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Sample records for code manual 3rd

  1. SEVERO code - user's manual

    International Nuclear Information System (INIS)

    Sacramento, A.M. do.

    1989-01-01

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

  2. Manually operated coded switch

    International Nuclear Information System (INIS)

    Barnette, J.H.

    1978-01-01

    The disclosure related to a manually operated recodable coded switch in which a code may be inserted, tried and used to actuate a lever controlling an external device. After attempting a code, the switch's code wheels must be returned to their zero positions before another try is made

  3. International Code Centres Network. Summary Report of the 3rd Biennial Technical Meeting

    International Nuclear Information System (INIS)

    Chung, Hyun-Kyung

    2013-07-01

    This report summarizes the proceedings of the third Technical Meeting of the International Code Centres Network held on 6-8 May in 2013. Ten experts from seven member states and four IAEA staff members attended the three-day meeting held at the IAEA Headquarters in Vienna to discuss issues on uncertainty estimates of theoretical atomic and molecular data. The report includes discussions on data issues, meeting conclusions and recommendations for the IAEA Atomic and Molecular Data Unit. (author)

  4. MELCOR computer code manuals

    Energy Technology Data Exchange (ETDEWEB)

    Summers, R.M.; Cole, R.K. Jr.; Smith, R.C.; Stuart, D.S.; Thompson, S.L. [Sandia National Labs., Albuquerque, NM (United States); Hodge, S.A.; Hyman, C.R.; Sanders, R.L. [Oak Ridge National Lab., TN (United States)

    1995-03-01

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

  5. MELCOR computer code manuals

    International Nuclear Information System (INIS)

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

    1995-03-01

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

  6. MARS CODE MANUAL VOLUME III - Programmer's Manual

    International Nuclear Information System (INIS)

    Chung, Bub Dong; Hwang, Moon Kyu; Jeong, Jae Jun; Kim, Kyung Doo; Bae, Sung Won; Lee, Young Jin; Lee, Won Jae

    2010-02-01

    Korea Advanced Energy Research Institute (KAERI) conceived and started the development of MARS code with the main objective of producing a state-of-the-art realistic thermal hydraulic systems analysis code with multi-dimensional analysis capability. MARS achieves this objective by very tightly integrating the one dimensional RELAP5/MOD3 with the multi-dimensional COBRA-TF codes. The method of integration of the two codes is based on the dynamic link library techniques, and the system pressure equation matrices of both codes are implicitly integrated and solved simultaneously. In addition, the Equation-Of-State (EOS) for the light water was unified by replacing the EOS of COBRA-TF by that of the RELAP5. This programmer's manual provides a complete list of overall information of code structure and input/output function of MARS. In addition, brief descriptions for each subroutine and major variables used in MARS are also included in this report, so that this report would be very useful for the code maintenance. The overall structure of the manual is modeled on the structure of the RELAP5 and as such the layout of the manual is very similar to that of the RELAP. This similitude to RELAP5 input is intentional as this input scheme will allow minimum modification between the inputs of RELAP5 and MARS3.1. MARS3.1 development team would like to express its appreciation to the RELAP5 Development Team and the USNRC for making this manual possible

  7. 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

  8. Tokamak simulation code manual

    International Nuclear Information System (INIS)

    Chung, Moon Kyoo; Oh, Byung Hoon; Hong, Bong Keun; Lee, Kwang Won

    1995-01-01

    The method to use TSC (Tokamak Simulation Code) developed by Princeton plasma physics laboratory is illustrated. In KT-2 tokamak, time dependent simulation of axisymmetric toroidal plasma and vertical stability have to be taken into account in design phase using TSC. In this report physical modelling of TSC are described and examples of application in JAERI and SERI are illustrated, which will be useful when TSC is installed KAERI computer system. (Author) 15 refs., 6 figs., 3 tabs

  9. Transient analysis of mercury experimental loop using the RELAP5 code. 3rd report. Transient analysis using mercury properties

