engineer will work with Group XTM personnel to obtain the required cross-section data for protons/nuclear cascade particles; and (3) The software engineer will perform 5 test calculations using the modified ONEBFP code to assess its accuracy and efficiency for proton transport problems. The test calculations will be documented in a brief report. Appendix C of the paper describes the quadrature set capability installed in the ONEBFP code pertinent to the fulfillment of subtask 1. A portion of the body of the paper describes the source and modeling and Appendix A describes the extraction of the cross section data used in this study, fulfilling subtask 2. The bulk of the attached report describes the test problems, states the modeling used for each problem, shows the results in both graphical and tabular form, and discusses the implications of the results. This fulfills the requirements of subtask 3

  8. Procedure for the use of the code SAGAPO-A and auxiliary programs

    International Nuclear Information System (INIS)

    Cevolani, S.

    1981-06-01

    This paper describes the procedure developed in order to optimize the use of the computer code SAGAPO-A for the thermo-fluid-dynamic analysis of gas cooled fuel element bundles. The first item of this procedure concerns the dynamic dimensioning of the code, having as target the optimization of the computer storage requirement. The second item concerns the graphical output: the results of the calculation are plotted together with the experimental results, in order to allow an immediate evaluation of the calculation. (orig.) [de

  9. Hanford Dose Overview Program. Comparison of AIRDOS-EPA and Hanford site dose codes

    International Nuclear Information System (INIS)

    Aaberg, R.L.; Napier, B.A.

    1985-11-01

    Radiation dose commitments for persons in the Hanford environs calculated using AIRDOS-EPA were compared with those calculated using a suite of Hanford codes: FOOD, PABLM, DACRIN, and KRONIC. Dose commitments to the population and to the maximally exposed individual (MI) based on annual releases of eight radionuclides from the N-Reactor, were calculated by these codes. Dose commitments from each pathway to the total body, lung, thyroid, and lower large intestine (LLI) are given for the population and MI, respectively. 11 refs., 25 tabs

  10. HETERO code, heterogeneous procedure for reactor calculation; Program Hetero, heterogeni postupak proracuna reaktora

    Energy Technology Data Exchange (ETDEWEB)

    Jovanovic, S M; Raisic, N M [Boris Kidric Institute of Nuclear Sciences Vinca, Beograd (Yugoslavia)

    1966-11-15

    This report describes the procedure for calculating the parameters of heterogeneous reactor system taking into account the interaction between fuel elements related to established geometry. First part contains the analysis of single fuel element in a diffusion medium, and criticality condition of the reactor system described by superposition of elements interactions. the possibility of performing such analysis by determination of heterogeneous system lattice is described in the second part. Computer code HETERO with the code KETAP (calculation of criticality factor {eta}{sub n} and flux distribution) is part of this report together with the example of RB reactor square lattice.

  11. GRASP [GRound-Water Adjunct Sensitivity Program]: A computer code to perform post-SWENT [simulator for water, energy, and nuclide transport] adjoint sensitivity analysis of steady-state ground-water flow: Technical report

    International Nuclear Information System (INIS)

    Wilson, J.L.; RamaRao, B.S.; McNeish, J.A.

    1986-11-01

    GRASP (GRound-Water Adjunct Senstivity Program) computes measures of the behavior of a ground-water system and the system's performance for waste isolation, and estimates the sensitivities of these measures to system parameters. The computed measures are referred to as ''performance measures'' and include weighted squared deviations of computed and observed pressures or heads, local Darcy velocity components and magnitudes, boundary fluxes, and travel distance and time along travel paths. The sensitivities are computed by the adjoint method and are exact derivatives of the performance measures with respect to the parameters for the modeled system, taken about the assumed parameter values. GRASP presumes steady-state, saturated grondwater flow, and post-processes the results of a multidimensional (1-D, 2-D, 3-D) finite-difference flow code. This document describes the mathematical basis for the model, the algorithms and solution techniques used, and the computer code design. The implementation of GRASP is verified with simple one- and two-dimensional flow problems, for which analytical expressions of performance measures and sensitivities are derived. The linkage between GRASP and multidimensional finite-difference flow codes is described. This document also contains a detailed user's manual. The use of GRASP to evaluate nuclear waste disposal issues has been emphasized throughout the report. The performance measures and their sensitivities can be employed to assist in directing data collection programs, expedite model calibration, and objectively determine the sensitivity of projected system performance to parameters

  12. Programming Video Games and Simulations in Science Education: Exploring Computational Thinking through Code Analysis

    Science.gov (United States)

    Garneli, Varvara; Chorianopoulos, Konstantinos

    2018-01-01

    Various aspects of computational thinking (CT) could be supported by educational contexts such as simulations and video-games construction. In this field study, potential differences in student motivation and learning were empirically examined through students' code. For this purpose, we performed a teaching intervention that took place over five…

  13. Thermal-hydraulic analysis for the LBE-cooled natural circulation reactor. Development of the MSG-COPD code and application to the system analysis. Research Document

    International Nuclear Information System (INIS)

    Iwasaki, Takashi; Sakai, Takaaki; Enuma, Yasuhiro; Mizuno, Tomoyasu

    2002-03-01

    Thermal-hydraulic analysis for the Lead-Bismuth eutectic (LBE)-cooled natural circulation reactor has been conducted by using a combined plant dynamics code (MSG-COPD). MSG-COPD has been developed to consider the multi-dimensional thermal-hydraulics effect on the plant dynamics during transients. Plant dynamics analyses for the LBE-cooled STAR-LM reactor, which has been designed by Argonne National Laboratory in U.S.A., have been performed to understand the basic thermal-hydraulic characteristics of the natural circulation reactor. As a result, it has been made clear that cold coolant remains in the lower plenum by the thermal stratification in case of the ULOHS condition with a severe temperature gradient at the stratified surface in the lower plenum. In addition, the flow-redistribution effect in a core channels by the buoyancy force has been evaluated for a candidate LBE-cooled FBR plant concept (LBE-FR), which has been designed by JNC. A linear evaluation method for the flow-redistribution coefficient is proposed for the LBE-FR, and compared with the multi-dimensional results by MSG-COPD. In conclusion, the method shows sufficient performance for the prediction of the flow-redistribution coefficient for typical lateral power distributions in the core. (author)

  14. Test of user- and system programs coded in real time languages - requirements on program language and testing tool

    International Nuclear Information System (INIS)

    Hertlin, J.; Mackert, M.

    1979-01-01

    In the present paper the functions are presented, which should be part of a test system for user programs in a higher treat time programming language, taking into account time sequences and competitive processes. As can be shown by the problem of testing, use of higher level real time programming languages renders the task of program development essentially easier, however performance of test procedures without appropriate test systems is very difficult. After the presentation of notions and methods for the testing of programs, general requirements on testing tools are described and the test system functions for a program test, beeing uncritical with respect to time, are placed together. Thereby, for every individual function, the interface between the test system, the program under test, and the residual program-generation system (compiler, binder, operating system, delay-time system, and loader) is given too. For the time-critical test, a series of desirable functions are described, which can be implemented with acceptable expense. (orig.) [de

  15. H0 precessor computer code

    International Nuclear Information System (INIS)

    van Dyck, O.B.; Floyd, R.A.

    1981-05-01

    A spin precessor using H - to H 0 stripping, followed by small precession magnets, has been developed for the LAMPF 800-MeV polarized H - beam. The performance of the system was studied with the computer code documented in this report. The report starts from the fundamental physics of a system of spins with hyperfine coupling in a magnetic field and contains many examples of beam behavior as calculated by the program

  16. The use of Photovoice to document and characterize the food security of users of community food programs in Iqaluit, Nunavut.

    Science.gov (United States)

    Lardeau, M-P; Healey, G; Ford, J

    2011-01-01

    Food insecurity is a chronic problem affecting Inuit communities. The most comprehensive assessment of Inuit food security to-date, the Inuit Health Survey, reported that 70% of Inuit pre-school children lived in 'food insecure' households. Food banks and soup kitchens are relatively new in the Arctic but the number of users is increasing. Little is known about the experience and determinants of food insecurity among food program users who are often among the most marginalized (socially and economically) in communities. The use of participatory research methods when working in the north of Canada can promote meaningful knowledge exchange with community members and this approach was used in the present 'Photovoice' research. Photovoice uses photography to develop a baseline understanding of an issue, in this case the experience and determinants of food insecurity among users of community food programs in Iqaluit, Nunavut. The target population includes those who face significant social and economic marginalization, an often neglected group in Arctic food systems research. Eight regular users of food programs were recruited and engaged in a Photovoice research project to document factors determining their daily food consumption. The research method was introduced in workshops and discussion included the ethical concerns related to photography and how to take pictures. Participants were supplied with digital cameras, and asked to answer the following question using photography: 'What aspects of your everyday life affect what you eat and how much you have to eat?'. In the final workshop, photographs were discussed among the group and participants identified key themes in the photographs, offering an understanding of food insecurity from their perspectives. The group then discussed what should be done with the knowledge gained. Factors improving food security were the customary systems for sharing 'country food', and the presence of social support networks in the

  17. Medical Applications of the PHITS Code (3): User Assistance Program for Medical Physics Computation.

    Science.gov (United States)

    Furuta, Takuya; Hashimoto, Shintaro; Sato, Tatsuhiko

    2016-01-01

    DICOM2PHITS and PSFC4PHITS are user assistance programs for medical physics PHITS applications. DICOM2PHITS is a program to construct the voxel PHITS simulation geometry from patient CT DICOM image data by using a conversion table from CT number to material composition. PSFC4PHITS is a program to convert the IAEA phase-space file data to PHITS format to be used as a simulation source of PHITS. Both of the programs are useful for users who want to apply PHITS simulation to verification of the treatment planning of radiation therapy. We are now developing a program to convert dose distribution obtained by PHITS to DICOM RT-dose format. We also want to develop a program which is able to implement treatment information included in other DICOM files (RT-plan and RT-structure) as a future plan.

  18. FENDL/MC. Library of continuous energy cross sections in ACE format for neutron-photon transport calculations with the Monte Carlo N-particle Transport Code system MCNP 4A. Version 1.1 of March 1995. Summary documentation

    International Nuclear Information System (INIS)

    Pashchenko, A.B.; Wienke, H.; Ganesan, S.

    1996-01-01

    Selected neutron reaction nuclear data evaluations for elements of interest to the IAEA's program on Fusion Evaluated Nuclear Data Library (FENDL) have been processed into ACE format using the NJOY system by R.E. MacFarlane. This document summarizes the resulting continuous energy cross-section data library FENDL/MC version 1.1. The data are available cost free, upon request from the IAEA Nuclear Data Section, online or on magnetic tape. (author). 1 tab

  19. Guidance document for revision of DOE Order 5820.2A, Radioactive Waste Technical Support Program. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Kudera, D.E.; McMurtrey, C.D.; Meagher, B.G.

    1993-04-01

    This document provides guidance for the revision of DOE Order 5820.2A, ``Radioactive Waste Management.`` Technical Working Groups have been established and are responsible for writing the revised order. The Technical Working Groups will use this document as a reference for polices and procedures that have been established for the revision process. The overall intent of this guidance is to outline how the order will be revised and how the revision process will be managed. In addition, this document outlines technical issues considered for inclusion by a Department of Energy Steering Committee.

  20. EAC european accident code. A modular system of computer programs to simulate LMFBR hypothetical accidents

    International Nuclear Information System (INIS)

    Wider, H.; Cametti, J.; Clusaz, A.; Devos, J.; VanGoethem, G.; Nguyen, H.; Sola, A.

    1985-01-01

    One aspect of fast reactor safety analysis consists of calculating the strongly coupled system of physical phenomena which contribute to the reactivity balance in hypothetical whole-core accidents: these phenomena are neutronics, fuel behaviour and heat transfer together with coolant thermohydraulics in single- and two-phase flow. Temperature variations in fuel, coolant and neighbouring structures induce, in fact, thermal reactivity feedbacks which are added up and put in the neutronics calculation to predict the neutron flux and the subsequent heat generation in the reactor. At this point a whole-core analysis code is necessary to examine for any hypothetical transient whether the various feedbacks result effectively in a negative balance, which is the basis condition to ensure stability and safety. The European Accident Code (EAC), developed at the Joint Research Centre of the CEC at Ispra (Italy), fulfills this objective. It is a modular informatics structure (quasi 2-D multichannel approach) aimed at collecting stand-alone computer codes of neutronics, fuel pin mechanics and hydrodynamics, developed both in national laboratories and in the JRC itself. EAC makes these modules interact with each other and produces results for these hypothetical accidents in terms of core damage and total energy release. 10 refs

  1. Overview of the U.S. DOE Hydrogen Safety, Codes and Standards Program. Part 4: Hydrogen Sensors; Preprint

    Energy Technology Data Exchange (ETDEWEB)

    Buttner, William J.; Rivkin, Carl; Burgess, Robert; Brosha, Eric; Mukundan, Rangachary; James, C. Will; Keller, Jay

    2016-12-01

    Hydrogen sensors are recognized as a critical element in the safety design for any hydrogen system. In this role, sensors can perform several important functions including indication of unintended hydrogen releases, activation of mitigation strategies to preclude the development of dangerous situations, activation of alarm systems and communication to first responders, and to initiate system shutdown. The functionality of hydrogen sensors in this capacity is decoupled from the system being monitored, thereby providing an independent safety component that is not affected by the system itself. The importance of hydrogen sensors has been recognized by DOE and by the Fuel Cell Technologies Office's Safety and Codes Standards (SCS) program in particular, which has for several years supported hydrogen safety sensor research and development. The SCS hydrogen sensor programs are currently led by the National Renewable Energy Laboratory, Los Alamos National Laboratory, and Lawrence Livermore National Laboratory. The current SCS sensor program encompasses the full range of issues related to safety sensors, including development of advance sensor platforms with exemplary performance, development of sensor-related code and standards, outreach to stakeholders on the role sensors play in facilitating deployment, technology evaluation, and support on the proper selection and use of sensors.

  2. NSURE code

    International Nuclear Information System (INIS)

    Rattan, D.S.

    1993-11-01

    NSURE stands for Near-Surface Repository code. NSURE is a performance assessment code. developed for the safety assessment of near-surface disposal facilities for low-level radioactive waste (LLRW). Part one of this report documents the NSURE model, governing equations and formulation of the mathematical models, and their implementation under the SYVAC3 executive. The NSURE model simulates the release of nuclides from an engineered vault, their subsequent transport via the groundwater and surface water pathways tot he biosphere, and predicts the resulting dose rate to a critical individual. Part two of this report consists of a User's manual, describing simulation procedures, input data preparation, output and example test cases

  3. Using Program Theory-Driven Evaluation Science to Crack the Da Vinci Code

    Science.gov (United States)

    Donaldson, Stewart I.

    2005-01-01

    Program theory-driven evaluation science uses substantive knowledge, as opposed to method proclivities, to guide program evaluations. It aspires to update, clarify, simplify, and make more accessible the evolving theory of evaluation practice commonly referred to as theory-driven or theory-based evaluation. The evaluator in this chapter provides a…

  4. Survey of nuclear fuel-cycle codes

    International Nuclear Information System (INIS)

    Thomas, C.R.; de Saussure, G.; Marable, J.H.

    1981-04-01

    A two-month survey of nuclear fuel-cycle models was undertaken. This report presents the information forthcoming from the survey. Of the nearly thirty codes reviewed in the survey, fifteen of these codes have been identified as potentially useful in fulfilling the tasks of the Nuclear Energy Analysis Division (NEAD) as defined in their FY 1981-1982 Program Plan. Six of the fifteen codes are given individual reviews. The individual reviews address such items as the funding agency, the author and organization, the date of completion of the code, adequacy of documentation, computer requirements, history of use, variables that are input and forecast, type of reactors considered, part of fuel cycle modeled and scope of the code (international or domestic, long-term or short-term, regional or national). The report recommends that the Model Evaluation Team perform an evaluation of the EUREKA uranium mining and milling code

  5. SAFIPA-Meraka Institute code-sprints program; a mechanism to enhance the development capacity of emerging developers – observations and lessons learned

    CSIR Research Space (South Africa)

    Coetzee, L

    2010-05-01

    Full Text Available -MERAKA code-sprints program, a possibility for development is identified. NAP, an initiative to enhance inclusion and empower persons with disabilities, has shown that initiatives need to come from within the community to succeed. A popular slogan... ownership of development efforts. This paper investigates the feasibility of the “ICT for Society through Society” paradigm at the hand of the SAFIPA-MERAKA code-sprints program, an analysis of the Information and Communications Technology...

  6. Integer-linear-programing optimization in scalable video multicast with adaptive modulation and coding in wireless networks.

    Science.gov (United States)

    Lee, Dongyul; Lee, Chaewoo

    2014-01-01

    The advancement in wideband wireless network supports real time services such as IPTV and live video streaming. However, because of the sharing nature of the wireless medium, efficient resource allocation has been studied to achieve a high level of acceptability and proliferation of wireless multimedia. Scalable video coding (SVC) with adaptive modulation and coding (AMC) provides an excellent solution for wireless video streaming. By assigning different modulation and coding schemes (MCSs) to video layers, SVC can provide good video quality to users in good channel conditions and also basic video quality to users in bad channel conditions. For optimal resource allocation, a key issue in applying SVC in the wireless multicast service is how to assign MCSs and the time resources to each SVC layer in the heterogeneous channel condition. We formulate this problem with integer linear programming (ILP) and provide numerical results to show the performance under 802.16 m environment. The result shows that our methodology enhances the overall system throughput compared to an existing algorithm.

  7. Integer-Linear-Programing Optimization in Scalable Video Multicast with Adaptive Modulation and Coding in Wireless Networks

    Directory of Open Access Journals (Sweden)

    Dongyul Lee

    2014-01-01

    Full Text Available The advancement in wideband wireless network supports real time services such as IPTV and live video streaming. However, because of the sharing nature of the wireless medium, efficient resource allocation has been studied to achieve a high level of acceptability and proliferation of wireless multimedia. Scalable video coding (SVC with adaptive modulation and coding (AMC provides an excellent solution for wireless video streaming. By assigning different modulation and coding schemes (MCSs to video layers, SVC can provide good video quality to users in good channel conditions and also basic video quality to users in bad channel conditions. For optimal resource allocation, a key issue in applying SVC in the wireless multicast service is how to assign MCSs and the time resources to each SVC layer in the heterogeneous channel condition. We formulate this problem with integer linear programming (ILP and provide numerical results to show the performance under 802.16 m environment. The result shows that our methodology enhances the overall system throughput compared to an existing algorithm.

  8. Code Maintenance and Design for a Visual Programming Language Graphical User Interface

    National Research Council Canada - National Science Library

    Pierson, Graham

    2004-01-01

    This work adds new functionality to an existing visual programming environment. It applies software maintenance techniques for use with the Java Language in a Microsoft Windows operating system environment...

  9. Documentation of a Regional Aquifer Simulation Model RAQSIM, and a description of support programs applied in the Twin Platte - Middle Republican Study Area, Nebraska

    Science.gov (United States)

    Cady, R.E.; Peckenpaugh, J.M.

    1985-01-01

    RAQSIM, a generalized flow model of a groundwater system using finite-element methods, is documented to explain how it works and to demonstrate that it gives valid results. Three support programs that are used to compute recharge and discharge data required as input to RAQSIM are described. RAQSIM was developed to solve transient, two-dimensional, regional groundwater flow problems with isotropic or anisotropic conductance. The model can also simulate radially-symmetric flow to a well and steady-state flow. The mathematical basis, program structure, data input and output procedures, organization of data sets, and program features and options of RAQSIM are discussed. An example , containing listings of data and results and illustrating RAQSIM 's capabilities, is discussed in detail. Two test problems also are discussed comparing RAQSIM 's results with analytical procedures. The first support program described, the PET Program, uses solar radiation and other climatic data in the Jensen-Haise method to compute potential evapotranspiration. The second support program, the Soil-Water Program, uses output from the PET Program, soil characteristics, and the ratio of potential to actual evapotranspiration for each crop to compute infiltration, storage, and removal of water from the soil zone. The third program, the Recharge-Discharge Program, uses output from the Soil-Water Program together with other data to compute recharge and discharge from the groundwater flow system. For each support program, a program listing and examples of the data and results for the Twin Platte-Middle Republican study are provided. In addition, a brief discussion on how each program operates and on procedures for running and modifying these programs are presented. (Author 's abstract)

  10. The enhanced forest inventory and analysis program of the USDA forest service: historical perspective and announcements of statistical documentation

    Science.gov (United States)

    Ronald E. McRoberts; William A. Bechtold; Paul L. Patterson; Charles T. Scott; Gregory A. Reams

    2005-01-01

    The Forest Inventory and Analysis (FIA) program of the USDA Forest Service has initiated a transition from regional, periodic inventories to an enhanced national FIA program featuring annual measurement of a proportion of plots in each state, greater national consistency, and integration with the ground sampling component of the Forest Health Monitoring (FHM) program...

  11. Development of the biosphere code BIOMOD: final report

    International Nuclear Information System (INIS)

    Kane, P.

    1983-05-01

    Final report to DoE on the development of the biosphere code BIOMOD. The work carried out under the contract is itemised. Reference is made to the six documents issued along with the final report. These consist of two technical notes issued as interim consultative documents, a user's guide and a programmer's guide to BIOMOD, a database description, program test document and a technical note entitled ''BIOMOD - preliminary findings''. (author)

  12. Thermal hydraulics and mechanics core design programs

    International Nuclear Information System (INIS)

    Heinecke, J.