    International Nuclear Information System (INIS)

    Kinoshita, Hidetaka; Kaminaga, Masanori; Hino, Ryutaro

    2000-02-01

    In order to promote the Neutron Science Project of JAERI, the design of a 5MW-spallation target system is in progress with the purpose of producing a practical neutron application while at the same time adhering to the highest levels of safety. To establish the safety of the target system, it is important to understand the transient behaviors during anticipated operational events of the system, and to design the safety protection systems for the safe termination of the transients. This report presents the analytical results of transient behaviors in the mercury experimental loop using mercury properties. At first, the analytical pressure distributions were compared with experimental data measured with the mercury experimental loop. The modeling data were modified to reproduce the actual pressure distributions of the mercury experimental loop. Then a loss of forced convection and a loss of coolant accident were analyzed. In the case of the pump trip, the transient analysis was conducted using two types of mercury pumps, the mechanical type pump with moment of inertia, and the electrical-magnetic type pump without moment of inertia. The results show there was no clear difference in the two analyses, since the mercury had a large inertia, which was 13.5 times that of the water. Moreover, in the case of a pipe rupture at the pump exit, a moderate pressure decrease was confirmed when a small breakage area existed in which the coolant flowed out gradually. Based on these results, it was appeared that the transient fluctuation of pressure in the mercury loop would not become large and accidents would have to be detected by small fluctuations in pressure. Based on these analyses, we plan to conduct a simulation test to verify the RELAP5 code, and then the analysis of a full-scale mercury system will be performed. (author)

  10. Nuclear science references coding manual

    International Nuclear Information System (INIS)

    Ramavataram, S.; Dunford, C.L.

    1996-08-01

    This manual is intended as a guide to Nuclear Science References (NSR) compilers. The basic conventions followed at the National Nuclear Data Center (NNDC), which are compatible with the maintenance and updating of and retrieval from the Nuclear Science References (NSR) file, are outlined. In Section H, the structure of the NSR file such as the valid record identifiers, record contents, text fields as well as the major TOPICS for which are prepared are enumerated. Relevant comments regarding a new entry into the NSR file, assignment of , generation of and linkage characteristics are also given in Section II. In Section III, a brief definition of the Keyword abstract is given followed by specific examples; for each TOPIC, the criteria for inclusion of an article as an entry into the NSR file as well as coding procedures are described. Authors preparing Keyword abstracts either to be published in a Journal (e.g., Nucl. Phys. A) or to be sent directly to NNDC (e.g., Phys. Rev. C) should follow the illustrations in Section III. The scope of the literature covered at the NNDC, the categorization into Primary and Secondary sources, etc., is discussed in Section IV. Useful information regarding permitted character sets, recommended abbreviations, etc., is given under Section V as Appendices

  11. Nuclear structure references coding manual

    International Nuclear Information System (INIS)

    Ramavataram, S.; Dunford, C.L.

    1984-02-01

    This manual is intended as a guide to Nuclear Structure References (NSR) compilers. The basic conventions followed at the National Nuclear Data Center (NNDC), which are compatible with the maintenance and updating of and retrieval from the Nuclear Structure References (NSR) file, are outlined. The structure of the NSR file such as the valid record identifiers, record contents, text fields as well as the major topics for which [KEYWORDS] are prepared are ennumerated. Relevant comments regarding a new entry into the NSR file, assignment of [KEYNO ], generation of [SELECTRS] and linkage characteristics are also given. A brief definition of the Keyword abstract is given followed by specific examples; for each TOPIC, the criteria for inclusion of an article as an entry into the NSR file as well as coding procedures are described. Authors submitting articles to Journals which require Keyword abstracts should follow the illustrations. The scope of the literature covered at NNDC, the categorization into Primary and Secondary sources, etc. is discussed. Useful information regarding permitted character sets, recommended abbreviations, etc. is given

  12. ARES: automated response function code. Users manual

    International Nuclear Information System (INIS)

    Maung, T.; Reynolds, G.M.