    1992-10-01

    The report documents the work performed within the Research and Development Task T hermal hydraulics and mechanics core design programs , funded by the German government. It contains the development of new codes, the extension of existing codes, the qualification and verification of codes and the development of a code library. The overall goal of this work was to adapt the system of thermal hydraulics and mechanics codes to the permanently growing requirements of the status of science and technology

  13. International training program: 3D S.UN.COP - Scaling, uncertainty and 3D thermal-hydraulics/neutron-kinetics coupled codes seminar

    International Nuclear Information System (INIS)

    Petruzzi, A.; D'Auria, F.; Bajs, T.; Reventos, F.

    2006-01-01

    Thermal-hydraulic system computer codes are extensively used worldwide for analysis of nuclear facilities by utilities, regulatory bodies, nuclear power plant designers and vendors, nuclear fuel companies, research organizations, consulting companies, and technical support organizations. The computer code user represents a source of uncertainty that can influence the results of system code calculations. This influence is commonly known as the 'user effect' and stems from the limitations embedded in the codes as well as from the limited capability of the analysts to use the codes. Code user training and qualification is an effective means for reducing the variation of results caused by the application of the codes by different users. This paper describes a systematic approach to training code users who, upon completion of the training, should be able to perform calculations making the best possible use of the capabilities of best estimate codes. In other words, the program aims at contributing towards solving the problem of user effect. The 3D S.UN.COP 2005 (Scaling, Uncertainty and 3D COuPled code calculations) seminar has been organized by University of Pisa and University of Zagreb as follow-up of the proposal to IAEA for the Permanent Training Course for System Code Users (D'Auria, 1998). It was recognized that such a course represented both a source of continuing education for current code users and a means for current code users to enter the formal training structure of a proposed 'permanent' stepwise approach to user training. The seminar-training was successfully held with the participation of 19 persons coming from 9 countries and 14 different institutions (universities, vendors, national laboratories and regulatory bodies). More than 15 scientists were involved in the organization of the seminar, presenting theoretical aspects of the proposed methodologies and holding the training and the final examination. A certificate (LA Code User grade) was released

  14. A program code generator for multiphysics biological simulation using markup languages.

    Science.gov (United States)

    Amano, Akira; Kawabata, Masanari; Yamashita, Yoshiharu; Rusty Punzalan, Florencio; Shimayoshi, Takao; Kuwabara, Hiroaki; Kunieda, Yoshitoshi

    2012-01-01

    To cope with the complexity of the biological function simulation models, model representation with description language is becoming popular. However, simulation software itself becomes complex in these environment, thus, it is difficult to modify the simulation conditions, target computation resources or calculation methods. In the complex biological function simulation software, there are 1) model equations, 2) boundary conditions and 3) calculation schemes. Use of description model file is useful for first point and partly second point, however, third point is difficult to handle for various calculation schemes which is required for simulation models constructed from two or more elementary models. We introduce a simulation software generation system which use description language based description of coupling calculation scheme together with cell model description file. By using this software, we can easily generate biological simulation code with variety of coupling calculation schemes. To show the efficiency of our system, example of coupling calculation scheme with three elementary models are shown.

  15. Exploring the Unknown: Selected Documents in the History of the U.S. Civil Space Program. Volume 4; Accessing Space

    Science.gov (United States)

    Logsdon, John M. (Editor); Williamson, Ray A. (Editor); Launius, Roger D. (Editor); Acker, Russell J. (Editor); Garber, Stephen J. (Editor); Friedman, Jonathan L. (Editor)

    1999-01-01

    The documents selected for inclusion in this volume are presented in four major chapters, each covering a particular aspect of access to space and the manner in which it has developed over time. These chapters focus on the evolution toward the giant Saturn V rocket, the development of the Space Shuttle, space transportation commercialization, and future space transportation possibilities. Each chapter in this volume is introduced by an overview essay, prepared by individuals who are particularly well qualified to write on the topic. In the main, these essays are intended to introduce and complement the documents in the chapter and to place them, for the most part, in a chronological and substantive context. Each essay contains references to the documents in the chapter it introduces, and many also contain references to documents in other chapters of the collection. These introductory essays are the responsibility of their individual authors, and the views and conclusions contained therein do not necessarily represent the opinions of either George Washington University or NASA.

  16. 77 FR 43535 - Grantee Codes for Certified Radiofrequency Equipment

    Science.gov (United States)

    2012-07-25

    ... FEDERAL COMMUNICATIONS COMMISSION 47 CFR Part 2 [FCC 12-60] Grantee Codes for Certified Radiofrequency Equipment AGENCY: Federal Communications Commission. ACTION: Final rule. SUMMARY: This document... authorization program for radiofrequency (RF) devices under part 2 of its rules. This program is one of the...

  17. Annual Coded Wire Tag Program; Oregon Missing Production Groups, 1994 Annual Report.

    Energy Technology Data Exchange (ETDEWEB)

    Garrison, Robert L.; Isaac, Dennis L.; Lewis, Mark A.

    1994-12-01

    The goal of this program is to develop the ability to estimate hatchery production survival values and evaluate effectiveness of Oregon hatcheries. To accomplish this goal. We are tagging missing production groups within hatcheries to assure each production group is identifiable to allow future evaluation upon recovery of tag data.

  18. CodeMaster--Automatic Assessment and Grading of App Inventor and Snap! Programs

    Science.gov (United States)

    von Wangenheim, Christiane Gresse; Hauck, Jean C. R.; Demetrio, Matheus Faustino; Pelle, Rafael; da Cruz Alves, Nathalia; Barbosa, Heliziane; Azevedo, Luiz Felipe

    2018-01-01

    The development of computational thinking is a major topic in K-12 education. Many of these experiences focus on teaching programming using block-based languages. As part of these activities, it is important for students to receive feedback on their assignments. Yet, in practice it may be difficult to provide personalized, objective and consistent…

  19. The Coded Schoolhouse: One-to-One Tablet Computer Programs and Urban Education

    Science.gov (United States)

    Crooks, Roderic N.

    2016-01-01

    Using a South Los Angeles charter school of approximately 650 students operated by a non-profit charter management organization (CMO) as the primary field site, this two-year, ethnographic research project examines the implementation of a one-to-one tablet computer program in a public high school. This dissertation examines the variety of ways…

  20. Registration document 2005

    International Nuclear Information System (INIS)

    2005-01-01

    This reference document of Gaz de France provides information and data on the Group activities in 2005: financial informations, business, activities, equipments factories and real estate, trade, capital, organization charts, employment, contracts and research programs. (A.L.B.)

  1. Forest Service programs, authorities, and relationships: A technical document supporting the 2000 USDA Forest Service RPA Assessment

    Science.gov (United States)

    Ervin G. Schuster; Michael A. Krebs

    2003-01-01

    The Forest and Rangeland Renewable Resources Planning Act (RPA) of 1974, as amended, directs the Forest Service to prepare and update a renewable resources assessment that would include "a description of Forest Service programs and responsibilities , their interrelationships, and the relationship of these programs and responsibilities to public and private...

  2. Input data instructions - simplified documentation of the computer program ANSYS. Report for 10 June 1976--31 March 1978

    International Nuclear Information System (INIS)

    Chang, P.Y.

    1978-02-01

    A simplified version of the input instructions for the computer program 'ANSYS' is presented for the non-linear elastoplastic analysis of a ship collision protection barrier structure. All essential information necessary for the grillage model are summarized while eliminating the instructions for other types of the problems. A benchmark example is given for checking the computer program

  3. Strategic environmental safety inspection for the National disposal program. Description of the inspection volume. Documentation for the scoping team

    International Nuclear Information System (INIS)

    2015-01-01

    The Strategic environmental safety inspection for the National disposal program covers the following topics: Legal framework: determination of the requirement for an environmental inspection program, coordination of the scoping team into the overall context; environmental targets; approach for assessment and evaluation of environmental impact, description of the inspection targets for the strategic environmental inspection; consideration of alternatives.

  4. Development of Regulatory Documents for Creation (Upgrade) of Physical Protection Systems under the Russian/American MPC and A Program

    International Nuclear Information System (INIS)

    Izmaylov, Alexandr V.; Babkin, Vladimir; Kurov, Valeriy; Piskarev, Alexander; O'Brien, Patricia E.; Wright, Troy L.; Schlegel, Stephen C.; Hazel, Michael J.; Miller, Daniel R.; Tuttle, John D.; Kovchegin, Dmitry

    2009-01-01

    The development of new or the upgrade of existing physical protection systems (PPS) for nuclear facilities involves a multi-step and multidimensional process. The process consists of conceptual design, design, and commissioning stages. The activities associated with each of these stages are governed by Russian government and agency regulations. To ensure a uniform approach to development or upgrading of PPS at Russian nuclear facilities, the development of a range of regulatory and methodological documents is necessary. Some issues of PPS development are covered by the regulatory documents developed by Rosatom, as well as other Russian agencies with nuclear facilities under their control. This regulatory development has been accomplished as part of the U.S.-Russian MPC and A cooperation or independently by the Russian Federation. While regulatory coverage is extensive, there are a number of issues such as vulnerability analysis, effectiveness assessment, upgrading PPS, and protection of information systems for PPS that require additional regulations be developed. This paper reports on the status of regulatory coverage for PPS development or upgrade, and outlines a new approach to regulatory document development. It describes the evolutionary process of regulatory development through experience gained in the design, development and implementation of PPS as well as experience gained through the cooperative efforts of Russian and U.S. experts involved the development of MPC and A regulations.

  5. A Semantic Analysis Method for Scientific and Engineering Code

    Science.gov (United States)

    Stewart, Mark E. M.

    1998-01-01

    This paper develops a procedure to statically analyze aspects of the meaning or semantics of scientific and engineering code. The analysis involves adding semantic declarations to a user's code and parsing this semantic knowledge with the original code using multiple expert parsers. These semantic parsers are designed to recognize formulae in different disciplines including physical and mathematical formulae and geometrical position in a numerical scheme. In practice, a user would submit code with semantic declarations of primitive variables to the analysis procedure, and its semantic parsers would automatically recognize and document some static, semantic concepts and locate some program semantic errors. A prototype implementation of this analysis procedure is demonstrated. Further, the relationship between the fundamental algebraic manipulations of equations and the parsing of expressions is explained. This ability to locate some semantic errors and document semantic concepts in scientific and engineering code should reduce the time, risk, and effort of developing and using these codes.

  6. Government programs for climate change mitigation in Japan. An analysis based on public budget documents and Government Project Review Sheets

    International Nuclear Information System (INIS)

    Kimura, Osamu

    2016-01-01

    The Japanese government has been spending huge public budgets for various programs to mitigate climate change, such as subsidy programs for energy efficient and renewable technologies, and R and D programs to develop innovative low carbon technologies. This report makes a comprehensive review of government projects and expenditure related to climate change mitigation in order to grasp their total expenditure and to analyze portfolio of supported technology and activity types, outcome, and the cost-effectiveness. It is estimated that the total expenditure for climate change mitigation excluding nuclear energy and forest sink projects amounts to 4.8 trillion JPY (approximately 40 billion USD) in the period of 2008 to 2014. 40% of the total expenditure went to only three largest programs, namely the Eco Car Subsidy, the Eco Point Programs for Appliances and Houses, all of which have gone through virtually no or only poor evaluations by the implementing ministries. While some programs had decent cost-effectiveness of reducing carbon dioxide emission at below 10,000 JPY/t-CO 2 (approximately 90 USD), there are also programs with very low cost-effectiveness at more than 100,000 JPY/t-CO 2 . Moreover, all of the evaluation was based on 'gross' reduction, not on 'net' of freeriders, rebound and other factors, which may lead to overestimation of performances. The result shows the need for a much larger resource for evaluation activities by the government. (author)

  7. Standardization Documents

    Science.gov (United States)

    2011-08-01

    Specifications and Standards; Guide Specifications; CIDs; and NGSs . Learn. Perform. Succeed. STANDARDIZATION DOCUMENTS Federal Specifications Commercial...national or international standardization document developed by a private sector association, organization, or technical society that plans ...Maintain lessons learned • Examples: Guidance for application of a technology; Lists of options Learn. Perform. Succeed. DEFENSE HANDBOOK

  8. Computer programs in BASIC language for graphite furnace atomic absorption using the method of additions. Part 2. Documentation

    International Nuclear Information System (INIS)

    Boyle, W.G. Jr.; Ryan, D.P.

    1979-08-01

    There are four computer programs, written in the BASIC language, used for taking and processing data from an atomic absorption spectrophotometer using the graphite furnace and the method of additions for calibration. The programs chain to each other and are divided into logical sections that have been flow-charted. The chaining sequences, general features, structure, order of subroutines and functions, and the storage of data are discussed. In addition, variables are listed and defined, and a complete listing of each program with a symbol occurrence table is provided

  9. The GEM code. A simulation program for the evaporation and the fission process of an excited nucleus

    Energy Technology Data Exchange (ETDEWEB)

    Furihata, Shiori [Mitsubishi Research Institute Inc., Tokyo (Japan); Niita, Koji [Research Organization for Information Science and Technology, Tokai, Ibaraki (Japan); Meigo, Shin-ichiro; Ikeda, Yujiro; Maekawa, Fujio [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2001-03-01

    The GEM code is a simulation program which describes the de-excitation process of an excited nucleus, which is based on the Generalized Evaporation Model and the Atchison fission model. It has been shown that the combination of the Bertini intranuclear cascade model and GEM accurately predicts the cross sections of light fragments, such as Be produced from the proton-induced reactions. It has also been shown that the use of the reevaluated parameters in the Atchison model improves predictions of cross sections of fission fragments produced from the proton-induced reaction on Au. In this report, we present details and the usage of the GEM code. Furthermore, the results of benchmark calculations are shown by using the combination of the Bertini intranuclear cascade model and the GEM code (INC/GEM). Neutron spectra and isotope production cross sections from the reactions on various targets irradiated by protons are calculated with INC/GEM. Those results are compared with experimental data as well as the calculation results with LAHET. INC/GEM reproduces the experiments of double differential neutron emissions from the reaction on Al and Pb. The isotopic distributions for He, Li, and Be produced from the reaction on Ag are in good agreement with experimental data within 50%, although INC/GEM underestimates those of heavier nuclei than O. It is also shown that the predictions with INC/GEM for isotope production of light fragments, such as Li and Be, are better than those calculation with LAHET, particularly for heavy target. INC/GEM also gives better estimates of the cross sections of fission products than LAHET. (author)

  10. Student Model Tools Code Release and Documentation

    DEFF Research Database (Denmark)

    Johnson, Matthew; Bull, Susan; Masci, Drew

    of its strengths and areas of improvement (Section 6). Several key appendices are attached to this report including user manuals for teacher and students (Appendix 3). Fundamentally, all relevant information is included in the report for those wishing to do further development work with the tool...

  11. Melt/concrete interactions: the Sandia experimental program, model development, and code comparison test

    International Nuclear Information System (INIS)

    Powers, D.A.; Muir, J.F.

    1979-01-01

    High temperature melt/concrete interactions have been studied both experimentally and analytically at Sandia under sponsorship of Reactor Safety Research of the US Nuclear Regulatory Commission. The purpose of these studies has been to develop an understanding of these interactions suitable for risk assessment. Results of the experimental program are summarized and a computer model of melt/concrete interactions is described. A melt/concrete interaction test that will allow this and other models of the interaction to be compared is also described

  12. Guidance document for the preparation of waste management plans for the Environmental Restoration Program at Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Clark, C. Jr.

    1993-07-01

    A project waste management (WM) plan is required for all Oak Ridge National Laboratory (ORNL) Environmental Restoration (ER) Program remedial investigation, decommission and decontamination (D ampersand D), and remedial action (RA) activities. The project WM plan describes the strategy for handling, packaging, treating, transporting, characterizing, storing, and/or disposing of waste produced as part of ORNL ER Program activities. The project WM plan also contains a strategy for ensuring worker and environmental protection during WM activities

  13. Computer model for refinery operations with emphasis on jet fuel production. Volume 3: Detailed systems and programming documentation

    Science.gov (United States)

    Dunbar, D. N.; Tunnah, B. G.

    1978-01-01

    The FORTRAN computing program predicts flow streams and material, energy, and economic balances of a typical petroleum refinery, with particular emphasis on production of aviation turbine fuels of varying end point and hydrogen content specifications. The program has a provision for shale oil and coal oil in addition to petroleum crudes. A case study feature permits dependent cases to be run for parametric or optimization studies by input of only the variables which are changed from the base case.

  14. An Optimal Linear Coding for Index Coding Problem

    OpenAIRE

    Pezeshkpour, Pouya

    2015-01-01

    An optimal linear coding solution for index coding problem is established. Instead of network coding approach by focus on graph theoric and algebraic methods a linear coding program for solving both unicast and groupcast index coding problem is presented. The coding is proved to be the optimal solution from the linear perspective and can be easily utilize for any number of messages. The importance of this work is lying mostly on the usage of the presented coding in the groupcast index coding ...

  15. Conceptual Design of Object Oriented Program (OOP) for Pilot Code of Two-Fluid, Three-field Model with C++ 6.0

    International Nuclear Information System (INIS)

    Chung, Bub Dong; Lee, Young Jin

    2006-01-01

    Engineering software for design purpose in nuclear industries have been developed since early 1970s, and well established in 1980s. The most popular and common language for the software development has been FORTRAN series, until the more sophisticated GUI and software coupling is needed. The advanced computer language, such as C++, C has been developed to help the programming for the easy GUI need and reuse of well developed routines, with adopting the objective oriented program. A recent trend of programming becomes objective-oriented since the results are often more intuitive and easier to maintain than procedure program. The main motivation of this work is to capture objective oriented concepts for conventional safety analysis programs which consist of many functions and procedure oriented structures. In this work, the new objective programming with C++ 6.0 language has been tried for the PILOT code written in FORTRAN language, and conceptual OOP design of the system safety analysis code has been done

  16. Establishing a communications link between two different, incompatible, personal computers: with practical examples and illustrations and program code.

    Science.gov (United States)

    Davidson, R W

    1985-01-01

    The increasing need to communicate to exchange data can be handled by personal microcomputers. The necessity for the transference of information stored in one type of personal computer to another type of personal computer is often encountered in the process of integrating multiple sources of information stored in different and incompatible computers in Medical Research and Practice. A practical example is demonstrated with two relatively inexpensive commonly used computers, the IBM PC jr. and the Apple IIe. The basic input/output (I/O) interface chip for serial communication for each computer are joined together using a Null connector and cable to form a communications link. Using BASIC (Beginner's All-purpose Symbolic Instruction Code) Computer Language and the Disk Operating System (DOS) the communications handshaking protocol and file transfer is established between the two computers. The BASIC programming languages used are Applesoft (Apple Personal Computer) and PC BASIC (IBM Personal computer).

  17. Quality assurance application in the documentation of nuclear research reactor

    International Nuclear Information System (INIS)

    Nababan, N.

    1999-01-01

    For each nuclear research reactor a document control system should be established and should be provide for preparation, review, approval, issuance, distribution, revision and validation (where appropriate) of documents essential to the management, performance and verification of work. In the document control system the responsibilities for each participating organization or individual should be defined in writing. The types of document include, but are not limited to document comprising the QA program, safety requirements, maintenance and operating procedures, inspection instructions, inspection and test reports, assessment reports, drawings, data files, calculations, specifications, computer codes, purchase orders and related documents, vendor supplied documents and work instruction. Management should identify the need for documents and should provide guidance to the organizations and people preparing them. The guidance should cover the status, scope and contents and the policies, standards and codes witch apply. It should also explain the need for feedback of experience. Plant modification or the results of assessments could also give rise to the need for a new document

  18. Systems Analysis Programs for Hands-on Integrated Reliability Evaluations (SAPHIRE) Code Reference Manual

    Energy Technology Data Exchange (ETDEWEB)

    C. L. Smith; K. J. Kvarfordt; S. T. Wood

    2008-08-01

    The Systems Analysis Programs for Hands-on Integrated Reliability Evaluations (SAPHIRE) is a software application developed for performing a complete probabilistic risk assessment (PRA) using a personal computer. SAPHIRE is funded by the U.S. Nuclear Regulatory Commission (NRC) and developed by the Idaho National Laboratory (INL). The INL's primary role in this project is that of software developer. However, the INL also plays an important role in technology transfer by interfacing and supporting SAPHIRE users comprised of a wide range of PRA practitioners from the NRC, national laboratories, the private sector, and foreign countries. SAPHIRE can be used to model a complex system’s response to initiating events, quantify associated damage outcome frequencies, and identify important contributors to this damage (Level 1 PRA) and to analyze containment performance during a severe accident and quantify radioactive releases (Level 2 PRA). It can be used for a PRA evaluating a variety of operating conditions, for example, for a nuclear reactor at full power, low power, or at shutdown conditions. Furthermore, SAPHIRE can be used to analyze both internal and external initiating events and has special features for transforming models built for internal event analysis to models for external event analysis. It can also be used in a limited manner to quantify risk in terms of release consequences to both the public and the environment (Level 3 PRA). SAPHIRE includes a separate module called the Graphical Evaluation Module (GEM). GEM provides a highly specialized user interface with SAPHIRE that automates SAPHIRE process steps for evaluating operational events at commercial nuclear power plants. Using GEM, an analyst can estimate the risk associated with operational events in a very efficient and expeditious manner. This reference guide will introduce the SAPHIRE Version 7.0 software. A brief discussion of the purpose and history of the software is included along with

  19. Systems Analysis Programs for Hands-on Integrated Reliability Evaluations (SAPHIRE) Code Reference Manual

    Energy Technology Data Exchange (ETDEWEB)

    C. L. Smith; K. J. Kvarfordt; S. T. Wood

    2006-07-01

    The Systems Analysis Programs for Hands-on Integrated Reliability Evaluations (SAPHIRE) is a software application developed for performing a complete probabilistic risk assessment (PRA) using a personal computer. SAPHIRE is funded by the U.S. Nuclear Regulatory Commission (NRC) and developed by the Idaho National Laboratory (INL). The INL's primary role in this project is that of software developer. However, the INL also plays an important role in technology transfer by interfacing and supporting SAPHIRE users comprised of a wide range of PRA practitioners from the NRC, national laboratories, the private sector, and foreign countries. SAPHIRE can be used to model a complex system’s response to initiating events, quantify associated damage outcome frequencies, and identify important contributors to this damage (Level 1 PRA) and to analyze containment performance during a severe accident and quantify radioactive releases (Level 2 PRA). It can be used for a PRA evaluating a variety of operating conditions, for example, for a nuclear reactor at full power, low power, or at shutdown conditions. Furthermore, SAPHIRE can be used to analyze both internal and external initiating events and has special features for ansforming models built for internal event analysis to models for external event analysis. It can also be used in a limited manner to quantify risk in terms of release consequences to both the public and the environment (Level 3 PRA). SAPHIRE includes a separate module called the Graphical Evaluation Module (GEM). GEM provides a highly specialized user interface with SAPHIRE that automates SAPHIRE process steps for evaluating operational events at commercial nuclear power plants. Using GEM, an analyst can estimate the risk associated with operational events in a very efficient and expeditious manner. This reference guide will introduce the SAPHIRE Version 7.0 software. A brief discussion of the purpose and history of the software is included along with

  20. Description of the TREBIL, CRESSEX and STREUSL computer programs, that belongs to RALLY computer code pack for the analysis of reliability systems

    International Nuclear Information System (INIS)

    Fernandes Filho, T.L.

    1982-11-01

    The RALLY computer code pack (RALLY pack) is a set of computer codes destinate to the reliability of complex systems, aiming to a risk analysis. Three of the six codes, are commented, presenting their purpose, input description, calculation methods and results obtained with each one of those computer codes. The computer codes are: TREBIL, to obtain the fault tree logical equivalent; CRESSEX, to obtain the minimal cut and the punctual values of the non-reliability and non-availability of the system; and STREUSL, for the dispersion calculation of those values around the media. In spite of the CRESSEX, in its version available at CNEN, uses a little long method to obtain the minimal cut in an HB-CNEN system, the three computer programs show good results, mainly the STREUSL, which permits the simulation of various components. (E.G.) [pt

  1. Development of a simple detector response function generation program: The CEARDRFs code

    Energy Technology Data Exchange (ETDEWEB)

    Wang Jiaxin, E-mail: jwang3@ncsu.edu [Center for Engineering Applications of Radioisotopes (CEAR), Department of Nuclear Engineering, North Carolina State University, Raleigh, NC 27695 (United States); Wang Zhijian; Peeples, Johanna [Center for Engineering Applications of Radioisotopes (CEAR), Department of Nuclear Engineering, North Carolina State University, Raleigh, NC 27695 (United States); Yu Huawei [Center for Engineering Applications of Radioisotopes (CEAR), Department of Nuclear Engineering, North Carolina State University, Raleigh, NC 27695 (United States); College of Geo-Resources and Information, China University of Petroleum, Qingdao, Shandong 266555 (China); Gardner, Robin P. [Center for Engineering Applications of Radioisotopes (CEAR), Department of Nuclear Engineering, North Carolina State University, Raleigh, NC 27695 (United States)

    2012-07-15

    A simple Monte Carlo program named CEARDRFs has been developed to generate very accurate detector response functions (DRFs) for scintillation detectors. It utilizes relatively rigorous gamma-ray transport with simple electron transport, and accounts for two phenomena that have rarely been treated: scintillator non-linearity and the variable flat continuum part of the DRF. It has been proven that these physics and treatments work well for 3 Multiplication-Sign 3 Double-Prime and 6 Multiplication-Sign 6 Double-Prime cylindrical NaI detector in CEAR's previous work. Now this approach has been expanded to cover more scintillation detectors with various common shapes and sizes. Benchmark experiments of 2 Multiplication-Sign 2 Double-Prime cylindrical BGO detector and 2 Multiplication-Sign 4 Multiplication-Sign 16 Double-Prime rectangular NaI detector have been carried out at CEAR with various radiactive sources. The simulation results of CEARDRFs have also been compared with MCNP5 calculations. The benchmark and comparison show that CEARDRFs can generate very accurate DRFs (more accurate than MCNP5) at a very fast speed (hundred times faster than MCNP5). The use of this program can significantly increase the accuracy of applications relying on detector spectroscopy like prompt gamma-ray neutron activation analysis, X-ray fluorescence analysis, oil well logging and homeland security. - Highlights: Black-Right-Pointing-Pointer CEARDRF has been developed to generate detector response functions (DRFs) for scintillation detectors a. Black-Right-Pointing-Pointer Generated DRFs are very accurate. Black-Right-Pointing-Pointer Simulation speed is hundreds of times faster than MCNP5. Black-Right-Pointing-Pointer It utilizes rigorous gamma-ray transport with simple electron transport. Black-Right-Pointing-Pointer It also accounts for scintillator non-linearity and the variable flat continuum part.

  2. Development of a simple detector response function generation program: The CEARDRFs code

    International Nuclear Information System (INIS)

    Wang Jiaxin; Wang Zhijian; Peeples, Johanna; Yu Huawei; Gardner, Robin P.

    2012-01-01

    A simple Monte Carlo program named CEARDRFs has been developed to generate very accurate detector response functions (DRFs) for scintillation detectors. It utilizes relatively rigorous gamma-ray transport with simple electron transport, and accounts for two phenomena that have rarely been treated: scintillator non-linearity and the variable flat continuum part of the DRF. It has been proven that these physics and treatments work well for 3×3″ and 6×6″ cylindrical NaI detector in CEAR's previous work. Now this approach has been expanded to cover more scintillation detectors with various common shapes and sizes. Benchmark experiments of 2×2″ cylindrical BGO detector and 2×4×16″ rectangular NaI detector have been carried out at CEAR with various radiactive sources. The simulation results of CEARDRFs have also been compared with MCNP5 calculations. The benchmark and comparison show that CEARDRFs can generate very accurate DRFs (more accurate than MCNP5) at a very fast speed (hundred times faster than MCNP5). The use of this program can significantly increase the accuracy of applications relying on detector spectroscopy like prompt gamma-ray neutron activation analysis, X-ray fluorescence analysis, oil well logging and homeland security. - Highlights: ► CEARDRF has been developed to generate detector response functions (DRFs) for scintillation detectors a. ► Generated DRFs are very accurate. ► Simulation speed is hundreds of times faster than MCNP5. ► It utilizes rigorous gamma-ray transport with simple electron transport. ► It also accounts for scintillator non-linearity and the variable flat continuum part.

  3. Vocable Code

    DEFF Research Database (Denmark)

    Soon, Winnie; Cox, Geoff

    2018-01-01

    a computational and poetic composition for two screens: on one of these, texts and voices are repeated and disrupted by mathematical chaos, together exploring the performativity of code and language; on the other, is a mix of a computer programming syntax and human language. In this sense queer code can...... be understood as both an object and subject of study that intervenes in the world’s ‘becoming' and how material bodies are produced via human and nonhuman practices. Through mixing the natural and computer language, this article presents a script in six parts from a performative lecture for two persons...

  4. Training program for energy conservation in new building construction. Volume III. Energy conservation technology for plan examiners and code administrators. Energy Conservation Technology Series 200

    Energy Technology Data Exchange (ETDEWEB)

    None

    1977-12-01

    Under the sponsorship of the United States Department of Energy, a Model Code for Energy Conservation in New Building Construction has been developed by those national organizations primarily concerned with the development and promulgation of model codes. The technical provisions are based on ASHRAE Standard 90-75 and are intended for use by state and local officials. The subject of regulation of new building construction to assure energy conservation is recognized as one in which code officials have not had previous exposure. It was also determined that application of the model code would be made at varying levels by officials with both a specific requirement for knowledge and a differing degree of prior training in the state-of-the-art. Therefore, a training program and instructional materials were developed for code officials to assist them in the implementation and enforcement of energy efficient standards and codes. The training program for Energy Conservation Tehnology for Plan Examiners and Code Administrators (ECT Series 200) is presented.

  5. Maury Documentation

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Supporting documentation for the Maury Collection of marine observations. Includes explanations from Maury himself, as well as guides and descriptions by the U.S....

  6. Documentation Service

    International Nuclear Information System (INIS)

    Charnay, J.; Chosson, L.; Croize, M.; Ducloux, A.; Flores, S.; Jarroux, D.; Melka, J.; Morgue, D.; Mottin, C.

    1998-01-01

    This service assures the treatment and diffusion of the scientific information and the management of the scientific production of the institute as well as the secretariat operation for the groups and services of the institute. The report on documentation-library section mentions: the management of the documentation funds, search in international databases (INIS, Current Contents, Inspects), Pret-Inter service which allows accessing documents through DEMOCRITE network of IN2P3. As realizations also mentioned are: the setup of a video, photo database, the Web home page of the institute's library, follow-up of digitizing the document funds by integrating the CD-ROMs and diskettes, electronic archiving of the scientific production, etc

  7. QA programme documentation

    International Nuclear Information System (INIS)

    Scheibelt, L.

    1980-01-01

    The present paper deals with the following topics: The need for a documented Q.A. program; Establishing a Q.A. program; Q.A. activities; Fundamental policies; Q.A. policies; Quality objectives Q.A. manual. (orig./RW)

  8. Speech coding

    Energy Technology Data Exchange (ETDEWEB)

    Ravishankar, C., Hughes Network Systems, Germantown, MD

    1998-05-08

    coding techniques are equally applicable to any voice signal whether or not it carries any intelligible information, as the term speech implies. Other terms that are commonly used are speech compression and voice compression since the fundamental idea behind speech coding is to reduce (compress) the transmission rate (or equivalently the bandwidth) And/or reduce storage requirements In this document the terms speech and voice shall be used interchangeably.

  9. Qualification testing program plan for SIMMER. A computer code for LMFBR disrupted core analysis

    International Nuclear Information System (INIS)

    Basdekas, D.L.; Silberberg, M.; Curtis, R.T.; Kelber, C.N.

    1978-07-01

    The objective of SIMMER qualification testing program is to assure that the mathematical models and input parameters are derived from experimental data, which, on the basis of criteria still to be established, are representative of the phenomena and processes governing the progression of a CDA in an LMFBR. At the present time, the work to meet this objective can be classified into three general task areas as they relate to the use of SIMMER in CDA analysis: (1) The whole-core energetic disassembly accident, or the ''vessel problem'': The objective here is to predict the partition of the total energy release, by a postulated severe power excursion, between the primary containment and the energy absorbed through nondestructive dissipative processes. (2) Single subassembly accident: The objective here is to determine the pertinent phenomena and to develop the capability to assess the significance and likelihood that such accidents might propagate to involvement of larger fraction of the core. (3) The whole-core transition phase accident: The objective here is to advance the understanding of the phenomena and processes involved, so that reliable predictions can be made of the possible consequences of a CDA and the potential for further nuclear excursions through recriticality

  10. Computerising documentation

    International Nuclear Information System (INIS)

    Anon.

    1992-01-01

    The nuclear power generation industry is faced with public concern and government pressures over safety, efficiency and risk. Operators throughout the industry are addressing these issues with the aid of a new technology - technical document management systems (TDMS). Used for strategic and tactical advantage, the systems enable users to scan, archive, retrieve, store, edit, distribute worldwide and manage the huge volume of documentation (paper drawings, CAD data and film-based information) generated in building, maintaining and ensuring safety in the UK's power plants. The power generation industry has recognized that the management and modification of operation critical information is vital to the safety and efficiency of its power plants. Regulatory pressure from the Nuclear Installations Inspectorate (NII) to operate within strict safety margins or lose Site Licences has prompted the need for accurate, up-to-data documentation. A document capture and management retrieval system provides a powerful cost-effective solution, giving rapid access to documentation in a tightly controlled environment. The computerisation of documents and plans is discussed in this article. (Author)

  11. Efficiently mobil. The action program for mobility management. Program documentation 2008-2010; effizient mobil. Das Aktionsprogramm fuer Mobilitaetsmanagement. Programmdokumentation 2008-2010

    Energy Technology Data Exchange (ETDEWEB)

    Haendschke, Stefan; Kraehe, Melanie [comps.

    2010-12-15

    An enhancement of the energy efficiency has to enable a satisfaction of needs with less energy expenditure. For this, mobility management is a prime example. This will provide a contribution to energy saving and climate protection. The contribution under consideration documents the results and a collection of possible measures for mobility management.

  12. Dosimetry and health effects self-teaching curriculum: illustrative problems to supplement the user's manual for the Dosimetry and Health Effects Computer Code

    International Nuclear Information System (INIS)

    Runkle, G.E.; Finley, N.C.

    1983-03-01

    This document contains a series of sample problems for the Dosimetry and Health Effects Computer Code to be used in conjunction with the user's manual (Runkle and Cranwell, 1982) for the code. This code was developed at Sandia National Laboratories for the Risk Methodology for Geologic Disposal of Radioactive Waste program (NRC FIN A-1192). The purpose of this document is to familiarize the user with the code, its capabilities, and its limitations. When the user has finished reading this document, he or she should be able to prepare data input for the Dosimetry and Health Effects code and have some insights into interpretation of the model output

  13. The Effects of a Statewide Evaluation Initiative in Gifted Education on Practitioner Knowledge, Concerns, and Program Documentation

    Science.gov (United States)

    Robinson, Ann; Cotabish, Alicia; Wood, Betty K.; O'Tuel, Fran S.

    2014-01-01

    When well-considered and grounded in current knowledge, program evaluations of services to gifted learners can be a powerful tool for increasing practitioners' knowledge and self-efficacy, and for effecting positive programmatic changes. The Arkansas Evaluation Initiative (AEI) in Gifted Education, a Jacob K. Javits-funded project, was implemented…

  14. Gamma ray shielding study of barium-bismuth-borosilicate glasses as transparent shielding materials using MCNP-4C code, XCOM program, and available experimental data

    Energy Technology Data Exchange (ETDEWEB)

    Bagheri, Reza; Yousefinia, Hassan [Nuclear Fuel Cycle Research School (NFCRS), Nuclear Science and Technology Research Institute (NSTRI), Atomic Energy Organization of Iran, Tehran (Iran, Islamic Republic of); Moghaddam, Alireza Khorrami [Radiology Department, Paramedical Faculty, Mazandaran University of Medical Sciences, Sari (Iran, Islamic Republic of)

    2017-02-15

    In this work, linear and mass attenuation coefficients, effective atomic number and electron density, mean free paths, and half value layer and 10th value layer values of barium-bismuth-borosilicate glasses were obtained for 662 keV, 1,173 keV, and 1,332 keV gamma ray energies using MCNP-4C code and XCOM program. Then obtained data were compared with available experimental data. The MCNP-4C code and XCOM program results were in good agreement with the experimental data. Barium-bismuth-borosilicate glasses have good gamma ray shielding properties from the shielding point of view.

  15. Gamma Ray Shielding Study of Barium–Bismuth–Borosilicate Glasses as Transparent Shielding Materials using MCNP-4C Code, XCOM Program, and Available Experimental Data

    Directory of Open Access Journals (Sweden)

    Reza Bagheri

    2017-02-01

    Full Text Available In this work, linear and mass attenuation coefficients, effective atomic number and electron density, mean free paths, and half value layer and 10th value layer values of barium–bismuth–borosilicate glasses were obtained for 662 keV, 1,173 keV, and 1,332 keV gamma ray energies using MCNP-4C code and XCOM program. Then obtained data were compared with available experimental data. The MCNP-4C code and XCOM program results were in good agreement with the experimental data. Barium–bismuth–borosilicate glasses have good gamma ray shielding properties from the shielding point of view.

  16. International training program in support of safety analysis. 3D S.UN.COP-scaling uncertainty and 3D thermal-hydraulics/neutron-kinetics coupled codes seminars

    International Nuclear Information System (INIS)

    Petruzzi, Alessandro; D'Auria, Francesco; Bajs, Tomislav; Reventos, Francesc; Hassan, Yassin

    2007-01-01

    Thermal-hydraulic system computer codes are extensively used worldwide for analysis of nuclear facilities by utilities, regulatory bodies, nuclear power plant designers and vendors, nuclear fuel companies, research organizations, consulting companies, and technical support organizations. The computer code user represents a source of uncertainty that can influence the results of system code calculations. This influence is commonly known as the user effect' and stems from the limitations embedded in the codes as well as from the limited capability of the analysis to use the codes. Code user training and qualification is an effective means for reducing the variation of results caused by the application of the codes by different users. This paper describes a systematic approach to training code users who, upon completion of the training, should be able to perform calculations making the best possible use of the capabilities of best estimate codes. In other words, the program aims at contributing towards solving the problem of user effect. The 3D S.UN.COP (Scaling, Uncertainty and 3D COuPled code calculations) seminars have been organized as follow-up of the proposal to IAEA for the Permanent Training Course for System Code Users. Six seminars have been held at University of Pisa (2003, 2004), at The Pennsylvania State University (2004), at University of Zagreb (2005), at the School of Industrial Engineering of Barcelona (January-February 2006) and in Buenos Aires, Argentina (October 2006), being this last one requested by ARN (Autoridad Regulatoria Nuclear), NA-SA (Nucleoelectrica Argentina S.A) and CNEA (Comision Nacional de Energia Atomica). It was recognized that such courses represented both a source of continuing education for current code users and a mean for current code users to enter the formal training structure of a proposed 'permanent' stepwise approach to user training. The 3D S.UN.COP 2006 in Barcelona was successfully held with the attendance of 33

  17. International Training Program in Support of Safety Analysis: 3D S.UN.COP-Scaling, Uncertainty and 3D Thermal-Hydraulics/Neutron-Kinetics Coupled Codes Seminars

    International Nuclear Information System (INIS)

    Petruzzi, Alessandro; D'Auria, Francesco; Bajs, Tomislav; Reventos, Francesc

    2006-01-01

    Thermal-hydraulic system computer codes are extensively used worldwide for analysis of nuclear facilities by utilities, regulatory bodies, nuclear power plant designers and vendors, nuclear fuel companies, research organizations, consulting companies, and technical support organizations. The computer code user represents a source of uncertainty that can influence the results of system code calculations. This influence is commonly known as the 'user effect' and stems from the limitations embedded in the codes as well as from the limited capability of the analysts to use the codes. Code user training and qualification is an effective means for reducing the variation of results caused by the application of the codes by different users. This paper describes a systematic approach to training code users who, upon completion of the training, should be able to perform calculations making the best possible use of the capabilities of best estimate codes. In other words, the program aims at contributing towards solving the problem of user effect. The 3D S.UN.COP (Scaling, Uncertainty and 3D COuPled code calculations) seminars have been organized as follow-up of the proposal to IAEA for the Permanent Training Course for System Code Users [1]. Five seminars have been held at University of Pisa (2003, 2004), at The Pennsylvania State University (2004), at University of Zagreb (2005) and at the School of Industrial Engineering of Barcelona (2006). It was recognized that such courses represented both a source of continuing education for current code users and a mean for current code users to enter the formal training structure of a proposed 'permanent' stepwise approach to user training. The 3D S.UN.COP 2006 was successfully held with the attendance of 33 participants coming from 18 countries and 28 different institutions (universities, vendors, national laboratories and regulatory bodies). More than 30 scientists (coming from 13 countries and 23 different institutions) were

  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. 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

  20. 76 FR 13101 - Building Energy Codes Program: Presenting and Receiving Comments to DOE Proposed Changes to the...

    Science.gov (United States)

    2011-03-10

    ... DEPARTMENT OF ENERGY 10 CFR Part 430 [Docket No. EERE-2011-BT-BC-0009] Building Energy Codes.... The IgCC is intended to provide a green model building code provisions for new and existing commercial... Code (IgCC) AGENCY: Office of Energy Efficiency and Renewable Energy, Department of Energy. ACTION...

  1. The KFA-Version of the high-energy transport code HETC and the generalized evaluation code SIMPEL

    International Nuclear Information System (INIS)

    Cloth, P.; Filges, D.; Sterzenbach, G.; Armstrong, T.W.; Colborn, B.L.

    1983-03-01

    This document describes the updates that have been made to the high-energy transport code HETC for use in the German spallation-neutron source project SNQ. Performance and purpose of the subsidiary code SIMPEL that has been written for general analysis of the HETC output are also described. In addition means of coupling to low energy transport programs, such as the Monte-Carlo code MORSE is provided. As complete input descriptions for HETC and SIMPEL are given together with a sample problem, this document can serve as a user's manual for these two codes. The document is also an answer to the demand that has been issued by a greater community of HETC users on the ICANS-IV meeting, Oct 20-24 1980, Tsukuba-gun, Japan for a complete description of at least one single version of HETC among the many different versions that exist. (orig.)

  2. Applications for electronic documents

    International Nuclear Information System (INIS)

    Beitel, G.A.

    1995-01-01

    This paper discusses the application of electronic media to documents, specifically Safety Analysis Reports (SARs), prepared for Environmental Restoration and Waste Management (ER ampersand WM) programs being conducted for the Department of Energy (DOE) at the Idaho National Engineering Laboratory (INEL). Efforts are underway to upgrade our document system using electronic format. To satisfy external requirements (DOE, State, and Federal), ER ampersand WM programs generate a complement of internal requirements documents including a SAR and Technical Safety Requirements along with procedures and training materials. Of interest, is the volume of information and the difficulty in handling it. A recently prepared ER ampersand WM SAR consists of 1,000 pages of text and graphics; supporting references add 10,000 pages. Other programmatic requirements documents consist of an estimated 5,000 pages plus references

  3. NATIONAL QUESTION IN PROGRAM DOCUMENTS OF UKRAINIAN POLITICAL ASSOCIATIONS OF CONSERVATIVE-CLERICAL DIRECTION IN WESTERN UKRAINE (1920-1930

    Directory of Open Access Journals (Sweden)

    Ruslan Demczyszak

    2016-12-01

    Full Text Available In the article activity of Ukrainian parties and social and political associations of conservative-clerical direction in Western Ukraine –UKA, UKS, UKNP (UNA– is explored. The place of national question in their programs is found out. The attitude to the slogan of autonomy of Western Ukraine within Poland and possible independence of Ukraine was researched. It analyzes the decision of party conferences, discussions on this subject on the pages of print media related to political organizations. Looks to character of Ukrainian-Polish relations of metropolitan Andrey Sheptytskyi and bishop Hrygory Khomyshyn are exposed.