    1981-06-01

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

  13. User's manual of Tokamak Simulation Code

    International Nuclear Information System (INIS)

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

    1992-12-01

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

  14. User manual of UNF code

    International Nuclear Information System (INIS)

    Zhang Jingshang

    2001-01-01

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

  15. The 3rd power unit roofing decontamination

    International Nuclear Information System (INIS)

    Samojlenko, Yu.N.; Golubev, V.V.

    1989-01-01

    The most features of the 3rd power unit (PU) roofing decontamination are described: 1) the most active materials were thrown into the 4th PU ruins before the Ukrytie construction completion; 2) the decontamination was fulfilled using remote-controlled mechanisms and manual devices (the main part). 6 figs.; 1 tab

  16. TASS code topical report. V.1 TASS code technical manual

    International Nuclear Information System (INIS)

    Sim, Suk K.; Chang, W. P.; Kim, K. D.; Kim, H. C.; Yoon, H. Y.

    1997-02-01

    TASS 1.0 code has been developed at KAERI for the initial and reload non-LOCA safety analysis for the operating PWRs as well as the PWRs under construction in Korea. TASS code will replace various vendor's non-LOCA safety analysis codes currently used for the Westinghouse and ABB-CE type PWRs in Korea. This can be achieved through TASS code input modifications specific to each reactor type. The TASS code can be run interactively through the keyboard operation. A simimodular configuration used in developing the TASS code enables the user easily implement new models. TASS code has been programmed using FORTRAN77 which makes it easy to install and port for different computer environments. The TASS code can be utilized for the steady state simulation as well as the non-LOCA transient simulations such as power excursions, reactor coolant pump trips, load rejections, loss of feedwater, steam line breaks, steam generator tube ruptures, rod withdrawal and drop, and anticipated transients without scram (ATWS). The malfunctions of the control systems, components, operator actions and the transients caused by the malfunctions can be easily simulated using the TASS code. This technical report describes the TASS 1.0 code models including reactor thermal hydraulic, reactor core and control models. This TASS code models including reactor thermal hydraulic, reactor core and control models. This TASS code technical manual has been prepared as a part of the TASS code manual which includes TASS code user's manual and TASS code validation report, and will be submitted to the regulatory body as a TASS code topical report for a licensing non-LOCA safety analysis for the Westinghouse and ABB-CE type PWRs operating and under construction in Korea. (author). 42 refs., 29 tabs., 32 figs

  17. ESP-TIMOC code manual

    International Nuclear Information System (INIS)

    Jaarsma, R.; Perlado, J.M.; Rief, H.

    1978-01-01

    ESP-TIMOC is an 'Event Scanning Program' to analyse the events (collision or boundary crossing parameters) of Monte Carlo particle transport problems. It is a modular program and belongs to the TIMOC code system. ESP-TIMOC is primarily designed to calculate the time dependent response functions such as energy dependent fluxes and currents at interfaces. An eventual extension to other quantities is simple and straight forward

  18. User's manual for the TMAD code

    International Nuclear Information System (INIS)

    Finfrock, S.H.

    1995-01-01

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

  19. 3rd Abel Symposium

    CERN Document Server

    Owren, Brynjulf

    2008-01-01

    The 2006 Abel symposium is focusing on contemporary research involving interaction between computer science, computational science and mathematics. In recent years, computation has been affecting pure mathematics in fundamental ways. Conversely, ideas and methods of pure mathematics are becoming increasingly important within computational and applied mathematics. At the core of computer science is the study of computability and complexity for discrete mathematical structures. Studying the foundations of computational mathematics raises similar questions concerning continuous mathematical structures. There are several reasons for these developments. The exponential growth of computing power is bringing computational methods into ever new application areas. Equally important is the advance of software and programming languages, which to an increasing degree allows the representation of abstract mathematical structures in program code. Symbolic computing is bringing algorithms from mathematical analysis into the...