  4. International Training Program: 3D S. Un. Cop - Scaling, Uncertainty and 3D Thermal-Hydraulics/Neutron-Kinetics Coupled Codes Seminar

    International Nuclear Information System (INIS)

    Pertuzzi, A.; D'Auria, F.; Bajs, T.; Reventos, F.

    2006-01-01

    Thermal-hydraulic system computer codes are extensively used worldwide for analysis of nuclear facilities by utilities, regulatory bodies, nuclear power plant designers and vendors, nuclear fuel companies, research organizations, consulting companies, and technical support organizations. The computer code user represents a source of uncertainty that can influence the results of system code calculations. This influence is commonly known as the 'user effect' and stems from the limitations embedded in the codes as well as from the limited capability of the analysts to use the codes. Code user training and qualification is an effective means for reducing the variation of results caused by the application of the codes by different users. This paper describes a systematic approach to training code users who, upon completion of the training, should be able to perform calculations making the best possible use of the capabilities of best estimate codes. In other words, the program aims at contributing towards solving the problem of user effect. The 3D S.UN.COP (Scaling, Uncertainty and 3D COuPled code calculations) seminars have been organized as follow-up of the proposal to IAEA for the Permanent Training Course for System Code Users (D'Auria, 1998). Four seminars have been held at University of Pisa (2003, 2004), at The Pennsylvania State University (2004) and at University of Zagreb (2005). It was recognized that such courses represented both a source of continuing education for current code users and a mean for current code users to enter the formal training structure of a proposed 'permanent' stepwise approach to user training. The 3D S.UN.COP 2005 was successfully held with the participation of 19 persons coming from 9 countries and 14 different institutions (universities, vendors, national laboratories and regulatory bodies). More than 15 scientists were involved in the organization of the seminar, presenting theoretical aspects of the proposed methodologies and

  5. Creating Tomorrow's Technologists: Contrasting Information Technology Curriculum in North American Library and Information Science Graduate Programs against Code4lib Job Listings

    Science.gov (United States)

    Maceli, Monica

    2015-01-01

    This research study explores technology-related course offerings in ALA-accredited library and information science (LIS) graduate programs in North America. These data are juxtaposed against a text analysis of several thousand LIS-specific technology job listings from the Code4lib jobs website. Starting in 2003, as a popular library technology…

  6. Refactoring test code

    NARCIS (Netherlands)

    A. van Deursen (Arie); L.M.F. Moonen (Leon); A. van den Bergh; G. Kok

    2001-01-01

    textabstractTwo key aspects of extreme programming (XP) are unit testing and merciless refactoring. Given the fact that the ideal test code / production code ratio approaches 1:1, it is not surprising that unit tests are being refactored. We found that refactoring test code is different from

  7. Code Cactus; Code Cactus

    Energy Technology Data Exchange (ETDEWEB)

    Fajeau, M; Nguyen, L T; Saunier, J [Commissariat a l' Energie Atomique, Centre d' Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France)

    1966-09-01

    This code handles the following problems: -1) Analysis of thermal experiments on a water loop at high or low pressure; steady state or transient behavior; -2) Analysis of thermal and hydrodynamic behavior of water-cooled and moderated reactors, at either high or low pressure, with boiling permitted; fuel elements are assumed to be flat plates: - Flowrate in parallel channels coupled or not by conduction across plates, with conditions of pressure drops or flowrate, variable or not with respect to time is given; the power can be coupled to reactor kinetics calculation or supplied by the code user. The code, containing a schematic representation of safety rod behavior, is a one dimensional, multi-channel code, and has as its complement (FLID), a one-channel, two-dimensional code. (authors) [French] Ce code permet de traiter les problemes ci-dessous: 1. Depouillement d'essais thermiques sur boucle a eau, haute ou basse pression, en regime permanent ou transitoire; 2. Etudes thermiques et hydrauliques de reacteurs a eau, a plaques, a haute ou basse pression, ebullition permise: - repartition entre canaux paralleles, couples on non par conduction a travers plaques, pour des conditions de debit ou de pertes de charge imposees, variables ou non dans le temps; - la puissance peut etre couplee a la neutronique et une representation schematique des actions de securite est prevue. Ce code (Cactus) a une dimension d'espace et plusieurs canaux, a pour complement Flid qui traite l'etude d'un seul canal a deux dimensions. (auteurs)

  8. Army-NASA aircrew/aircraft integration program (A3I) software detailed design document, phase 3

    Science.gov (United States)

    Banda, Carolyn; Chiu, Alex; Helms, Gretchen; Hsieh, Tehming; Lui, Andrew; Murray, Jerry; Shankar, Renuka

    1990-01-01

    The capabilities and design approach of the MIDAS (Man-machine Integration Design and Analysis System) computer-aided engineering (CAE) workstation under development by the Army-NASA Aircrew/Aircraft Integration Program is detailed. This workstation uses graphic, symbolic, and numeric prototyping tools and human performance models as part of an integrated design/analysis environment for crewstation human engineering. Developed incrementally, the requirements and design for Phase 3 (Dec. 1987 to Jun. 1989) are described. Software tools/models developed or significantly modified during this phase included: an interactive 3-D graphic cockpit design editor; multiple-perspective graphic views to observe simulation scenarios; symbolic methods to model the mission decomposition, equipment functions, pilot tasking and loading, as well as control the simulation; a 3-D dynamic anthropometric model; an intermachine communications package; and a training assessment component. These components were successfully used during Phase 3 to demonstrate the complex interactions and human engineering findings involved with a proposed cockpit communications design change in a simulated AH-64A Apache helicopter/mission that maps to empirical data from a similar study and AH-1 Cobra flight test.

  9. NOAA Weather Radio - EAS Event Codes

    Science.gov (United States)

    Non-Zero All Hazards Logo Emergency Alert Description Event Codes Fact Sheet FAQ Organization Search Coding Using SAME SAME Non-Zero Codes DOCUMENTS NWR Poster NWR Brochure NWR Brochure Printing Notes

  10. TableSim--A program for analysis of small-sample categorical data.

    Science.gov (United States)

    David J. Rugg

    2003-01-01

    Documents a computer program for calculating correct P-values of 1-way and 2-way tables when sample sizes are small. The program is written in Fortran 90; the executable code runs in 32-bit Microsoft-- command line environments.

  11. CMS DOCUMENTATION

    CERN Multimedia

    CMS TALKS AT MAJOR MEETINGS The agenda and talks from major CMS meetings can now be electronically accessed from the iCMS Web site. The following items can be found on: http://cms.cern.ch/iCMS/ General - CMS Weeks (Collaboration Meetings), CMS Weeks Agendas The talks presented at the Plenary Sessions. LHC Symposiums Management - CB - MB - FB - FMC Agendas and minutes are accessible to CMS members through their AFS account (ZH). However some linked documents are restricted to the Board Members. FB documents are only accessible to FB members. LHCC The talks presented at the ‘CMS Meetings with LHCC Referees’ are available on request from the PM or MB Country Representative. Annual Reviews The talks presented at the 2006 Annual reviews are posted.   CMS DOCUMENTS It is considered useful to establish information on the first employment of CMS doctoral students upon completion of their theses. Therefore it is requested that Ph.D students inform the CMS Secretariat a...

  12. CMS DOCUMENTATION

    CERN Multimedia

    CMS TALKS AT MAJOR MEETINGS The agenda and talks from major CMS meetings can now be electronically accessed from the iCMS Web site. The following items can be found on: http://cms.cern.ch/iCMS/ General - CMS Weeks (Collaboration Meetings), CMS Weeks Agendas The talks presented at the Plenary Sessions. LHC Symposiums Management - CB - MB - FB - FMC Agendas and minutes are accessible to CMS members through their AFS account (ZH). However some linked documents are restricted to the Board Members. FB documents are only accessible to FB members. LHCC The talks presented at the ‘CMS Meetings with LHCC Referees’ are available on request from the PM or MB Country Representative. Annual Reviews The talks presented at the 2006 Annual reviews are posted. CMS DOCUMENTS It is considered useful to establish information on the first employment of CMS doctoral students upon completion of their theses. Therefore it is requested that Ph.D students inform the CMS Secretariat about the natu...

  13. CMS DOCUMENTATION

    CERN Multimedia

    CMS TALKS AT MAJOR MEETINGS The agenda and talks from major CMS meetings can now be electronically accessed from the iCMS Web site. The following items can be found on: http://cms.cern.ch/iCMS/ General - CMS Weeks (Collaboration Meetings), CMS Weeks Agendas The talks presented at the Plenary Sessions. LHC Symposiums Management - CB - MB - FB - FMC Agendas and minutes are accessible to CMS members through their AFS account (ZH). However some linked documents are restricted to the Board Members. FB documents are only accessible to FB members. LHCC The talks presented at the ‘CMS Meetings with LHCC Referees’ are available on request from the PM or MB Country Representative. Annual Reviews The talks presented at the 2006 Annual reviews are posted. CMS DOCUMENTS It is considered useful to establish information on the first employment of CMS doctoral students upon completion of their theses. Therefore it is requested that Ph.D students inform the CMS Secretariat about the natur...

  14. CMS DOCUMENTATION

    CERN Multimedia

    CMS TALKS AT MAJOR MEETINGS The agenda and talks from major CMS meetings can now be electronically accessed from the iCMS Web site. The following items can be found on: http://cms.cern.ch/iCMS/ Management- CMS Weeks (Collaboration Meetings), CMS Weeks Agendas The talks presented at the Plenary Sessions. Management - CB - MB - FB Agendas and minutes are accessible to CMS members through their AFS account (ZH). However some linked documents are restricted to the Board Members. FB documents are only accessible to FB members. LHCC The talks presented at the ‘CMS Meetings with LHCC Referees’ are available on request from the PM or MB Country Representative. Annual Reviews The talks presented at the 2007 Annual reviews are posted. CMS DOCUMENTS It is considered useful to establish information on the first employment of CMS doctoral students upon completion of their theses. Therefore it is requested that Ph.D students inform the CMS Secretariat about the nature of employment and ...

  15. CMS DOCUMENTATION

    CERN Multimedia

    CMS TALKS AT MAJOR MEETINGS The agenda and talks from major CMS meetings can now be electronically accessed from the iCMS Web site. The following items can be found on: http://cms.cern.ch/iCMS/ Management- CMS Weeks (Collaboration Meetings), CMS Weeks Agendas The talks presented at the Plenary Sessions. Management - CB - MB - FB Agendas and minutes are accessible to CMS members through their AFS account (ZH). However some linked documents are restricted to the Board Members. FB documents are only accessible to FB members. LHCC The talks presented at the ‘CMS Meetings with LHCC Referees’ are available on request from the PM or MB Country Representative. Annual Reviews The talks presented at the 2007 Annual reviews are posted. CMS DOCUMENTS It is considered useful to establish information on the first employment of CMS doctoral students upon completion of their theses. Therefore it is requested that Ph.D students inform the CMS Secretariat about the nature of em¬pl...

  16. CMS DOCUMENTATION

    CERN Multimedia

    CMS TALKS AT MAJOR MEETINGS The agenda and talks from major CMS meetings can now be electronically accessed from the iCMS Web site. The following items can be found on: http://cms.cern.ch/iCMS/ General - CMS Weeks (Collaboration Meetings), CMS Weeks Agendas The talks presented at the Plenary Sessions. LHC Symposiums Management - CB - MB - FB - FMC Agendas and minutes are accessible to CMS members through their AFS account (ZH). However some linked documents are restricted to the Board Members. FB documents are only accessible to FB members. LHCC The talks presented at the ‘CMS Meetings with LHCC Referees’ are available on request from the PM or MB Country Representative. Annual Reviews The talks presented at the 2006 Annual reviews are posted. CMS DOCUMENTS It is considered useful to establish information on the first employment of CMS doctoral students upon completion of their theses. Therefore it is requested that Ph.D students inform the CMS Secretariat about the na...

  17. System Design Description for the TMAD Code

    International Nuclear Information System (INIS)

    Finfrock, S.H.

    1995-01-01

    This document serves as the System Design Description (SDD) for the TMAD Code System, which includes the TMAD code and the LIBMAKR code. The SDD provides a detailed description of the theory behind the code, and the implementation of that theory. It is essential for anyone who is attempting to review or modify the code or who otherwise needs to understand the internal workings of the code. In addition, this document includes, in Appendix A, the System Requirements Specification for the TMAD System

  18. Vibration computer programs E13101, E13102, E13104, and E13112 and application to the NERVA program. Project 187: Methodology documentation

    Science.gov (United States)

    Mironenko, G.

    1972-01-01

    Programs for the analyses of the free or forced, undamped vibrations of one or two elastically-coupled lumped parameter teams are presented. Bearing nonlinearities, casing and rotor distributed mass and elasticity, rotor imbalance, forcing functions, gyroscopic moments, rotary inertia, and shear and flexural deformations are all included in the system dynamics analysis. All bearings have nonlinear load displacement characteristics, the solution is achieved by iteration. Rotor imbalances allowed by such considerations as pilot tolerances and runouts as well as bearing clearances (allowing concail or cylindrical whirl) determine the forcing function magnitudes. The computer programs first obtain a solution wherein the bearings are treated as linear springs of given spring rates. Then, based upon the computed bearing reactions, new spring rates are predicted and another solution of the modified system is made. The iteration is continued until the changes to bearing spring rates and bearing reactions become negligibly small.

  19. Synthesizing Certified Code

    OpenAIRE

    Whalen, Michael; Schumann, Johann; Fischer, Bernd

    2002-01-01

    Code certification is a lightweight approach for formally demonstrating software quality. Its basic idea is to require code producers to provide formal proofs that their code satisfies certain quality properties. These proofs serve as certificates that can be checked independently. Since code certification uses the same underlying technology as program verification, it requires detailed annotations (e.g., loop invariants) to make the proofs possible. However, manually adding annotations to th...

  20. First steps towards a validation of the new burnup and depletion code TNT

    Energy Technology Data Exchange (ETDEWEB)

    Herber, S.C.; Allelein, H.J. [RWTH Aachen (Germany). Inst. for Reactor Safety and Reactor Technology; Research Center Juelich (Germany). Inst. for Energy and Climate Research - Nuclear Waste Disposal and Reactor Safety (IEK-6); Friege, N. [RWTH Aachen (Germany). Inst. for Reactor Safety and Reactor Technology; Kasselmann, S. [Research Center Juelich (Germany). Inst. for Energy and Climate Research - Nuclear Waste Disposal and Reactor Safety (IEK-6)

    2012-11-01

    In the frame of the fusion of the core design calculation capabilities, represented by V.S.O.P., and the accident calculation capabilities, represented by MGT(-3D), the successor of the TINTE code, difficulties were observed in defining an interface between a program backbone and the ORIGEN code respectively the ORIGENJUEL code. The estimation of the effort of refactoring the ORIGEN code or to write a new burnup code from scratch, led to the decision that it would be more efficient writing a new code, which could benefit from existing programming and software engineering tools from the computer code side and which can use the latest knowledge of nuclear reactions, e.g. consider all documented reaction channels. Therefore a new code with an object-oriented approach was developed at IEK-6. Object-oriented programming is currently state of the art and provides mostly an improved extensibility and maintainability. The new code was named TNT which stands for Topological Nuclide Transformation, since the code makes use of the real topology of the nuclear reactions. Here we want to present some first validation results from code to code benchmarks with the codes ORIGEN V2.2 and FISPACT2005 and whenever possible analytical results also used for the comparison. The 2 reference codes were chosen due to their high reputation in the field of fission reactor analysis (ORIGEN) and fusion facilities (FISPACT). (orig.)

  1. Nuclear power plants documentation system

    International Nuclear Information System (INIS)

    Schwartz, E.L.

    1991-01-01

    Since the amount of documents (type and quantity) necessary for the entire design of a NPP is very large, this implies that an overall and detailed identification, filling and retrieval system shall be implemented. This is even more applicable to the FINAL QUALITY DOCUMENTATION of the plant, as stipulated by IAEA Safety Codes and related guides. For such a purpose it was developed a DOCUMENTATION MANUAL, which describes in detail the before mentioned documentation system. Here we present the expected goals and results which we have to reach for Angra 2 and 3 Project. (author)

  2. Documentation of a groundwater flow model (SJRRPGW) for the San Joaquin River Restoration Program study area, California

    Science.gov (United States)

    Traum, Jonathan A.; Phillips, Steven P.; Bennett, George L.; Zamora, Celia; Metzger, Loren F.

    2014-01-01

    To better understand the potential effects of restoration flows on existing drainage problems, anticipated as a result of the San Joaquin River Restoration Program (SJRRP), the U.S. Geological Survey (USGS), in cooperation with the U.S. Bureau of Reclamation (Reclamation), developed a groundwater flow model (SJRRPGW) of the SJRRP study area that is within 5 miles of the San Joaquin River and adjacent bypass system from Friant Dam to the Merced River. The primary goal of the SJRRP is to reestablish the natural ecology of the river to a degree that restores salmon and other fish populations. Increased flows in the river, particularly during the spring salmon run, are a key component of the restoration effort. A potential consequence of these increased river flows is the exacerbation of existing irrigation drainage problems along a section of the river between Mendota and the confluence with the Merced River. Historically, this reach typically was underlain by a water table within 10 feet of the land surface, thus requiring careful irrigation management and (or) artificial drainage to maintain crop health. The SJRRPGW is designed to meet the short-term needs of the SJRRP; future versions of the model may incorporate potential enhancements, several of which are identified in this report. The SJRRPGW was constructed using the USGS groundwater flow model MODFLOW and was built on the framework of the USGS Central Valley Hydrologic Model (CVHM) within which the SJRRPGW model domain is embedded. The Farm Process (FMP2) was used to simulate the supply and demand components of irrigated agriculture. The Streamflow-Routing Package (SFR2) was used to simulate the streams and bypasses and their interaction with the aquifer system. The 1,300-square mile study area was subdivided into 0.25-mile by 0.25-mile cells. The sediment texture of the aquifer system, which was used to distribute hydraulic properties by model cell, was refined from that used in the CVHM to better represent

  3. Building Capacity Through Hands-on Computational Internships to Assure Reproducible Results and Implementation of Digital Documentation in the ICERT REU Program

    Science.gov (United States)

    Gomez, R.; Gentle, J.

    2015-12-01

    Modern data pipelines and computational processes require that meticulous methodologies be applied in order to insure that the source data, algorithms, and results are properly curated, managed and retained while remaining discoverable, accessible, and reproducible. Given the complexity of understanding the scientific problem domain being researched, combined with the overhead of learning to use advanced computing technologies, it becomes paramount that the next generation of scientists and researchers learn to embrace best-practices. The Integrative Computational Education and Research Traineeship (ICERT) is a National Science Foundation (NSF) Research Experience for Undergraduates (REU) Site at the Texas Advanced Computing Center (TACC). During Summer 2015, two ICERT interns joined the 3DDY project. 3DDY converts geospatial datasets into file types that can take advantage of new formats, such as natural user interfaces, interactive visualization, and 3D printing. Mentored by TACC researchers for ten weeks, students with no previous background in computational science learned to use scripts to build the first prototype of the 3DDY application, and leveraged Wrangler, the newest high performance computing (HPC) resource at TACC. Test datasets for quadrangles in central Texas were used to assemble the 3DDY workflow and code. Test files were successfully converted into a stereo lithographic (STL) format, which is amenable for use with a 3D printers. Test files and the scripts were documented and shared using the Figshare site while metadata was documented for the 3DDY application using OntoSoft. These efforts validated a straightforward set of workflows to transform geospatial data and established the first prototype version of 3DDY. Adding the data and software management procedures helped students realize a broader set of tangible results (e.g. Figshare entries), better document their progress and the final state of their work for the research group and community

  4. Recommended HSE-7 documents hierarchy

    International Nuclear Information System (INIS)

    Klein, R.B.; Jennrich, E.A.; Lund, D.M.; Danna, J.G.; Davis, K.D.; Rutz, A.C.

    1990-01-01

    This report recommends a hierarchy of waste management documents at Los Alamos National Laboratory (LANL or ''Laboratory''). The hierarchy addresses documents that are required to plan, implement, and document waste management programs at Los Alamos. These documents will enable the waste management group and the six sections contained within that group to satisfy requirements that are imposed upon them by the US Department of Energy (DOE), DOE Albuquerque Operations, US Environmental Protection Agency, various State of New Mexico agencies, and Laboratory management

  5. CNEA's quality system documentation

    International Nuclear Information System (INIS)

    Mazzini, M.M.; Garonis, O.H.

    1998-01-01

    Full text: To obtain an effective and coherent documentation system suitable for CNEA's Quality Management Program, we decided to organize the CNEA's quality documentation with : a- Level 1. Quality manual. b- Level 2. Procedures. c-Level 3. Qualities plans. d- Level 4: Instructions. e- Level 5. Records and other documents. The objective of this work is to present a standardization of the documentation of the CNEA's quality system of facilities, laboratories, services, and R and D activities. Considering the diversity of criteria and formats for elaboration the documentation by different departments, and since ultimately each of them generally includes the same quality management policy, we proposed the elaboration of a system in order to improve the documentation, avoiding unnecessary time wasting and costs. This will aloud each sector to focus on their specific documentation. The quality manuals of the atomic centers fulfill the rule 3.6.1 of the Nuclear Regulatory Authority, and the Safety Series 50-C/SG-Q of the International Atomic Energy Agency. They are designed by groups of competent and highly trained people of different departments. The normative procedures are elaborated with the same methodology as the quality manuals. The quality plans which describe the organizational structure of working group and the appropriate documentation, will asses the quality manuals of facilities, laboratories, services, and research and development activities of atomic centers. The responsibilities for approval of the normative documentation are assigned to the management in charge of the administration of economic and human resources in order to fulfill the institutional objectives. Another improvement aimed to eliminate unnecessary invaluable processes is the inclusion of all quality system's normative documentation in the CNEA intranet. (author) [es

  6. REVEAL: Software Documentation and Platform Migration

    Science.gov (United States)

    Wilson, Michael A.; Veibell, Victoir T.; Freudinger, Lawrence C.

    2008-01-01

    The Research Environment for Vehicle Embedded Analysis on Linux (REVEAL) is reconfigurable data acquisition software designed for network-distributed test and measurement applications. In development since 2001, it has been successfully demonstrated in support of a number of actual missions within NASA s Suborbital Science Program. Improvements to software configuration control were needed to properly support both an ongoing transition to operational status and continued evolution of REVEAL capabilities. For this reason the project described in this report targets REVEAL software source documentation and deployment of the software on a small set of hardware platforms different from what is currently used in the baseline system implementation. This report specifically describes the actions taken over a ten week period by two undergraduate student interns and serves as a final report for that internship. The topics discussed include: the documentation of REVEAL source code; the migration of REVEAL to other platforms; and an end-to-end field test that successfully validates the efforts.

  7. Structural analysis program of plant piping system. Introduction of AutoPIPE V8i new feature. JSME PPC-class 2 piping code

    International Nuclear Information System (INIS)

    Motohashi, Kazuhiko

    2009-01-01

    After an integration with ADLPipe, AutoPIPE V8i (ver.9.1) became the structural analysis program of plant piping system featured with analysis capability for the ASME NB Class 1 and JSME PPC-Class 2 piping codes including ASME NC Class 2 and ASME ND Class 3. This article described analysis capability for the JSME PPC-Class 2 piping code as well as new general features such as static analysis up to 100 thermal, 10 seismic and 10 wind load cases including different loading scenarios and pipe segment edit function: join, split, reverse and re-order segments. (T. Tanaka)

  8. EGS code system: computer programs for the Monte Carlo simulation of electromagnetic cascade showers. Version 3. [EGS, PEGS, TESTSR, in MORTRAN

    Energy Technology Data Exchange (ETDEWEB)

    Ford, R.L.; Nelson, W.R.

    1978-06-01

    A code to simulate almost any electron--photon transport problem conceivable is described. The report begins with a lengthy historical introduction and a description of the shower generation process. Then the detailed physics of the shower processes and the methods used to simulate them are presented. Ideas of sampling theory, transport techniques, particle interactions in general, and programing details are discussed. Next, EGS calculations and various experiments and other Monte Carlo results are compared. The remainder of the report consists of user manuals for EGS, PEGS, and TESTSR codes; options, input specifications, and typical output are included. 38 figures, 12 tables. (RWR)

  9. Codes and curves

    CERN Document Server

    Walker, Judy L

    2000-01-01

    When information is transmitted, errors are likely to occur. Coding theory examines efficient ways of packaging data so that these errors can be detected, or even corrected. The traditional tools of coding theory have come from combinatorics and group theory. Lately, however, coding theorists have added techniques from algebraic geometry to their toolboxes. In particular, by re-interpreting the Reed-Solomon codes, one can see how to define new codes based on divisors on algebraic curves. For instance, using modular curves over finite fields, Tsfasman, Vladut, and Zink showed that one can define a sequence of codes with asymptotically better parameters than any previously known codes. This monograph is based on a series of lectures the author gave as part of the IAS/PCMI program on arithmetic algebraic geometry. Here, the reader is introduced to the exciting field of algebraic geometric coding theory. Presenting the material in the same conversational tone of the lectures, the author covers linear codes, inclu...

  10. ROOT Reference Documentation

    CERN Document Server

    Fuakye, Eric Gyabeng

    2017-01-01

    A ROOT Reference Documentation has been implemented to generate all the lists of libraries needed for each ROOT class. Doxygen has no option to generate or add the lists of libraries for each ROOT class. Therefore shell scripting and a basic C++ program was employed to import the lists of libraries needed by each ROOT class.

  11. Methodology, status, and plans for development and assessment of the RELAP5 code

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, G.W.; Riemke, R.A. [Idaho National Engineering Laboratory, Idaho Falls, ID (United States)

    1997-07-01

    RELAP/MOD3 is a computer code used for the simulation of transients and accidents in light-water nuclear power plants. The objective of the program to develop and maintain RELAP5 was and is to provide the U.S. Nuclear Regulatory Commission with an independent tool for assessing reactor safety. This paper describes code requirements, models, solution scheme, language and structure, user interface validation, and documentation. The paper also describes the current and near term development program and provides an assessment of the code`s strengths and limitations.

  12. Version 4. 00 of the MINTEQ geochemical code

    Energy Technology Data Exchange (ETDEWEB)

    Eary, L.E.; Jenne, E.A.

    1992-09-01

    The MINTEQ code is a thermodynamic model that can be used to calculate solution equilibria for geochemical applications. Included in the MINTEQ code are formulations for ionic speciation, ion exchange, adsorption, solubility, redox, gas-phase equilibria, and the dissolution of finite amounts of specified solids. Since the initial development of the MINTEQ geochemical code, a number of undocumented versions of the source code and data files have come into use at the Pacific Northwest Laboratory (PNL). This report documents these changes, describes source code modifications made for the Aquifer Thermal Energy Storage (ATES) program, and provides comprehensive listings of the data files. A version number of 4.00 has been assigned to the MINTEQ source code and the individual data files described in this report.

  13. Version 4.00 of the MINTEQ geochemical code

    Energy Technology Data Exchange (ETDEWEB)

    Eary, L.E.; Jenne, E.A.

    1992-09-01

    The MINTEQ code is a thermodynamic model that can be used to calculate solution equilibria for geochemical applications. Included in the MINTEQ code are formulations for ionic speciation, ion exchange, adsorption, solubility, redox, gas-phase equilibria, and the dissolution of finite amounts of specified solids. Since the initial development of the MINTEQ geochemical code, a number of undocumented versions of the source code and data files have come into use at the Pacific Northwest Laboratory (PNL). This report documents these changes, describes source code modifications made for the Aquifer Thermal Energy Storage (ATES) program, and provides comprehensive listings of the data files. A version number of 4.00 has been assigned to the MINTEQ source code and the individual data files described in this report.

  14. R5FORCE: a program to compute fluid induced forces using hydrodynamic output from the RELAP5 code

    International Nuclear Information System (INIS)

    Watkins, J.C.

    1983-01-01

    This paper describes the computer code R5FORCE, a postprocessor to the RELAP5/MOD1 thermal-hydraulics code. R5FORCE computes piping hydraulic force/time histories that can be input into various structural analysis computer codes. R5FORCE solves the momentum conservation equation using the pressure and wall shear force terms rather than the pressure and fluid acceleration terms; eliminating potential instabilities associated with computing the time derivative in the fluid acceleration term. The updates to REALP5 required to generate the input data to R5FORCE are also discussed

  15. Coding completeness and quality of relative survival-related variables in the National Program of Cancer Registries Cancer Surveillance System, 1995-2008.

    Science.gov (United States)

    Wilson, Reda J; O'Neil, M E; Ntekop, E; Zhang, Kevin; Ren, Y

    2014-01-01

    Calculating accurate estimates of cancer survival is important for various analyses of cancer patient care and prognosis. Current US survival rates are estimated based on data from the National Cancer Institute's (NCI's) Surveillance, Epidemiology, and End RESULTS (SEER) program, covering approximately 28 percent of the US population. The National Program of Cancer Registries (NPCR) covers about 96 percent of the US population. Using a population-based database with greater US population coverage to calculate survival rates at the national, state, and regional levels can further enhance the effective monitoring of cancer patient care and prognosis in the United States. The first step is to establish the coding completeness and coding quality of the NPCR data needed for calculating survival rates and conducting related validation analyses. Using data from the NPCR-Cancer Surveillance System (CSS) from 1995 through 2008, we assessed coding completeness and quality on 26 data elements that are needed to calculate cancer relative survival estimates and conduct related analyses. Data elements evaluated consisted of demographic, follow-up, prognostic, and cancer identification variables. Analyses were performed showing trends of these variables by diagnostic year, state of residence at diagnosis, and cancer site. Mean overall percent coding completeness by each NPCR central cancer registry averaged across all data elements and diagnosis years ranged from 92.3 percent to 100 percent. RESULTS showing the mean percent coding completeness for the relative survival-related variables in NPCR data are presented. All data elements but 1 have a mean coding completeness greater than 90 percent as was the mean completeness by data item group type. Statistically significant differences in coding completeness were found in the ICD revision number, cause of death, vital status, and date of last contact variables when comparing diagnosis years. The majority of data items had a coding

  16. Coding for urologic office procedures.

    Science.gov (United States)

    Dowling, Robert A; Painter, Mark

    2013-11-01

    This article summarizes current best practices for documenting, coding, and billing common office-based urologic procedures. Topics covered include general principles, basic and advanced urologic coding, creation of medical records that support compliant coding practices, bundled codes and unbundling, global periods, modifiers for procedure codes, when to bill for evaluation and management services during the same visit, coding for supplies, and laboratory and radiology procedures pertinent to urology practice. Detailed information is included for the most common urology office procedures, and suggested resources and references are provided. This information is of value to physicians, office managers, and their coding staff. Copyright © 2013 Elsevier Inc. All rights reserved.

  17. Nuclear code abstracts (1975 edition)

    International Nuclear Information System (INIS)

    Akanuma, Makoto; Hirakawa, Takashi

    1976-02-01

    Nuclear Code Abstracts is compiled in the Nuclear Code Committee to exchange information of the nuclear code developments among members of the committee. Enlarging the collection, the present one includes nuclear code abstracts obtained in 1975 through liaison officers of the organizations in Japan participating in the Nuclear Energy Agency's Computer Program Library at Ispra, Italy. The classification of nuclear codes and the format of code abstracts are the same as those in the library. (auth.)

  18. SANSMIC design document.

    Energy Technology Data Exchange (ETDEWEB)

    Weber, Paula D. [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Rudeen, David Keith [GRAM, Inc., Albuquerque, NM (United States)

    2015-07-01

    The United States Strategic Petroleum Reserve (SPR) maintains an underground storage system consisting of caverns that were leached or solution mined in four salt domes located near the Gulf of Mexico in Texas and Louisiana. The SPR comprises more than 60 active caverns containing approximately 700 million barrels of crude oil. Sandia National Labo- ratories (SNL) is the geotechnical advisor to the SPR. As the most pressing need at the inception of the SPR was to create and fill storage volume with oil, the decision was made to leach the caverns and fill them simultaneously (leach-fill). Therefore, A.J. Russo developed SANSMIC in the early 1980s which allows for a transient oil-brine interface (OBI) making it possible to model leach-fill and withdrawal operations. As the majority of caverns are currently filled to storage capacity, the primary uses of SANSMIC at this time are related to the effects of small and large withdrawals, expansion of existing caverns, and projecting future pillar to diameter ratios. SANSMIC was identified by SNL as a priority candidate for qualification. This report continues the quality assurance (QA) process by documenting the "as built" mathematical and numerical models that comprise this document. The pro- gram flow is outlined and the models are discussed in detail. Code features that were added later or were not documented previously have been expounded. No changes in the code's physics have occurred since the original documentation (Russo, 1981, 1983) although recent experiments may yield improvements to the temperature and plume methods in the future.

  19. Optimized periodic verification testing blended risk and performance-based MOV inservice test program an application of ASME code case OMN-1

    Energy Technology Data Exchange (ETDEWEB)

    Sellers, C.; Fleming, K.; Bidwell, D.; Forbes, P. [and others

    1996-12-01

    This paper presents an application of ASME Code Case OMN-1 to the GL 89-10 Program at the South Texas Project Electric Generating Station (STPEGS). Code Case OMN-1 provides guidance for a performance-based MOV inservice test program that can be used for periodic verification testing and allows consideration of risk insights. Blended probabilistic and deterministic evaluation techniques were used to establish inservice test strategies including both test methods and test frequency. Described in the paper are the methods and criteria for establishing MOV safety significance based on the STPEGS probabilistic safety assessment, deterministic considerations of MOV performance characteristics and performance margins, the expert panel evaluation process, and the development of inservice test strategies. Test strategies include a mix of dynamic and static testing as well as MOV exercising.

  20. Optimized periodic verification testing blended risk and performance-based MOV inservice test program an application of ASME code case OMN-1

    International Nuclear Information System (INIS)

    Sellers, C.; Fleming, K.; Bidwell, D.; Forbes, P.

    1996-01-01

    This paper presents an application of ASME Code Case OMN-1 to the GL 89-10 Program at the South Texas Project Electric Generating Station (STPEGS). Code Case OMN-1 provides guidance for a performance-based MOV inservice test program that can be used for periodic verification testing and allows consideration of risk insights. Blended probabilistic and deterministic evaluation techniques were used to establish inservice test strategies including both test methods and test frequency. Described in the paper are the methods and criteria for establishing MOV safety significance based on the STPEGS probabilistic safety assessment, deterministic considerations of MOV performance characteristics and performance margins, the expert panel evaluation process, and the development of inservice test strategies. Test strategies include a mix of dynamic and static testing as well as MOV exercising

  1. Evaluation the total exposure of soil sample in Adaya site and the obtain risk assessments for the worker by Res Rad code program

    International Nuclear Information System (INIS)

    Mahadi, A. M.; Khadim, A. A. N.; Ibrahim, Z. H.; Ali, S. A.

    2012-12-01

    The present study aims to evaluation the total exposure to the worker in Adaya site risk assessment by using Res Rad code program. The study including 5 areas soil sample calculate in the site and analysis it by High Pure Germaniums (Hg) system made (CANBERRA) company. The soil sample simulation by (Res Rad) code program by inter the radioactive isotope concentration and the specification of the contamination zone area, depth and the cover depth of it. The total exposure of same sample was about 9 mSv/year and the (Heast 2001 Morbidity, FGR13 Morbidity) about 2.045 state every 100 worker in the year. There are simple different between Heast 2001 Morbidity and FGR13 Morbidity according to the Dose Conversion Factor (DCF) use it. The (FGR13 Morbidity) about 2.041 state every 100 worker in the year. (Author)

  2. LCS Content Document Application

    Science.gov (United States)

    Hochstadt, Jake

    2011-01-01

    My project at KSC during my spring 2011 internship was to develop a Ruby on Rails application to manage Content Documents..A Content Document is a collection of documents and information that describes what software is installed on a Launch Control System Computer. It's important for us to make sure the tools we use everyday are secure, up-to-date, and properly licensed. Previously, keeping track of the information was done by Excel and Word files between different personnel. The goal of the new application is to be able to manage and access the Content Documents through a single database backed web application. Our LCS team will benefit greatly with this app. Admin's will be able to login securely to keep track and update the software installed on each computer in a timely manner. We also included exportability such as attaching additional documents that can be downloaded from the web application. The finished application will ease the process of managing Content Documents while streamlining the procedure. Ruby on Rails is a very powerful programming language and I am grateful to have the opportunity to build this application.

  3. The materiality of Code

    DEFF Research Database (Denmark)

    Soon, Winnie

    2014-01-01

    This essay studies the source code of an artwork from a software studies perspective. By examining code that come close to the approach of critical code studies (Marino, 2006), I trace the network artwork, Pupufu (Lin, 2009) to understand various real-time approaches to social media platforms (MSN......, Twitter and Facebook). The focus is not to investigate the functionalities and efficiencies of the code, but to study and interpret the program level of code in order to trace the use of various technological methods such as third-party libraries and platforms’ interfaces. These are important...... to understand the socio-technical side of a changing network environment. Through the study of code, including but not limited to source code, technical specifications and other materials in relation to the artwork production, I would like to explore the materiality of code that goes beyond technical...

  4. CMS DOCUMENTATION

    CERN Multimedia

    CMS TALKS AT MAJOR MEETINGS The agenda and talks from major CMS meetings can now be electronically accessed from the ICMS Web site. The following items can be found on: http://cms.cern.ch/iCMS Management – CMS Weeks (Collaboration Meetings), CMS Weeks Agendas The talks presented at the Plenary Sessions. Management – CB – MB – FB Agendas and minutes are accessible to CMS members through Indico. LHCC The talks presented at the ‘CMS Meetings with LHCC Referees’ are available on request from the PM or MB Country Representative. Annual Reviews The talks presented at the 2008 Annual Reviews are posted in Indico. CMS DOCUMENTS It is considered useful to establish information on the first employment of CMS doctoral student upon completion of their theses.  Therefore it is requested that Ph.D students inform the CMS Secretariat about the nature of employment and name of their first employer. The Notes, Conference Reports and Theses published si...

  5. Documentation and user's guide for DOSTOMAN: a pathways computer model of radionuclide movement

    International Nuclear Information System (INIS)

    Root, R.W. Jr.

    1980-01-01

    This report documents the mathematical development and the computer implementation of the Savannah River Laboratory computer code used to simulate radonuclide movement in the environment. The user's guide provides all the necessary information for the prospective user to input the required data, execute the computer program, and display the results

  6. 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

  7. A computerized energy systems code and information library at Soreq

    Energy Technology Data Exchange (ETDEWEB)

    Silverman, I; Shapira, M; Caner, D; Sapier, D [Israel Atomic Energy Commission, Yavne (Israel). Soreq Nuclear Research Center

    1996-12-01

    In the framework of the contractual agreement between the Ministry of Energy and Infrastructure and the Division of Nuclear Engineering of the Israel Atomic Energy Commission, both Soreq-NRC and Ben-Gurion University have agreed to establish, in 1991, a code center. This code center contains a library of computer codes and relevant data, with particular emphasis on nuclear power plant research and development support. The code center maintains existing computer codes and adapts them to the ever changing computing environment, keeps track of new code developments in the field of nuclear engineering, and acquires the most recent revisions of computer codes of interest. An attempt is made to collect relevant codes developed in Israel and to assure that proper documentation and application instructions are available. En addition to computer programs, the code center collects sample problems and international benchmarks to verify the codes and their applications to various areas of interest to nuclear power plant engineering and safety evaluation. Recently, the reactor simulation group at Soreq acquired, using funds provided by the Ministry of Energy and Infrastructure, a PC work station operating under a Linux operating system to give users of the library an easy on-line way to access resources available at the library. These resources include the computer codes and their documentation, reports published by the reactor simulation group, and other information databases available at Soreq. Registered users set a communication line, through a modem, between their computer and the new workstation at Soreq and use it to download codes and/or information or to solve their problems, using codes from the library, on the computer at Soreq (authors).

  8. A computerized energy systems code and information library at Soreq

    International Nuclear Information System (INIS)

    Silverman, I.; Shapira, M.; Caner, D.; Sapier, D.

    1996-01-01

    In the framework of the contractual agreement between the Ministry of Energy and Infrastructure and the Division of Nuclear Engineering of the Israel Atomic Energy Commission, both Soreq-NRC and Ben-Gurion University have agreed to establish, in 1991, a code center. This code center contains a library of computer codes and relevant data, with particular emphasis on nuclear power plant research and development support. The code center maintains existing computer codes and adapts them to the ever changing computing environment, keeps track of new code developments in the field of nuclear engineering, and acquires the most recent revisions of computer codes of interest. An attempt is made to collect relevant codes developed in Israel and to assure that proper documentation and application instructions are available. En addition to computer programs, the code center collects sample problems and international benchmarks to verify the codes and their applications to various areas of interest to nuclear power plant engineering and safety evaluation. Recently, the reactor simulation group at Soreq acquired, using funds provided by the Ministry of Energy and Infrastructure, a PC work station operating under a Linux operating system to give users of the library an easy on-line way to access resources available at the library. These resources include the computer codes and their documentation, reports published by the reactor simulation group, and other information databases available at Soreq. Registered users set a communication line, through a modem, between their computer and the new workstation at Soreq and use it to download codes and/or information or to solve their problems, using codes from the library, on the computer at Soreq (authors)

  9. Sugar Industry Influence on the Scientific Agenda of the National Institute of Dental Research’s 1971 National Caries Program: A Historical Analysis of Internal Documents

    Science.gov (United States)

    Kearns, Cristin E.; Glantz, Stanton A.; Schmidt, Laura A.