  20. MARS code manual volume II: input requirements

    International Nuclear Information System (INIS)

    Chung, Bub Dong; Kim, Kyung Doo; Bae, Sung Won; Jeong, Jae Jun; Lee, Seung Wook; Hwang, Moon Kyu

    2010-02-01

    Korea Advanced Energy Research Institute (KAERI) conceived and started the development of MARS code with the main objective of producing a state-of-the-art realistic thermal hydraulic systems analysis code with multi-dimensional analysis capability. MARS achieves this objective by very tightly integrating the one dimensional RELAP5/MOD3 with the multi-dimensional COBRA-TF codes. The method of integration of the two codes is based on the dynamic link library techniques, and the system pressure equation matrices of both codes are implicitly integrated and solved simultaneously. In addition, the Equation-Of-State (EOS) for the light water was unified by replacing the EOS of COBRA-TF by that of the RELAP5. This input manual provides a complete list of input required to run MARS. The manual is divided largely into two parts, namely, the one-dimensional part and the multi-dimensional part. The inputs for auxiliary parts such as minor edit requests and graph formatting inputs are shared by the two parts and as such mixed input is possible. The overall structure of the input is modeled on the structure of the RELAP5 and as such the layout of the manual is very similar to that of the RELAP. This similitude to RELAP5 input is intentional as this input scheme will allow minimum modification between the inputs of RELAP5 and MARS3.1. MARS3.1 development team would like to express its appreciation to the RELAP5 Development Team and the USNRC for making this manual possible

  1. Manual risk zoning wind turbines. Final version. 3rd updated version May 2013. 3 ed.; Handboek risicozonering windturbines. Eindversie. 3e geactualiseerde versie mei 2013

    Energy Technology Data Exchange (ETDEWEB)

    Faasen, C.J.; Franck, P.A.L.; Taris, A.M.H.W. [DNV KEMA, Arnhem (Netherlands)

    2013-05-15

    The title manual has been drafted to be able to quickly inventory the safety risks of wind turbines, which can speed up the licensing procedures for the installation of wind turbines. Attention is paid to the following categories: building areas, roads, waterways, railroads, industrial areas, underground cables and mains, aboveground cables, power transmission lines, dikes and dams, and telecommunication. For each of these categories the risks are calculated. This is an updated version of the manual which was first published in 2000 and updated in 2005 [Dutch] Dit is een actualisatie van het Handboek uit 2005. Het oorspronkelijke Handboek is in 2000 opgesteld. Het in 2000 verschenen Handboek is door ECN samengesteld in opdracht van Novem (nu: Agentschap NL) met als doel een uniforme methode te bieden voor het uitvoeren van kwantitatieve risicoanalyses en voor het toetsen van de resultaten aan acceptatiecriteria. Dit Handboek bood antwoord op de vraag van zowel projectontwikkelaars als overheden naar een algemeen geldende methode om veiligheidsrisico's van windturbines te berekenen voor diverse omgevingsaspecten. In 2005 is een actualisatie van het Handboek uitgebracht door ECN en KEMA in opdracht van SenterNovem (nu onderdeel van Agentschap NL). Daarin is verder ingegaan op turbines met grotere vermogens en is het Handboek aangevuld met rekenvoorbeelden. Vanwege de verdere ontwikkeling van de windturbinetechnologie, aangepaste wetgeving, het feit dat rekenmodellen verouderd waren en dat diverse infrastructuur steeds vaker gebundeld of geclusterd met windturbines wordt gerealiseerd, is het wenselijk / noodzakelijk de eventuele risico's op een consistente en eenduidige wijze in kaart te brengen. Daarom heeft Agentschap NL in 2012 opdracht gegeven aan DNV KEMA om het Handboek opnieuw te actualiseren. Hierbij zijn de resultaten van het rapport: 'Rekenmethodiek zonering windturbines in relatie tot gas- en elektrische infrastructuur' (2012), dat in

  2. SSC-K code user's manual

    Energy Technology Data Exchange (ETDEWEB)

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

    2000-07-01

    The Supper System Code of KAERI (SSC-K) is a best-estimate system code for analyzing a variety of off-normal or accidents in the heat transport system of a pool type LMR design. It is being developed at Korea Atomic Energy Research Inititution (KAERI) on the basis of SSC-L, originally developed at BNL to analyze loop-type LMR transients. SSC-K can handle both designs of loop and pool type LMRs. SSC-K contains detailed mechanistic models of transient thermal, hydraulic, neutronic, and mechanical phenomena to describe the response of the reactor core, coolant, fuel elements, and structures to accident conditions. This report provides an overview of recent model developmentsvfor the SSC-K computer code, focusing on phenomenological model descriptions for new thermal, hydraulic, neutronic, and mechnaical modules. A comprehensive description of the models for pool-type reactor is given in Chapters 2 and 3; the steady-state plant characterization, prior to the initiation of transient is described in Chapter 2 and their transient counterparts are discussed in Chapter 3. In Chapter 4, a discussion on the intermediate heat exchanger (IHX) is presented. The IHX model of SSC-K is similar to that used in the SSC-L, except for some changes required for the pool-type configuration of reactor vessel. In Chapter 5, an electromagnetic (EM) pump is modeled as a component. There are two pump choices available in SSC-K; a centrifugal pump which was originally imbedded into the SSC-L, and an EM pump which was introduced for the KALIMER design. In Chapter 6, a model of passive safety decay heat removal system(PSDRS) is discussed, which removes decay heat through the reactor and containment vessel walls to the ambient air heat sink. In Chapter 7, models for various reactivity feedback effects are discussed. Reactivity effects of importance in fast reactor include the Doppler effect, effects of sodium density changes, effects of dimensional changes in core geometry. Finally in Chapter 8

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

    International Nuclear Information System (INIS)

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

    1999-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1999-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Maung, T.; Reynolds, G.M.

    1981-06-01

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

  6. User's manual for a measurement simulation code

    International Nuclear Information System (INIS)

    Kern, E.A.

    1982-07-01

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

  7. User's manual for a process model code

    International Nuclear Information System (INIS)

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

    1981-03-01

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

  8. User manual of FRAPCON-I computer code

    International Nuclear Information System (INIS)

    Chia, C.T.

    1985-11-01

    The manual for using the FRAPCON-I code implanted by Reactor Department of Brazilian-CNEN to convert IBM FORTRAN in FORTRAN 77 of Honeywell Bull computer is presented. The FRAPCON-I code describes the behaviour of fuel rods of PWR type reactors at stationary state during long periods of burnup. (M.C.K.)

  9. Citham-2 computer code-User manual

    International Nuclear Information System (INIS)

    Batista, J.L.

    1984-01-01

    The procedures and the input data for the Citham-2 computer code are described. It is a subroutine that modifies the nuclide concentration taking in account its burn and prepares cross sections library in 2,3 or 4 energy groups, to the used for Citation program. (E.G.) [pt

  10. MARS CODE MANUAL VOLUME V: Models and Correlations

    International Nuclear Information System (INIS)

    Chung, Bub Dong; Bae, Sung Won; Lee, Seung Wook; Yoon, Churl; Hwang, Moon Kyu; Kim, Kyung Doo; Jeong, Jae Jun