    2015-01-01

    Background In 1966, the National Institute of Dental Research (NIDR) began planning a targeted research program to identify interventions for widespread application to eradicate dental caries (tooth decay) within a decade. In 1971, the NIDR launched the National Caries Program (NCP). The objective of this paper is to explore the sugar industry’s interaction with the NIDR to alter the research priorities of the NIDR NCP. Methods and Findings We used internal cane and beet sugar industry documents from 1959 to 1971 to analyze industry actions related to setting research priorities for the NCP. The sugar industry could not deny the role of sucrose in dental caries given the scientific evidence. They therefore adopted a strategy to deflect attention to public health interventions that would reduce the harms of sugar consumption rather than restricting intake. Industry tactics included the following: funding research in collaboration with allied food industries on enzymes to break up dental plaque and a vaccine against tooth decay with questionable potential for widespread application, cultivation of relationships with the NIDR leadership, consulting of members on an NIDR expert panel, and submission of a report to the NIDR that became the foundation of the first request for proposals issued for the NCP. Seventy-eight percent of the sugar industry submission was incorporated into the NIDR’s call for research applications. Research that could have been harmful to sugar industry interests was omitted from priorities identified at the launch of the NCP. Limitations are that this analysis relies on one source of sugar industry documents and that we could not interview key actors. Conclusions The NCP was a missed opportunity to develop a scientific understanding of how to restrict sugar consumption to prevent tooth decay. A key factor was the alignment of research agendas between the NIDR and the sugar industry. This historical example illustrates how industry protects

  10. PCRELAP5: data calculation program for RELAP 5 code; PCRELAP5: programa de calculo dos dados de entrada para o codigo RELAP5

    Energy Technology Data Exchange (ETDEWEB)

    Silvestre, Larissa Jacome Barros

    2016-07-01

    Nuclear accidents in the world led to the establishment of rigorous criteria and requirements for nuclear power plant operations by the international regulatory bodies. By using specific computer programs, simulations of various accidents and transients likely to occur at any nuclear power plant are required for certifying and licensing a nuclear power plant. Based on this scenario, some sophisticated computational tools have been used such as the Reactor Excursion and Leak Analysis Program (RELAP5), which is the most widely used code for the thermo-hydraulic analysis of accidents and transients in nuclear reactors in Brazil and worldwide. A major difficulty in the simulation by using RELAP5 code is the amount of information required for the simulation of thermal-hydraulic accidents or transients. The preparation of the input data requires a great number of mathematical operations to calculate the geometry of the components. Thus, for those calculations performance and preparation of RELAP5 input data, a friendly mathematical preprocessor was designed. The Visual Basic for Application (VBA) for Microsoft Excel demonstrated to be an effective tool to perform a number of tasks in the development of the program. In order to meet the needs of RELAP5 users, the RELAP5 Calculation Program (Programa de Calculo do RELAP5 - PCRELAP5) was designed. The components of the code were codified; all entry cards including the optional cards of each one have been programmed. In addition, an English version for PCRELAP5 was provided. Furthermore, a friendly design was developed in order to minimize the time of preparation of input data and errors committed by users. In this work, the final version of this preprocessor was successfully applied for Safety Injection System (SIS) of Angra 2. (author)

  11. Probe code: a set of programs for processing and analysis of the left ventricular function - User's manual

    International Nuclear Information System (INIS)

    Piva, R.M.V.

    1987-01-01

    The User's Manual of the Probe Code is an addendum to the M.Sc. thesis entitled A Microcomputer System of Nuclear Probe to Check the Left Ventricular Function. The Probe Code is a software which was developed for processing and off-line analysis curves from the Left Ventricular Function, that were obtained in vivo. These curves are produced by means of an external scintigraph probe, which was collimated and put on the left ventricule, after a venous inoculation of Tc-99 m. (author)

  12. Variable & Recode Definitions - SEER Documentation

    Science.gov (United States)

    Resources that define variables and provide documentation for reporting using SEER and related datasets. Choose from SEER coding and staging manuals plus instructions for recoding behavior, site, stage, cause of death, insurance, and several additional topics. Also guidance on months survived, calculating Hispanic mortality, and site-specific surgery.

  13. The Aesthetics of Coding

    DEFF Research Database (Denmark)

    Andersen, Christian Ulrik

    2007-01-01

    Computer art is often associated with computer-generated expressions (digitally manipulated audio/images in music, video, stage design, media facades, etc.). In recent computer art, however, the code-text itself – not the generated output – has become the artwork (Perl Poetry, ASCII Art, obfuscated...... code, etc.). The presentation relates this artistic fascination of code to a media critique expressed by Florian Cramer, claiming that the graphical interface represents a media separation (of text/code and image) causing alienation to the computer’s materiality. Cramer is thus the voice of a new ‘code...... avant-garde’. In line with Cramer, the artists Alex McLean and Adrian Ward (aka Slub) declare: “art-oriented programming needs to acknowledge the conditions of its own making – its poesis.” By analysing the Live Coding performances of Slub (where they program computer music live), the presentation...

  14. SGHWR - quality assurance documentation

    International Nuclear Information System (INIS)

    Garrard, R.S.; Caulfield, J.

    1976-01-01

    The quality assurance program for a modern power station such as an SGHWR type reactor plant must include a record of quality achievement. The case history record which is evidence of the actual quality of the plant and is a data bank of design, manufacture, and results of inspections and tests, is described. Documentation distribution, which keeps all key areas informed of plant item quality status, and the retrieval and storage of information, are briefly discussed. (U.K.)

  15. AUDIT plan documenting method

    International Nuclear Information System (INIS)

    Cornecsu, M.

    1995-01-01

    The work describes a method of documenting the AUDIT plan upon the basis of two quantitative elements resulting from quality assurance program appraisal system function implementation degree as established from the latest AUDIT performed an system function weight in QAP, respectively, appraised by taking into account their significance for the activities that are to be performed in the period for which the AUDITs are planned. (Author) 3 Figs., 2 Refs

  16. IMAGE Programming Guidelines

    Energy Technology Data Exchange (ETDEWEB)

    Stehfest, E; De Waal, L.

    2010-09-15

    This document describes the requirements and guidelines for the software of the IMAGE system. The motivation for this report was a substantial restructuring of the source code for IMAGE version 2.5. The requirements and guidelines relate to design considerations as well as to aspects of maintainability and portability. The design considerations determine guidelines about subjects, such as program structure, model hierarchy, the use of data modules, and the error message system. Maintainability and portability aspects determine the guidelines on, for example, the Fortran 90 standard, naming conventions, code lay-out, and internal documentation.

  17. Code, standard and specifications

    International Nuclear Information System (INIS)

    Abdul Nassir Ibrahim; Azali Muhammad; Ab. Razak Hamzah; Abd. Aziz Mohamed; Mohamad Pauzi Ismail

    2008-01-01

    Radiography also same as the other technique, it need standard. This standard was used widely and method of used it also regular. With that, radiography testing only practical based on regulations as mentioned and documented. These regulation or guideline documented in code, standard and specifications. In Malaysia, level one and basic radiographer can do radiography work based on instruction give by level two or three radiographer. This instruction was produced based on guideline that mention in document. Level two must follow the specifications mentioned in standard when write the instruction. From this scenario, it makes clearly that this radiography work is a type of work that everything must follow the rule. For the code, the radiography follow the code of American Society for Mechanical Engineer (ASME) and the only code that have in Malaysia for this time is rule that published by Atomic Energy Licensing Board (AELB) known as Practical code for radiation Protection in Industrial radiography. With the existence of this code, all the radiography must follow the rule or standard regulated automatically.

  18. Apparatus-Program Complexes Processing and Creation of Essentially non-Format Documents on the Basis of Technology Auto-Adaptive Fonts

    Directory of Open Access Journals (Sweden)

    E. G. Andrianova

    2014-01-01

    Full Text Available The need to translate paper documents into electronic form demanded a development of methods and algorithms for automatic processing systems and web publishing unformatted graphic documents of on-line libraries. Translation of scanned images into modern formats of electronic documents using OCR programmes faces serious difficulties. These difficulties are connected with the standardization set of fonts and design of printed documents. There is also a need to maintain the original form of electronic format of such documents. The article discusses the possibility for building an extensible adaptive dictionary of graphic objects, which constitute unformatted graphics documents. Dictionary automatically adjusted as graphics processing and accumulation of statistical information for each new document. This adaptive extensible dictionary of graphic letters, fonts, and other objects of automated particular document processing is called "auto-adaptive font", and a set of its application methods is named "auto-adaptive font technology."Based on the theory of estimation algorithms, a mathematical model is designed. It allows us to represent all objects of unformatted graphic document in a unified manner to build a feature vector for each object, and evaluate a similarity of these objects in the selected metric. The algorithm of the adaptive models of graphic images is developed and a criterion for combining similar properties in one element to build an auto-adaptive font is offered thus allowing us to build a software core of hardware-software complex for processing the unformatted graphic documents. A standard block diagram of hardware-software complex is developed to process the unformatted graphic documents. The article presents a description of all the blocks of this complex, including document processing station and its interaction with the web server of publishing electronic documents.

  19. High-level waste storage tank farms/242-A evaporator standards/requirements identification document (S/RID), Vol. 5

    Energy Technology Data Exchange (ETDEWEB)

    1994-04-01

    The Fire Protection functional area for the Hanford Site Tank Farm facilities and support structures is based on the application of relevant DOE orders, regulations, and industry codes and standards. The fire protection program defined in this document may be divided into three areas: (1) organizational, (2) administrative programmatic features, and (3) technical features. The information presented in each section is in the form of program elements and orders, regulations, industry codes, and standards that serve as the attributes of a fire protection program for the Tank Farm facilities. Upon completion this document will be utilized as the basis to evaluate compliance of the fire protection program being implemented for the Tank Farm facilities with the requirements of DOE orders and industry codes and standards.

  20. High-level waste storage tank farms/242-A evaporator standards/requirements identification document (S/RID), Vol. 5

    International Nuclear Information System (INIS)

    1994-04-01

    The Fire Protection functional area for the Hanford Site Tank Farm facilities and support structures is based on the application of relevant DOE orders, regulations, and industry codes and standards. The fire protection program defined in this document may be divided into three areas: (1) organizational, (2) administrative programmatic features, and (3) technical features. The information presented in each section is in the form of program elements and orders, regulations, industry codes, and standards that serve as the attributes of a fire protection program for the Tank Farm facilities. Upon completion this document will be utilized as the basis to evaluate compliance of the fire protection program being implemented for the Tank Farm facilities with the requirements of DOE orders and industry codes and standards

  1. Synthesizing Certified Code

    Science.gov (United States)

    Whalen, Michael; Schumann, Johann; Fischer, Bernd

    2002-01-01

    Code certification is a lightweight approach to demonstrate software quality on a formal level. Its basic idea is to require producers to provide formal proofs that their code satisfies certain quality properties. These proofs serve as certificates which can be checked independently. Since code certification uses the same underlying technology as program verification, it also requires many detailed annotations (e.g., loop invariants) to make the proofs possible. However, manually adding theses annotations to the code is time-consuming and error-prone. We address this problem by combining code certification with automatic program synthesis. We propose an approach to generate simultaneously, from a high-level specification, code and all annotations required to certify generated code. Here, we describe a certification extension of AUTOBAYES, a synthesis tool which automatically generates complex data analysis programs from compact specifications. AUTOBAYES contains sufficient high-level domain knowledge to generate detailed annotations. This allows us to use a general-purpose verification condition generator to produce a set of proof obligations in first-order logic. The obligations are then discharged using the automated theorem E-SETHEO. We demonstrate our approach by certifying operator safety for a generated iterative data classification program without manual annotation of the code.

  2. The path of code linting

    CERN Multimedia

    CERN. Geneva

    2017-01-01

    Join the path of code linting and discover how it can help you reach higher levels of programming enlightenment. Today we will cover how to embrace code linters to offload cognitive strain on preserving style standards in your code base as well as avoiding error-prone constructs. Additionally, I will show you the journey ahead for integrating several code linters in the programming tools your already use with very little effort.

  3. Methodology and assumptions for evaluating heating and cooling energy requirements in new single-family residential buildings: Technical support document for the PEAR (Program for Energy Analysis of Residences) microcomputer program

    Energy Technology Data Exchange (ETDEWEB)

    Huang, Y.J.; Ritschard, R.; Bull, J.; Byrne, S.; Turiel, I.; Wilson, D.; Hsui, C.; Foley, D.

    1987-01-01

    This report provides technical documentation for a software package called PEAR (Program for Energy Analysis of Residences) developed by LBL. PEAR offers an easy-to-use and accurate method of estimating the energy savings associated with various energy conservation measures used in site-built, single-family homes. This program was designed for use by non-technical groups such as home builders, home buyers or others in the buildings industry, and developed as an integral part of a set of voluntary guidelines entitled Affordable Housing Through Energy Conservation: A Guide to Designing and Constructing Energy Efficient Homes. These guidelines provide a method for selecting and evaluating cost-effective energy conservation measures based on the energy savings estimated by PEAR. This work is part of a Department of Energy program aimed at conducting research that will improve the energy efficiency of the nation's stock of conventionally-built and manufactured homes, and presenting the results to the public in a simplified format.

  4. Fracture flow code

    International Nuclear Information System (INIS)

    Dershowitz, W; Herbert, A.; Long, J.

    1989-03-01

    The hydrology of the SCV site will be modelled utilizing discrete fracture flow models. These models are complex, and can not be fully cerified by comparison to analytical solutions. The best approach for verification of these codes is therefore cross-verification between different codes. This is complicated by the variation in assumptions and solution techniques utilized in different codes. Cross-verification procedures are defined which allow comparison of the codes developed by Harwell Laboratory, Lawrence Berkeley Laboratory, and Golder Associates Inc. Six cross-verification datasets are defined for deterministic and stochastic verification of geometric and flow features of the codes. Additional datasets for verification of transport features will be documented in a future report. (13 figs., 7 tabs., 10 refs.) (authors)

  5. Spent Nuclear Fuel Project Document Management Plan

    International Nuclear Information System (INIS)

    Connor, M.D.; Harizison, G.L.; Rice, W.C.

    1995-12-01

    The SNF Project Document Management Plan identifies and describes the currently available systems and processes for implementing and maintaining an effective document control and records management program. This program governs the methods by which documents are generated, released, distributed, maintained current, retired, and ultimately disposed

  6. XSOR codes users manual

    International Nuclear Information System (INIS)

    Jow, Hong-Nian; Murfin, W.B.; Johnson, J.D.

    1993-11-01

    This report describes the source term estimation codes, XSORs. The codes are written for three pressurized water reactors (Surry, Sequoyah, and Zion) and two boiling water reactors (Peach Bottom and Grand Gulf). The ensemble of codes has been named ''XSOR''. The purpose of XSOR codes is to estimate the source terms which would be released to the atmosphere in severe accidents. A source term includes the release fractions of several radionuclide groups, the timing and duration of releases, the rates of energy release, and the elevation of releases. The codes have been developed by Sandia National Laboratories for the US Nuclear Regulatory Commission (NRC) in support of the NUREG-1150 program. The XSOR codes are fast running parametric codes and are used as surrogates for detailed mechanistic codes. The XSOR codes also provide the capability to explore the phenomena and their uncertainty which are not currently modeled by the mechanistic codes. The uncertainty distributions of input parameters may be used by an. XSOR code to estimate the uncertainty of source terms

  7. Revised C++ coding conventions

    CERN Document Server

    Callot, O

    2001-01-01

    This document replaces the note LHCb 98-049 by Pavel Binko. After a few years of practice, some simplification and clarification of the rules was needed. As many more people have now some experience in writing C++ code, their opinion was also taken into account to get a commonly agreed set of conventions

  8. Coding Partitions

    Directory of Open Access Journals (Sweden)

    Fabio Burderi

    2007-05-01

    Full Text Available Motivated by the study of decipherability conditions for codes weaker than Unique Decipherability (UD, we introduce the notion of coding partition. Such a notion generalizes that of UD code and, for codes that are not UD, allows to recover the ``unique decipherability" at the level of the classes of the partition. By tacking into account the natural order between the partitions, we define the characteristic partition of a code X as the finest coding partition of X. This leads to introduce the canonical decomposition of a code in at most one unambiguouscomponent and other (if any totally ambiguouscomponents. In the case the code is finite, we give an algorithm for computing its canonical partition. This, in particular, allows to decide whether a given partition of a finite code X is a coding partition. This last problem is then approached in the case the code is a rational set. We prove its decidability under the hypothesis that the partition contains a finite number of classes and each class is a rational set. Moreover we conjecture that the canonical partition satisfies such a hypothesis. Finally we consider also some relationships between coding partitions and varieties of codes.

  9. Documentation of TRU biological transport model (BIOTRAN)

    Energy Technology Data Exchange (ETDEWEB)

    Gallegos, A.F.; Garcia, B.J.; Sutton, C.M.

    1980-01-01

    Inclusive of Appendices, this document describes the purpose, rationale, construction, and operation of a biological transport model (BIOTRAN). This model is used to predict the flow of transuranic elements (TRU) through specified plant and animal environments using biomass as a vector. The appendices are: (A) Flows of moisture, biomass, and TRU; (B) Intermediate variables affecting flows; (C) Mnemonic equivalents (code) for variables; (D) Variable library (code); (E) BIOTRAN code (Fortran); (F) Plants simulated; (G) BIOTRAN code documentation; (H) Operating instructions for BIOTRAN code. The main text is presented with a specific format which uses a minimum of space, yet is adequate for tracking most relationships from their first appearance to their formulation in the code. Because relationships are treated individually in this manner, and rely heavily on Appendix material for understanding, it is advised that the reader familiarize himself with these materials before proceeding with the main text.

  10. Documentation of TRU biological transport model (BIOTRAN)

    International Nuclear Information System (INIS)

    Gallegos, A.F.; Garcia, B.J.; Sutton, C.M.

    1980-01-01

    Inclusive of Appendices, this document describes the purpose, rationale, construction, and operation of a biological transport model (BIOTRAN). This model is used to predict the flow of transuranic elements (TRU) through specified plant and animal environments using biomass as a vector. The appendices are: (A) Flows of moisture, biomass, and TRU; (B) Intermediate variables affecting flows; (C) Mnemonic equivalents (code) for variables; (D) Variable library (code); (E) BIOTRAN code (Fortran); (F) Plants simulated; (G) BIOTRAN code documentation; (H) Operating instructions for BIOTRAN code. The main text is presented with a specific format which uses a minimum of space, yet is adequate for tracking most relationships from their first appearance to their formulation in the code. Because relationships are treated individually in this manner, and rely heavily on Appendix material for understanding, it is advised that the reader familiarize himself with these materials before proceeding with the main text

  11. FRAC (failure rate analysis code): a computer program for analysis of variance of failure rates. An application user's guide

    International Nuclear Information System (INIS)

    Martz, H.F.; Beckman, R.J.; McInteer, C.R.

    1982-03-01

    Probabilistic risk assessments (PRAs) require estimates of the failure rates of various components whose failure modes appear in the event and fault trees used to quantify accident sequences. Several reliability data bases have been designed for use in providing the necessary reliability data to be used in constructing these estimates. In the nuclear industry, the Nuclear Plant Reliability Data System (NPRDS) and the In-Plant Reliability Data System (IRPDS), among others, were designed for this purpose. An important characteristic of such data bases is the selection and identification of numerous factors used to classify each component that is reported and the subsequent failures of each component. However, the presence of such factors often complicates the analysis of reliability data in the sense that it is inappropriate to group (that is, pool) data for those combinations of factors that yield significantly different failure rate values. These types of data can be analyzed by analysis of variance. FRAC (Failure Rate Analysis Code) is a computer code that performs an analysis of variance of failure rates. In addition, FRAC provides failure rate estimates

  12. Computer code selection criteria for flow and transport code(s) to be used in undisturbed vadose zone calculations for TWRS environmental analyses

    International Nuclear Information System (INIS)

    Mann, F.M.

    1998-01-01

    The Tank Waste Remediation System (TWRS) is responsible for the safe storage, retrieval, and disposal of waste currently being held in 177 underground tanks at the Hanford Site. In order to successfully carry out its mission, TWRS must perform environmental analyses describing the consequences of tank contents leaking from tanks and associated facilities during the storage, retrieval, or closure periods and immobilized low-activity tank waste contaminants leaving disposal facilities. Because of the large size of the facilities and the great depth of the dry zone (known as the vadose zone) underneath the facilities, sophisticated computer codes are needed to model the transport of the tank contents or contaminants. This document presents the code selection criteria for those vadose zone analyses (a subset of the above analyses) where the hydraulic properties of the vadose zone are constant in time the geochemical behavior of the contaminant-soil interaction can be described by simple models, and the geologic or engineered structures are complicated enough to require a two-or three dimensional model. Thus, simple analyses would not need to use the fairly sophisticated codes which would meet the selection criteria in this document. Similarly, those analyses which involve complex chemical modeling (such as those analyses involving large tank leaks or those analyses involving the modeling of contaminant release from glass waste forms) are excluded. The analyses covered here are those where the movement of contaminants can be relatively simply calculated from the moisture flow. These code selection criteria are based on the information from the low-level waste programs of the US Department of Energy (DOE) and of the US Nuclear Regulatory Commission as well as experience gained in the DOE Complex in applying these criteria. Appendix table A-1 provides a comparison between the criteria in these documents and those used here. This document does not define the models (that

  13. OCRWM baseline management procedure for document identifiers

    International Nuclear Information System (INIS)

    1993-03-01

    This procedure establishes a uniform numbering system (document identifier) for all Program and project technical, cost, and schedule baselines, and selected management and procurement documents developed for and controlled by the Office of Civilian Radioactive Waste Management (OCRWM) for the Civilian Radioactive Waste Management System (CRWMS). The document identifier defined in this procedure is structured to ensure that the relational integrity between configuration items (CIs) and their associated documentation and software is maintained, traceable, categorical, and retrievable for the life of the program

  14. An abstract model of rogue code insertion into radio frequency wireless networks. The effects of computer viruses on the Program Management Office

    Science.gov (United States)

    Feudo, Christopher V.

    1994-04-01

    This dissertation demonstrates that inadequately protected wireless LANs are more vulnerable to rogue program attack than traditional LANs. Wireless LANs not only run the same risks as traditional LANs, but they also run additional risks associated with an open transmission medium. Intruders can scan radio waves and, given enough time and resources, intercept, analyze, decipher, and reinsert data into the transmission medium. This dissertation describes the development and instantiation of an abstract model of the rogue code insertion process into a DOS-based wireless communications system using radio frequency (RF) atmospheric signal transmission. The model is general enough to be applied to widely used target environments such as UNIX, Macintosh, and DOS operating systems. The methodology and three modules, the prober, activator, and trigger modules, to generate rogue code and insert it into a wireless LAN were developed to illustrate the efficacy of the model. Also incorporated into the model are defense measures against remotely introduced rogue programs and a cost-benefit analysis that determined that such defenses for a specific environment were cost-justified.