    2010-02-01

    Korea Advanced Energy Research Institute (KAERI) conceived and started the development of MARS code with the main objective of producing a state-of-the-art realistic thermal hydraulic systems analysis code with multi-dimensional analysis capability. MARS achieves this objective by very tightly integrating the one dimensional RELAP5/MOD3 with the multi-dimensional COBRA-TF codes. The method of integration of the two codes is based on the dynamic link library techniques, and the system pressure equation matrices of both codes are implicitly integrated and solved simultaneously. In addition, the Equation-Of-State (EOS) for the light water was unified by replacing the EOS of COBRA-TF by that of the RELAP5. This models and correlations manual provides a complete list of detailed information of the thermal-hydraulic models used in MARS, so that this report would be very useful for the code users. The overall structure of the manual is modeled on the structure of the RELAP5 and as such the layout of the manual is very similar to that of the RELAP. This similitude to RELAP5 input is intentional as this input scheme will allow minimum modification between the inputs of RELAP5 and MARS3.1. MARS3.1 development team would like to express its appreciation to the RELAP5 Development Team and the USNRC for making this manual possible

  11. Colloid transport code-nuclear user's manual

    International Nuclear Information System (INIS)

    Jain, R.

    1992-01-01

    This report describes the CTCN computer code, designed to solve the equations of transient colloidal transport of radionuclides in porous and fractured media. This Fortran 77 package solves systems of coupled nonlinear differential equations with a wide range of boundary conditions. The package uses the Method of Lines technique with a special section which forms finite-difference discretizations in up to four spatial dimensions to automatically convert the system into a set of ordinary differential equations. The CTCN code then solves these equations using a robust, efficient ODE solver. Thus CTCN can be used to solve population balance equations along with the usual transport equations to model colloid transport processes or as a general problem solver to treat up to four-dimensional differential systems

  12. Manual phased arrays for weld inspections using North American codes

    International Nuclear Information System (INIS)

    Moles, Michael

    2008-01-01

    Phased arrays are primarily a method of generating and receiving ultrasound, not a new technology. In addition, the physics of ultrasound generated by phased arrays is identical to that from conventional monocrystals. Not surprisingly, all the major North American (and some European) codes accept phased arrays, either explicitly or implicitly. However, the technique and procedures needs to be proven, typically by a Performance Demonstration. The ASME (AmeicanSociety for Mechanical Engineers) Section V and API RP2X explicitly accept phased arrays. Three ASME code cases have been written specifically fo manual phased array: Code Cases 2541. 2557 and 2558. Over and above the general requirements of Article 4, these Code Cases require full waveform calibration. This is echoed in ASTM E-2491, a Standard Guide for setting up phased arrays. In addition. details such as focusing and reporting are addressed. The American Petroleum Institute QUTE procedure did not need any modifications to be compatible with manual phased arrays. The American Welding Society (AWS) Structural Welding Code D1.1 implicitly accepts phased arrays. New technologies such as phased arrays can be proven using Annex K. Nonetheless, a manual phased array unit using the standard AWS probe and displaying 45, 60 and 70degrees waveforms would be acceptable for D1.1 a s is . Overall, most major North American codes accept phased arrays, however, the technique and procedures must be proven, often using a Performance Demonstration. (author)

  13. MARS code manual volume I: code structure, system models, and solution methods

    International Nuclear Information System (INIS)

    Chung, Bub Dong; Kim, Kyung Doo; Bae, Sung Won; Jeong, Jae Jun; Lee, Seung Wook; Hwang, Moon Kyu; Yoon, Churl

    2010-02-01

    Korea Advanced Energy Research Institute (KAERI) conceived and started the development of MARS code with the main objective of producing a state-of-the-art realistic thermal hydraulic systems analysis code with multi-dimensional analysis capability. MARS achieves this objective by very tightly integrating the one dimensional RELAP5/MOD3 with the multi-dimensional COBRA-TF codes. The method of integration of the two codes is based on the dynamic link library techniques, and the system pressure equation matrices of both codes are implicitly integrated and solved simultaneously. In addition, the Equation-Of-State (EOS) for the light water was unified by replacing the EOS of COBRA-TF by that of the RELAP5. This theory manual provides a complete list of overall information of code structure and major function of MARS including code architecture, hydrodynamic model, heat structure, trip / control system and point reactor kinetics model. Therefore, this report would be very useful for the code users. The overall structure of the manual is modeled on the structure of the RELAP5 and as such the layout of the manual is very similar to that of the RELAP. This similitude to RELAP5 input is intentional as this input scheme will allow minimum modification between the inputs of RELAP5 and MARS3.1. MARS3.1 development team would like to express its appreciation to the RELAP5 Development Team and the USNRC for making this manual possible