  15. Quality assurance procedures for the CONTAIN severe reactor accident computer code

    International Nuclear Information System (INIS)

    Russell, N.A.; Washington, K.E.; Bergeron, K.D.; Murata, K.K.; Carroll, D.E.; Harris, C.L.

    1991-01-01

    The CONTAIN quality assurance program follows a strict set of procedures designed to ensure the integrity of the code, to avoid errors in the code, and to prolong the life of the code. The code itself is maintained under a code-configuration control system that provides a historical record of changes. All changes are incorporated using an update processor that allows separate identification of improvements made to each successive code version. Code modifications and improvements are formally reviewed and checked. An exhaustive, multilevel test program validates the theory and implementation of all codes changes through assessment calculations that compare the code-predicted results to standard handbooks of idealized test cases. A document trail and archive establish the problems solved by the software, the verification and validation of the software, software changes and subsequent reverification and revalidation, and the tracking of software problems and actions taken to resolve those problems. This document describes in detail the CONTAIN quality assurance procedures. 4 refs., 21 figs., 4 tabs

  16. Modular programming method at JAERI

    International Nuclear Information System (INIS)

    Asai, Kiyoshi; Katsuragi, Satoru

    1982-02-01

    In this report the histories, concepts and a method for the construction and maintenance of nuclear code systems of Japan Atomic Energy Research Institute (JAERI) are presented. The method is mainly consisted of novel computer features. The development process of the features and experiences with them which required many man-months and efforts of scientists and engineers of JAERI and a computer manufacturer are also described. One of the features is a file handling program named datapool. The program is being used in code systems which are under development at JAERI. The others are computer features such as dynamic linking, reentrant coding of Fortran programs, interactive programming facility, document editor, quick system output viewer and editor, flexible man-machine interactive Fortran executor, and selective use of time-sharing or batch oriented computer in an interactive porgramming environment. In 1980 JAERI has replaced its two old computer systems by three FACOM M-200 computer systems and they have such features as mentioned above. Since 1981 most code systems, or even big single codes can be changed to modular code systems even if the developers or users of the systems will not recognize the fact that they are using modular code systems. The purpose of this report is to describe our methodology of modular programming from aspects of computer features and some of their applications to nuclear codes to get sympathetic understanding of it from persons of organizations who are concerned with the effective use of computers, especially, in nuclear research fields. (author)

  17. Elaboration of data and documents intended to complement and expand the German series of nuclear engineering codes. 4. Technical report. Current knowledge of the mechanisms of corrosion fatigue in ferritic materials

    International Nuclear Information System (INIS)

    Frank, J.

    1997-01-01

    Concerning the processes of crack initiation under cyclic loading in a high-temperature water environment, examinations are performed in the USA for amending the design-basis curves published in ASME section III, which are comparable to those contained in the KTA code 3201.2. A revision of ASME section III has not yet been published. The same applies to the processes of crack propagation under cyclic loading in a high-temperature water environment, US experts examining for the purpose of amendment the limiting curves of cyclic crack propagation rates of carbon and low-alloyed steels in a water environment published in ASME section XI. (Orig./CB) [de

  18. Computer codes for safety analysis

    International Nuclear Information System (INIS)

    Holland, D.F.

    1986-11-01

    Computer codes for fusion safety analysis have been under development in the United States for about a decade. This paper will discuss five codes that are currently under development by the Fusion Safety Program. The purpose and capability of each code will be presented, a sample given, followed by a discussion of the present status and future development plans

  19. AREVA - 2013 Reference document

    International Nuclear Information System (INIS)

    2014-01-01

    This Reference Document contains information on the AREVA group's objectives, prospects and development strategies, as well as estimates of the markets, market shares and competitive position of the AREVA group. Content: 1 - Person responsible for the Reference Document; 2 - Statutory auditors; 3 - Selected financial information; 4 - Description of major risks confronting the company; 5 - Information about the issuer; 6 - Business overview; 7 - Organizational structure; 8 - Property, plant and equipment; 9 - Situation and activities of the company and its subsidiaries; 10 - Capital resources; 11 - Research and development programs, patents and licenses; 12 - Trend information; 13 - Profit forecasts or estimates; 14 - Management and supervisory bodies; 15 - Compensation and benefits; 16 - Functioning of the management and supervisory bodies; 17 - Human resources information; 18 - Principal shareholders; 19 - Transactions with related parties; 20 - Financial information concerning assets, financial positions and financial performance; 21 - Additional information; 22 - Major contracts; 23 - Third party information, statements by experts and declarations of interest; 24 - Documents on display; 25 - Information on holdings; Appendix 1: report of the supervisory board chairman on the preparation and organization of the board's activities and internal control procedures; Appendix 2: statutory auditors' reports; Appendix 3: environmental report; Appendix 4: non-financial reporting methodology and independent third-party report on social, environmental and societal data; Appendix 5: ordinary and extraordinary general shareholders' meeting; Appendix 6: values charter; Appendix 7: table of concordance of the management report; glossaries

  20. Content Documents Management

    Science.gov (United States)

    Muniz, R.; Hochstadt, J.; Boelke J.; Dalton, A.

    2011-01-01

    The Content Documents are created and managed under the System Software group with. Launch Control System (LCS) project. The System Software product group is lead by NASA Engineering Control and Data Systems branch (NEC3) at Kennedy Space Center. The team is working on creating Operating System Images (OSI) for different platforms (i.e. AIX, Linux, Solaris and Windows). Before the OSI can be created, the team must create a Content Document which provides the information of a workstation or server, with the list of all the software that is to be installed on it and also the set where the hardware belongs. This can be for example in the LDS, the ADS or the FR-l. The objective of this project is to create a User Interface Web application that can manage the information of the Content Documents, with all the correct validations and filters for administrator purposes. For this project we used one of the most excellent tools in agile development applications called Ruby on Rails. This tool helps pragmatic programmers develop Web applications with Rails framework and Ruby programming language. It is very amazing to see how a student can learn about OOP features with the Ruby language, manage the user interface with HTML and CSS, create associations and queries with gems, manage databases and run a server with MYSQL, run shell commands with command prompt and create Web frameworks with Rails. All of this in a real world project and in just fifteen weeks!

  1. Static Code Analysis with Gitlab-CI

    CERN Document Server

    Datko, Szymon Tomasz

    2016-01-01

    Static Code Analysis is a simple but efficient way to ensure that application’s source code is free from known flaws and security vulnerabilities. Although such analysis tools are often coming with more advanced code editors, there are a lot of people who prefer less complicated environments. The easiest solution would involve education – where to get and how to use the aforementioned tools. However, counting on the manual usage of such tools still does not guarantee their actual usage. On the other hand, reducing the required effort, according to the idea “setup once, use anytime without sweat” seems like a more promising approach. In this paper, the approach to automate code scanning, within the existing CERN’s Gitlab installation, is described. For realization of that project, the Gitlab-CI service (the “CI” stands for "Continuous Integration"), with Docker assistance, was employed to provide a variety of static code analysers for different programming languages. This document covers the gene...

  2. TVF-NMCRC-A powerful program for writing and executing simulation inputs for the FLUKA Monte Carlo Code system

    International Nuclear Information System (INIS)

    Mark, S.; Khomchenko, S.; Shifrin, M.; Haviv, Y.; Schwartz, J.R.; Orion, I.

    2007-01-01

    We at the Negev Monte Carlo Research Center (NMCRC) have developed a powerful new interface for writing and executing FLUKA input files-TVF-NMCRC. With the TVF tool a FLUKA user has the ability to easily write an input file without requiring any previous experience. The TVF-NMCRC tool is a LINUX program that has been verified for the most common LINUX-based operating systems, and is suitable for the latest version of FLUKA (FLUKA 2006.3)

  3. 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.

  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. Regulatory guidance document

    International Nuclear Information System (INIS)

    1994-05-01

    The Office of Civilian Radioactive Waste Management (OCRWM) Program Management System Manual requires preparation of the OCRWM Regulatory Guidance Document (RGD) that addresses licensing, environmental compliance, and safety and health compliance. The document provides: regulatory compliance policy; guidance to OCRWM organizational elements to ensure a consistent approach when complying with regulatory requirements; strategies to achieve policy objectives; organizational responsibilities for regulatory compliance; guidance with regard to Program compliance oversight; and guidance on the contents of a project-level Regulatory Compliance Plan. The scope of the RGD includes site suitability evaluation, licensing, environmental compliance, and safety and health compliance, in accordance with the direction provided by Section 4.6.3 of the PMS Manual. Site suitability evaluation and regulatory compliance during site characterization are significant activities, particularly with regard to the YW MSA. OCRWM's evaluation of whether the Yucca Mountain site is suitable for repository development must precede its submittal of a license application to the Nuclear Regulatory Commission (NRC). Accordingly, site suitability evaluation is discussed in Chapter 4, and the general statements of policy regarding site suitability evaluation are discussed in Section 2.1. Although much of the data and analyses may initially be similar, the licensing process is discussed separately in Chapter 5. Environmental compliance is discussed in Chapter 6. Safety and Health compliance is discussed in Chapter 7

  6. NASA Lewis Steady-State Heat Pipe Code Architecture

    Science.gov (United States)

    Mi, Ye; Tower, Leonard K.

    2013-01-01

    NASA Glenn Research Center (GRC) has developed the LERCHP code. The PC-based LERCHP code can be used to predict the steady-state performance of heat pipes, including the determination of operating temperature and operating limits which might be encountered under specified conditions. The code contains a vapor flow algorithm which incorporates vapor compressibility and axially varying heat input. For the liquid flow in the wick, Darcy s formula is employed. Thermal boundary conditions and geometric structures can be defined through an interactive input interface. A variety of fluid and material options as well as user defined options can be chosen for the working fluid, wick, and pipe materials. This report documents the current effort at GRC to update the LERCHP code for operating in a Microsoft Windows (Microsoft Corporation) environment. A detailed analysis of the model is presented. The programming architecture for the numerical calculations is explained and flowcharts of the key subroutines are given

  7. Examining the economics of seawater desalination using the DEEP code

    International Nuclear Information System (INIS)

    2000-11-01

    This Technical Document presents analysis of the results of the study initiated by the IAEA on comparison of costs of nuclear and fossil fuel energy sources coupled with selected seawater desalination processes, including regional studies and sensitivity analysis. The economical modelling was performed with use of the Desalination Economic Evaluation Program code (DEEP) released in 1998 which incorporated the latest advances in economic modelling and technological changes in both desalination and reactor technologies

  8. Application bar-code system for solid radioactive waste management

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Y. H.; Kim, T. K.; Kang, I. S.; Cho, H. S.; Son, J. S. [KAERI, Taejon (Korea, Republic of)

    2004-07-01

    Solid radioactive wastes are generated from the post-irradiated fuel examination facility, the irradiated material examination facility, the research reactor, and the laboratories at KAERI. A bar-code system for a solid radioactive waste management of a research organization became necessary while developing the RAWMIS(Radioactive Waste Management Integration System) which it can generate personal history management for efficient management of a waste, documents, all kinds of statistics. This paper introduces an input and output application program design to do to database with data in the results and a stream process of a treatment that analyzed the waste occurrence present situation and data by bar-code system.

  9. Computer codes for the operational control of the research reactors

    International Nuclear Information System (INIS)

    Kalker, K.J.; Nabbi, R.; Bormann, H.J.

    1986-01-01

    Four small computer codes developed by ZFR are presented, which have been used for several years during operation of the research reactors FRJ-1, FRJ-2, AVR (all in Juelich) and DR-2 (Riso, Denmark). Because of interest coming from the other reactor stations the codes are documented within the frame work of the IAEA Research Contract No. 3634/FG. The zero-dimensional burnup program CREMAT is used for reactor cores in which flux measurements at each individual fuel element are carried out during operation. The program yields burnup data for each fuel element and for the whole core. On the basis of these data, fuel reloading is prepared for the next operational period under consideration of the permitted minimum shut down reactivity of the system. The program BURNY calculates burnup for fuel elements inaccessible for flux measurements, but for which 'position weighting factors' have been measured/calculated during zero power operation of the core, and which are assumed to be constant in all operational situations. The code CURIAX calculates post-irradiation data for discharged fuel elements needed in their manipulation and transport. These three programs have been written for highly enriched fuel and take into account U-235 only. The modification of CREMAT for LEU Cores and its combiantion with ORIGEN is in preparation. KINIK is an inverse kinetic code and widely used for absorber rod calibration at the abovementioned research reactors. It includes a special polynomial subroutine which can easily be used in other codes. (orig.) [de

  10. Graphics Standards in the Computer-aided Acquisition and Logistic Support (CALS) Program, Fiscal Year 1989. Volume 1. Test Requirements Document and Extended CGM (CGEM)

    Science.gov (United States)

    1990-07-01

    at the firet meng in Munich, it was foyud isthere exis•s some avedap between the stated goals of• • DG Standards and t•e CGt e SG con ded t in cumin ... stressing importance of liaison and harmonization with closely related groups; Japan - making suggestions that the NWI and Requirements Document be improved

  11. Lean coding machine. Facilities target productivity and job satisfaction with coding automation.

    Science.gov (United States)

    Rollins, Genna

    2010-07-01

    Facilities are turning to coding automation to help manage the volume of electronic documentation, streamlining workflow, boosting productivity, and increasing job satisfaction. As EHR adoption increases, computer-assisted coding may become a necessity, not an option.

  12. User's guide for FRMOD, a zero dimensional FRM burn code

    International Nuclear Information System (INIS)

    Driemeryer, D.; Miley, G.H.

    1979-01-01

    The zero-dimensional FRM plasma burn code, FRMOD is written in the FORTRAN language and is currently available on the Control Data Corporation (CDC) 7600 computer at the Magnetic Fusion Energy Computer Center (MFECC), sponsored by the US Department of Energy, in Livermore, CA. This guide assumes that the user is familiar with the system architecture and some of the utility programs available on the MFE-7600 machine, since online documentation is available for system routines through the use of the DOCUMENT utility. Users may therefore refer to it for answers to system related questions

  13. The MESORAD dose assessment model: Computer code

    International Nuclear Information System (INIS)

    Ramsdell, J.V.; Athey, G.F.; Bander, T.J.; Scherpelz, R.I.

    1988-10-01

    MESORAD is a dose equivalent model for emergency response applications that is designed to be run on minicomputers. It has been developed by the Pacific Northwest Laboratory for use as part of the Intermediate Dose Assessment System in the US Nuclear Regulatory Commission Operations Center in Washington, DC, and the Emergency Management System in the US Department of Energy Unified Dose Assessment Center in Richland, Washington. This volume describes the MESORAD computer code and contains a listing of the code. The technical basis for MESORAD is described in the first volume of this report (Scherpelz et al. 1986). A third volume of the documentation planned. That volume will contain utility programs and input and output files that can be used to check the implementation of MESORAD. 18 figs., 4 tabs

  14. Correct coding for laboratory procedures during assisted reproductive technology cycles.

    Science.gov (United States)

    2016-04-01

    This document provides updated coding information for services related to assisted reproductive technology procedures. This document replaces the 2012 ASRM document of the same name. Copyright © 2016 American Society for Reproductive Medicine. Published by Elsevier Inc. All rights reserved.

  15. Qualifying codes under software quality assurance: Two examples as guidelines for codes that are existing or under development

    Energy Technology Data Exchange (ETDEWEB)

    Mangold, D.

    1993-05-01

    Software quality assurance is an area of concem for DOE, EPA, and other agencies due to the poor quality of software and its documentation they have received in the past. This report briefly summarizes the software development concepts and terminology increasingly employed by these agencies and provides a workable approach to scientific programming under the new requirements. Following this is a practical description of how to qualify a simulation code, based on a software QA plan that has been reviewed and officially accepted by DOE/OCRWM. Two codes have recently been baselined and qualified, so that they can be officially used for QA Level 1 work under the DOE/OCRWM QA requirements. One of them was baselined and qualified within one week. The first of the codes was the multi-phase multi-component flow code TOUGH version 1, an already existing code, and the other was a geochemistry transport code STATEQ that was under development The way to accomplish qualification for both types of codes is summarized in an easy-to-follow step-by step fashion to illustrate how to baseline and qualify such codes through a relatively painless procedure.

  16. Qualifying codes under software quality assurance: Two examples as guidelines for codes that are existing or under development

    International Nuclear Information System (INIS)

    Mangold, D.

    1993-05-01

    Software quality assurance is an area of concern for DOE, EPA, and other agencies due to the poor quality of software and its documentation they have received in the past. This report briefly summarizes the software development concepts and terminology increasingly employed by these agencies and provides a workable approach to scientific programming under the new requirements. Following this is a practical description of how to qualify a simulation code, based on a software QA plan that has been reviewed and officially accepted by DOE/OCRWM. Two codes have recently been baselined and qualified, so that they can be officially used for QA Level 1 work under the DOE/OCRWM QA requirements. One of them was baselined and qualified within one week. The first of the codes was the multi-phase multi-component flow code TOUGH version 1, an already existing code, and the other was a geochemistry transport code STATEQ that was under development The way to accomplish qualification for both types of codes is summarized in an easy-to-follow step-by step fashion to illustrate how to baseline and qualify such codes through a relatively painless procedure

  17. PREREM: an interactive data preprocessing code for INREM II. Part I: user's manual. Part II: code structure

    Energy Technology Data Exchange (ETDEWEB)

    Ryan, M.T.; Fields, D.E.

    1981-05-01

    PREREM is an interactive computer code developed as a data preprocessor for the INREM-II (Killough, Dunning, and Pleasant, 1978a) internal dose program. PREREM is intended to provide easy access to current and self-consistent nuclear decay and radionuclide-specific metabolic data sets. Provision is made for revision of metabolic data, and the code is intended for both production and research applications. Documentation for the code is in two parts. Part I is a user's manual which emphasizes interpretation of program prompts and choice of user input. Part II stresses internal structure and flow of program control and is intended to assist the researcher who wishes to revise or modify the code or add to its capabilities. PREREM is written for execution on a Digital Equipment Corporation PDP-10 System and much of the code will require revision before it can be run on other machines. The source program length is 950 lines (116 blocks) and computer core required for execution is 212 K bytes. The user must also have sufficient file space for metabolic and S-factor data sets. Further, 64 100 K byte blocks of computer storage space are required for the nuclear decay data file. Computer storage space must also be available for any output files produced during the PREREM execution. 9 refs., 8 tabs.

  18. Investigating the Simulink Auto-Coding Process

    Science.gov (United States)

    Gualdoni, Matthew J.

    2016-01-01

    the program; additionally, this is lost time that could be spent testing and analyzing the code. This is one of the more prominent issues with the auto-coding process, and while much information is available with regard to optimizing Simulink designs to produce efficient and reliable C++ code, not much research has been made public on how to reduce the code generation time. It is of interest to develop some insight as to what causes code generation times to be so significant, and determine if there are architecture guidelines or a desirable auto-coding configuration set to assist in streamlining this step of the design process for particular applications. To address the issue at hand, the Simulink coder was studied at a foundational level. For each different component type made available by the software, the features, auto-code generation time, and the format of the generated code were analyzed and documented. Tools were developed and documented to expedite these studies, particularly in the area of automating sequential builds to ensure accurate data was obtained. Next, the Ramses model was examined in an attempt to determine the composition and the types of technologies used in the model. This enabled the development of a model that uses similar technologies, but takes a fraction of the time to auto-code to reduce the turnaround time for experimentation. Lastly, the model was used to run a wide array of experiments and collect data to obtain knowledge about where to search for bottlenecks in the Ramses model. The resulting contributions of the overall effort consist of an experimental model for further investigation into the subject, as well as several automation tools to assist in analyzing the model, and a reference document offering insight to the auto-coding process, including documentation of the tools used in the model analysis, data illustrating some potential problem areas in the auto-coding process, and recommendations on areas or practices in the current

  19. DABIE: a data banking system of integral experiments for reactor core characteristics computer codes

    International Nuclear Information System (INIS)

    Matsumoto, Kiyoshi; Naito, Yoshitaka; Ohkubo, Shuji; Aoyanagi, Hideo.

    1987-05-01

    A data banking system of integral experiments for reactor core characteristics computer codes, DABIE, has been developed to lighten the burden on searching so many documents to obtain experiment data required for verification of reactor core characteristics computer code. This data banking system, DABIE, has capabilities of systematic classification, registration and easy retrieval of experiment data. DABIE consists of data bank and supporting programs. Supporting programs are data registration program, data reference program and maintenance program. The system is designed so that user can easily register information of experiment systems including figures as well as geometry data and measured data or obtain those data through TSS terminal interactively. This manual describes the system structure, how-to-use and sample uses of this code system. (author)

  20. ForTrilinos Design Document

    Energy Technology Data Exchange (ETDEWEB)

    Young, Mitchell T. [ORNL; Johnson, Seth R. [ORNL; Prokopenko, Andrey V. [ORNL; Evans, Katherine J. [ORNL; Heroux, Michael A. [Sandia National Laboratories (SNL)

    2017-08-01

    With the development of a Fortran Interface to Trilinos, ForTrilinos, modelers using modern Fortran will beable to provide their codes the capability to use solvers and other capabilities on exascale machines via astraightforward infrastructure that accesses Trilinos. This document outlines what Fortrilinos does andexplains briefly how it works. We show it provides a general access to packages via an entry point and usesan xml file from fortran code. With the first release, ForTrilinos will enable Teuchos to take xml parameterlists from Fortran code and set up data structures. It will provide access to linear solvers and eigensolvers.Several examples are provided to illustrate the capabilities in practice. We explain what the user shouldhave already with their code and what Trilinos provides and returns to the Fortran code. We provideinformation about the build process for ForTrilinos, with a practical example. In future releases, nonlinearsolvers, time iteration, advanced preconditioning techniques, and inversion of control (IoC), to enablecallbacks to Fortran routines, will be available.

  1. The International Atomic Energy Agency Flag Code

    International Nuclear Information System (INIS)

    1999-01-01

    The document reproduces the text of the IAEA Flag Code which was promulgated by the Director General on 15 September 1999, pursuant to the decision of the Board of Governors on 10 June 1999 to adopt an Agency flag as described in document GOV/1999/41 and its use in accordance with a flag code to be promulgated by the Director General

  2. The International Atomic Energy Agency Flag Code

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-11-17

    The document reproduces the text of the IAEA Flag Code which was promulgated by the Director General on 15 September 1999, pursuant to the decision of the Board of Governors on 10 June 1999 to adopt an Agency flag as described in document GOV/1999/41 and its use in accordance with a flag code to be promulgated by the Director General.

  3. Speaking Code

    DEFF Research Database (Denmark)

    Cox, Geoff

    Speaking Code begins by invoking the “Hello World” convention used by programmers when learning a new language, helping to establish the interplay of text and code that runs through the book. Interweaving the voice of critical writing from the humanities with the tradition of computing and software...

  4. Generic safety documentation model

    International Nuclear Information System (INIS)

    Mahn, J.A.

    1994-04-01

    This document is intended to be a resource for preparers of safety documentation for Sandia National Laboratories, New Mexico facilities. It provides standardized discussions of some topics that are generic to most, if not all, Sandia/NM facilities safety documents. The material provides a ''core'' upon which to develop facility-specific safety documentation. The use of the information in this document will reduce the cost of safety document preparation and improve consistency of information

  5. PROGRAMMED INSTRUCTION IN WEST AFRICA AND THE ARAB STATES, A REPORT ON TWO TRAINING WORKSHOPS. EDUCATIONAL STUDIES AND DOCUMENTS, NO. 52.

    Science.gov (United States)

    KOMOSKI, P. KENNETH; GREEN, EDWARD J.

    DURING THE SUMMER OF 1963 NINETEEN PERSONS IN RAMALLAH, JORDAN AND THIRTY-SEVEN PERSONS IN IBADAN, NIGERIA TOOK A SIX WEEK TRAINING WORKSHOP COURSE IN PROGRAMED INSTRUCTION. THE COURSE CONSISTED OF LECTURES, GROUP DISCUSSIONS, READING ASSIGNMENTS, INDIVIDUAL CONFERENCES, PROGRAM WRITING, EDITING, AND STUDENT TRIALS. THE TRAINEES MADE COMMENDABLE…

  6. Procedure and code for calculating black control rods taking into account epithermal absorption, code CAS-1; Postupak i program za proracun crnih kontrolnih sipki, uzimajuci u obzir i epitermalnu apsorpciju, CAS-1

    Energy Technology Data Exchange (ETDEWEB)

    Martinc, R; Trivunac, N; Zivkovic, Z [Boris Kidric Institute of nuclear sciences Vinca, Belgrade (Yugoslavia)

    1964-12-15

    This report describes the computer code CAS-1, calculation method and procedure applied for calculating the black control rods taking into account the epithermal neutron absorption. Results obtained for supercell method applied for regular lattice reflected in the multiplication medium is part of this report in addition to the computer code manual.

  7. Evaluation of the FRAPCON-3 Computer Code

    International Nuclear Information System (INIS)

    Jernkvist, Lars Olof; Massih, Ali

    2002-03-01

    The FRAPCON-3 computer code has been evaluated with respect to its applicability, modeling capability, user friendliness, source code structure and supporting experimental database. The code is intended for thermo-mechanical analyses of light water reactor nuclear fuel rods under steady-state operational conditions and moderate power excursions. It is applicable to both boiling- and pressurized water reactor fuel rods with UO 2 fuel, ranging up to about 65 MWd/kg U in rod average burnup. The models and numerical methods in FRAPCON-3 are relatively simple, which makes the code transparent and also fairly easy to modify and extend for the user. The fundamental equations for heat transfer, structural analysis and fuel fission gas release are solved in one-dimensional (radial) and stationary (time-independent) form, and interaction between axial segments of the rod is confined to calculations of coolant axial flow and rod internal gas pressure. The code is fairly easy to use; fuel rod design data and time histories of fuel rod power and coolant inlet conditions are input via a single text file, and the corresponding calculated variation with time of important fuel rod parameters are printed to a single output file in textual form. The results can also be presented in graphical form through an interface to the general graphics program xmgr. FRAPCON-3 also provides the possibility to export calculated results to the transient fuel rod analysis code FRAPTRAN, where the data can be used as burnup-dependent initial conditions to a postulated transient. Most of the source code to FRAPCON-3 is written in Fortran-IV, which is an archaic, non-standard dialect of the Fortran programming language. Since Fortran-IV is not accepted by all compilers for the latest standard of the language, Fortran-95, there is a risk that the source code must be partly rewritten in the future. Documentation of the code comprises (i) a general code description, which briefly presents models

  8. Evaluation of the FRAPCON-3 Computer Code

    Energy Technology Data Exchange (ETDEWEB)

    Jernkvist, Lars Olof; Massih, Ali [Quantum Technologies AB, Uppsala (Sweden)

    2002-03-01

    The FRAPCON-3 computer code has been evaluated with respect to its applicability, modeling capability, user friendliness, source code structure and supporting experimental database. The code is intended for thermo-mechanical analyses of light water reactor nuclear fuel rods under steady-state operational conditions and moderate power excursions. It is applicable to both boiling- and pressurized water reactor fuel rods with UO{sub 2} fuel, ranging up to about 65 MWd/kg U in rod average burnup. The models and numerical methods in FRAPCON-3 are relatively simple, which makes the code transparent and also fairly easy to modify and extend for the user. The fundamental equations for heat transfer, structural analysis and fuel fission gas release are solved in one-dimensional (radial) and stationary (time-independent) form, and interaction between axial segments of the rod is confined to calculations of coolant axial flow and rod internal gas pressure. The code is fairly easy to use; fuel rod design data and time histories of fuel rod power and coolant inlet conditions are input via a single text file, and the corresponding calculated variation with time of important fuel rod parameters are printed to a single output file in textual form. The results can also be presented in graphical form through an interface to the general graphics program xmgr. FRAPCON-3 also provides the possibility to export calculated results to the transient fuel rod analysis code FRAPTRAN, where the data can be used as burnup-dependent initial conditions to a postulated transient. Most of the source code to FRAPCON-3 is written in Fortran-IV, which is an archaic, non-standard dialect of the Fortran programming language. Since Fortran-IV is not accepted by all compilers for the latest standard of the language, Fortran-95, there is a risk that the source code must be partly rewritten in the future. Documentation of the code comprises (i) a general code description, which briefly presents models

  9. Quality Managment Program (QMP) report: A review of quality management programs developed in response to Title 10, Section 35.32 of the Code of Federal Regulations

    Energy Technology Data Exchange (ETDEWEB)

    Witte, M.C.

    1994-10-01

    In July of 1991, the Nuclear Regulatory Commission published a Final Rule in the Federal Register amending regulations governing medical therapeutic administrations of byproduct material and certain uses of radioactive sodium iodide. These amendments required implementation of a Quality Management Program (QMP) to provide high confidence that the byproduct material -- or radiation from byproduct material -- will be administered as directed by an authorized user physician. Herein, this rule is referred to as the QM rule. The Final Rule was published after two proposed rules had been published in the Federal Register.

  10. TRIPOLI 01, a three-dimensional polykinetic Monte Carlo program. Pt.1. Presentation of the TRIPOLI code

    International Nuclear Information System (INIS)

    Baur, A.; Bourdet, L.; Gonnord, J.; Nimal, J.C.; Vergnaud, T.

    1977-01-01

    TRIPOLI is a package of programs intended for solving the neutron polykinetic transport in any three-dimensional geometry. It is written in FORTRAN for IBM computers and the 400 kilo octets are not overflown (buffers excluded). The Monte Carlo method is used. Particular emphasis is put on the problems of reducing the calculating time through two different ways: weighting or smoothing techniques have been used for processing the strong attenuations with a reasonable computer time consumption, and the quantities have been pre-calculated to reduce to a maximum the simulation time. TRIPOLI has been conceived to solve a large scale of neutron propagation problems involving fast neutrons (calculation of radiation damage in materials, biological dose or inelastic γ production), slow neutrons (mechanical structure activation, neutron flux on control chambers or sources of capture γ radiation); near the cores (materials irradiation inside power or experimental reactors) or at large distances from the sources (activation of the secondary fluid or radiation streaming through the shields). Three new possibilities appear in TRIPOLI 2: calculations in unsteady operation, point calculations of the reaction rates using the method of 'the shockless flux after the shock', and the FINE RESPONSE method in opposition to INTEGRAL RESPONSES [fr

  11. Code of Practice

    International Nuclear Information System (INIS)

    Doyle, Colin; Hone, Christopher; Nowlan, N.V.

    1984-05-01

    This Code of Practice introduces accepted safety procedures associated with the use of alpha, beta, gamma and X-radiation in secondary schools (pupils aged 12 to 18) in Ireland, and summarises good practice and procedures as they apply to radiation protection. Typical dose rates at various distances from sealed sources are quoted, and simplified equations are used to demonstrate dose and shielding calculations. The regulatory aspects of radiation protection are outlined, and references to statutory documents are given

  12. Pharmaceutical Industry Off-label Promotion and Self-regulation: A Document Analysis of Off-label Promotion Rulings by the United Kingdom Prescription Medicines Code of Practice Authority 2003-2012.

    Directory of Open Access Journals (Sweden)

    Andreas Vilhelmsson

    2016-01-01

    Full Text Available European Union law prohibits companies from marketing drugs off-label. In the United Kingdom--as in some other European countries, but unlike the United States--industry self-regulatory bodies are tasked with supervising compliance with marketing rules. The objectives of this study were to (1 characterize off-label promotion rulings in the UK compared to the whistleblower-initiated cases in the US and (2 shed light on the UK self-regulatory mechanism for detecting, deterring, and sanctioning off-label promotion.We conducted structured reviews of rulings by the UK self-regulatory authority, the Prescription Medicines Code of Practice Authority (PMCPA, between 2003 and 2012. There were 74 off-label promotion rulings involving 43 companies and 65 drugs. Nineteen companies were ruled in breach more than once, and ten companies were ruled in breach three or more times over the 10-y period. Drawing on a typology previously developed to analyse US whistleblower complaints, we coded and analysed the apparent strategic goals of each off-label marketing scheme and the practices consistent with those alleged goals. 50% of rulings cited efforts to expand drug use to unapproved indications, and 39% and 38% cited efforts to expand beyond approved disease entities and dosing strategies, respectively. The most frequently described promotional tactic was attempts to influence prescribers (n = 72, 97%, using print material (70/72, 97%, for example, advertisements (21/70, 30%. Although rulings cited prescribers as the prime target of off-label promotion, competing companies lodged the majority of complaints (prescriber: n = 16, 22%, versus companies: n = 42, 57%. Unlike US whistleblower complaints, few UK rulings described practices targeting consumers (n = 3, 4%, payers (n = 2, 3%, or company staff (n = 2, 3%. Eight UK rulings (11% pertaining to six drugs described promotion of the same drug for the same off-label use as was alleged by whistleblowers in the US

  13. Pharmaceutical Industry Off-label Promotion and Self-regulation: A Document Analysis of Off-label Promotion Rulings by the United Kingdom Prescription Medicines Code of Practice Authority 2003-2012.

    Science.gov (United States)

    Vilhelmsson, Andreas; Davis, Courtney; Mulinari, Shai

    2016-01-01

    European Union law prohibits companies from marketing drugs off-label. In the United Kingdom--as in some other European countries, but unlike the United States--industry self-regulatory bodies are tasked with supervising compliance with marketing rules. The objectives of this study were to (1) characterize off-label promotion rulings in the UK compared to the whistleblower-initiated cases in the US and (2) shed light on the UK self-regulatory mechanism for detecting, deterring, and sanctioning off-label promotion. We conducted structured reviews of rulings by the UK self-regulatory authority, the Prescription Medicines Code of Practice Authority (PMCPA), between 2003 and 2012. There were 74 off-label promotion rulings involving 43 companies and 65 drugs. Nineteen companies were ruled in breach more than once, and ten companies were ruled in breach three or more times over the 10-y period. Drawing on a typology previously developed to analyse US whistleblower complaints, we coded and analysed the apparent strategic goals of each off-label marketing scheme and the practices consistent with those alleged goals. 50% of rulings cited efforts to expand drug use to unapproved indications, and 39% and 38% cited efforts to expand beyond approved disease entities and dosing strategies, respectively. The most frequently described promotional tactic was attempts to influence prescribers (n = 72, 97%), using print material (70/72, 97%), for example, advertisements (21/70, 30%). Although rulings cited prescribers as the prime target of off-label promotion, competing companies lodged the majority of complaints (prescriber: n = 16, 22%, versus companies: n = 42, 57%). Unlike US whistleblower complaints, few UK rulings described practices targeting consumers (n = 3, 4%), payers (n = 2, 3%), or company staff (n = 2, 3%). Eight UK rulings (11%) pertaining to six drugs described promotion of the same drug for the same off-label use as was alleged by whistleblowers in the US. However

  14. Pharmaceutical Industry Off-label Promotion and Self-regulation: A Document Analysis of Off-label Promotion Rulings by the United Kingdom Prescription Medicines Code of Practice Authority 2003–2012

    Science.gov (United States)

    Vilhelmsson, Andreas; Davis, Courtney; Mulinari, Shai

    2016-01-01

    Background European Union law prohibits companies from marketing drugs off-label. In the United Kingdom—as in some other European countries, but unlike the United States—industry self-regulatory bodies are tasked with supervising compliance with marketing rules. The objectives of this study were to (1) characterize off-label promotion rulings in the UK compared to the whistleblower-initiated cases in the US and (2) shed light on the UK self-regulatory mechanism for detecting, deterring, and sanctioning off-label promotion. Methods and Findings We conducted structured reviews of rulings by the UK self-regulatory authority, the Prescription Medicines Code of Practice Authority (PMCPA), between 2003 and 2012. There were 74 off-label promotion rulings involving 43 companies and 65 drugs. Nineteen companies were ruled in breach more than once, and ten companies were ruled in breach three or more times over the 10-y period. Drawing on a typology previously developed to analyse US whistleblower complaints, we coded and analysed the apparent strategic goals of each off-label marketing scheme and the practices consistent with those alleged goals. 50% of rulings cited efforts to expand drug use to unapproved indications, and 39% and 38% cited efforts to expand beyond approved disease entities and dosing strategies, respectively. The most frequently described promotional tactic was attempts to influence prescribers (n = 72, 97%), using print material (70/72, 97%), for example, advertisements (21/70, 30%). Although rulings cited prescribers as the prime target of off-label promotion, competing companies lodged the majority of complaints (prescriber: n = 16, 22%, versus companies: n = 42, 57%). Unlike US whistleblower complaints, few UK rulings described practices targeting consumers (n = 3, 4%), payers (n = 2, 3%), or company staff (n = 2, 3%). Eight UK rulings (11%) pertaining to six drugs described promotion of the same drug for the same off-label use as was alleged by

  15. AREVA - 2012 Reference document

    International Nuclear Information System (INIS)

    2013-03-01

    After a presentation of the person responsible for this Reference Document, of statutory auditors, and of a summary of financial information, this report address the different risk factors: risk management and coverage, legal risk, industrial and environmental risk, operational risk, risk related to major projects, liquidity and market risk, and other risks (related to political and economic conditions, to Group's structure, and to human resources). The next parts propose information about the issuer, a business overview (markets for nuclear power and renewable energies, customers and suppliers, group's strategy, operations), a brief presentation of the organizational structure, a presentation of properties, plants and equipment (principal sites, environmental issues which may affect these items), analysis and comments on the group's financial position and performance, a presentation of capital resources, a presentation of research and development activities (programs, patents and licenses), a brief description of financial objectives and profit forecasts or estimates, a presentation of administration, management and supervision bodies, a description of the operation of corporate bodies, an overview of personnel, of principal shareholders, and of transactions with related parties, a more detailed presentation of financial information concerning assets, financial positions and financial performance. Addition information regarding share capital is given, as well as an indication of major contracts, third party information, available documents, and information on holdings

  16. AREVA 2010 Reference document

    International Nuclear Information System (INIS)

    2010-01-01

    After a presentation of the person responsible for this document, and of statutory auditors, this report proposes some selected financial information. Then, it addresses, presents and comments the different risk factors: risk management and coverage, legal risk, industrial and environmental risk, operational risk, risks related to major projects, liquidity and market risk, and other risk. Then, after a presentation of the issuer, it proposes a business overview (markets for nuclear and renewable energies, AREVA customers and suppliers, strategy, activities), a presentation of the organizational structure, a presentation of AREVA properties, plants and equipment (sites, environmental issues), an analysis and comment of the group's financial position and performance, a presentation of its capital resources, an overview of its research and development activities, programs, patents and licenses. It indicates profit forecast and estimates, presents the administrative, management and supervisory bodies, and compensation and benefits amounts, reports of the functioning of corporate bodies. It describes the human resource company policy, indicates the main shareholders and transactions with related parties. It proposes financial information concerning assets, financial positions and financial performance. This document contains its French and its English versions

  17. Test and evaluation document for DOT Specification 7A Type A Packaging. Revision 3

    International Nuclear Information System (INIS)

    1996-01-01

    The US Department of Energy (DOE) has been conducting, through several of its operating contractors, an evaluation and testing program to qualify Type A radioactive material packagings per US Department of Transportation (DOT) Specification 7A (DOT-7A) of the Code of Federal Regulations (CFR), Title 49, Part 178 (49 CFR 178). The program is currently administered by the DOE, Office of Facility Safety Analysis, DOE/EH-32, at DOE-Headquarters (DOE-HQ) in Germantown, Maryland. This document summarizes the evaluation and testing performed for all of the packagings successfully qualified in this program

  18. Test and evaluation document for DOT Specification 7A Type A Packaging. Revision 3

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-01-30

    The US Department of Energy (DOE) has been conducting, through several of its operating contractors, an evaluation and testing program to qualify Type A radioactive material packagings per US Department of Transportation (DOT) Specification 7A (DOT-7A) of the Code of Federal Regulations (CFR), Title 49, Part 178 (49 CFR 178). The program is currently administered by the DOE, Office of Facility Safety Analysis, DOE/EH-32, at DOE-Headquarters (DOE-HQ) in Germantown, Maryland. This document summarizes the evaluation and testing performed for all of the packagings successfully qualified in this program.

  19. Areva, reference document 2006

    International Nuclear Information System (INIS)

    2006-01-01

    This reference document contains information on the AREVA group's objectives, prospects and development strategies, particularly in Chapters 4 and 7. It contains information on the markets, market shares and competitive position of the AREVA group. Content: - 1 Person responsible for the reference document and persons responsible for auditing the financial statements; - 2 Information pertaining to the transaction (Not applicable); - 3 General information on the company and its share capital: Information on AREVA, on share capital and voting rights, Investment certificate trading, Dividends, Organization chart of AREVA group companies, Equity interests, Shareholders' agreements; - 4 Information on company operations, new developments and future prospects: Overview and strategy of the AREVA group, The Nuclear Power and Transmission and Distribution markets, The energy businesses of the AREVA group, Front End division, Reactors and Services division, Back End division, Transmission and Distribution division, Major contracts, The principal sites of the AREVA group, AREVA's customers and suppliers, Sustainable Development and Continuous Improvement, Capital spending programs, Research and development programs, intellectual property and trademarks, Risk and insurance; - 5 Assets - Financial position - Financial performance: Analysis of and comments on the group's financial position and performance, 2006 Human Resources Report, Environmental Report, Consolidated financial statements, Notes to the consolidated financial statements, AREVA SA financial statements, Notes to the corporate financial statements; 6 - Corporate Governance: Composition and functioning of corporate bodies, Executive compensation, Profit-sharing plans, AREVA Values Charter, Annual Combined General Meeting of Shareholders of May 3, 2007; 7 - Recent developments and future prospects: Events subsequent to year-end closing for 2006, Outlook; 8 - Glossary; 9 - Table of concordance

  20. Areva reference document 2007

    International Nuclear Information System (INIS)

    2008-01-01

    This reference document contains information on the AREVA group's objectives, prospects and development strategies, particularly in Chapters 4 and 7. It contains also information on the markets, market shares and competitive position of the AREVA group. Content: 1 - Person responsible for the reference document and persons responsible for auditing the financial statements; 2 - Information pertaining to the transaction (not applicable); 3 - General information on the company and its share capital: Information on Areva, Information on share capital and voting rights, Investment certificate trading, Dividends, Organization chart of AREVA group companies, Equity interests, Shareholders' agreements; 4 - Information on company operations, new developments and future prospects: Overview and strategy of the AREVA group, The Nuclear Power and Transmission and Distribution markets, The energy businesses of the AREVA group, Front End division, Reactors and Services division, Back End division, Transmission and Distribution division, Major contracts 140 Principal sites of the AREVA group, AREVA's customers and suppliers, Sustainable Development and Continuous Improvement, Capital spending programs, Research and Development programs, Intellectual Property and Trademarks, Risk and insurance; 5 - Assets financial position financial performance: Analysis of and comments on the group's financial position and performance, Human Resources report, Environmental report, Consolidated financial statements 2007, Notes to the consolidated financial statements, Annual financial statements 2007, Notes to the corporate financial statements; 6 - Corporate governance: Composition and functioning of corporate bodies, Executive compensation, Profit-sharing plans, AREVA Values Charter, Annual Ordinary General Meeting of Shareholders of April 17, 2008; 7 - Recent developments and future prospects: Events subsequent to year-end closing for 2007, Outlook; Glossary; table of concordance