  14. Module type plant system dynamics analysis code (MSG-COPD). Code manual

    International Nuclear Information System (INIS)

    Sakai, Takaaki

    2002-11-01

    MSG-COPD is a module type plant system dynamics analysis code which involves a multi-dimensional thermal-hydraulics calculation module to analyze pool type of fast breeder reactors. Explanations of each module and the methods for the input data are described in this code manual. (author)

  15. Sample problem manual for benchmarking of cask analysis codes

    International Nuclear Information System (INIS)

    Glass, R.E.

    1988-02-01

    A series of problems have been defined to evaluate structural and thermal codes. These problems were designed to simulate the hypothetical accident conditions given in Title 10 of the Code of Federal Regulation, Part 71 (10CFR71) while retaining simple geometries. This produced a problem set that exercises the ability of the codes to model pertinent physical phenomena without requiring extensive use of computer resources. The solutions that are presented are consensus solutions based on computer analyses done by both national laboratories and industry in the United States, United Kingdom, France, Italy, Sweden, and Japan. The intent of this manual is to provide code users with a set of standard structural and thermal problems and solutions which can be used to evaluate individual codes. 19 refs., 19 figs., 14 tabs

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

    International Nuclear Information System (INIS)

    Zhang, Jingshang

    2006-03-01

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

  17. Lecture Notes in Statistics. 3rd Semester

    DEFF Research Database (Denmark)

    The lecture note is prepared to meet the requirements for the 3rd semester course in statistics at the Aarhus School of Business. It focuses on multiple regression models, analysis of variance, and log-linear models.......The lecture note is prepared to meet the requirements for the 3rd semester course in statistics at the Aarhus School of Business. It focuses on multiple regression models, analysis of variance, and log-linear models....

  18. Mars 2.2 code manual: input requirements

    International Nuclear Information System (INIS)

    Chung, Bub Dong; Lee, Won Jae; Jeong, Jae Jun; Lee, Young Jin; Hwang, Moon Kyu; Kim, Kyung Doo; Lee, Seung Wook; Bae, Sung Won

    2003-07-01

    Korea Advanced Energy Research Institute (KAERI) conceived and started the development of MARS code with the main objective of producing a state-of-the-art realistic thermal hydraulic systems analysis code with multi-dimensional analysis capability. MARS achieves this objective by very tightly integrating the one dimensional RELAP5/MOD3 with the multi-dimensional COBRA-TF codes. The method of integration of the two codes is based on the dynamic link library techniques, and the system pressure equation matrices of both codes are implicitly integrated and solved simultaneously. In addition, the Equation-of-State (EOS) for the light water was unified by replacing the EOS of COBRA-TF by that of the RELAP5. This input manual provides a complete list of input required to run MARS. The manual is divided largely into two parts, namely, the one-dimensional part and the multi-dimensional part. The inputs for auxiliary parts such as minor edit requests and graph formatting inputs are shared by the two parts and as such mixed input is possible. The overall structure of the input is modeled on the structure of the RELAP5 and as such the layout of the manual is very similar to that of the RELAP. This similitude to RELAP5 input is intentional as this input scheme will allow minimum modification between the inputs of RELAP5 and MARS. MARS development team would like to express its appreciation to the RELAP5 Development Team and the USNRC for making this manual possible

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

    International Nuclear Information System (INIS)

    Hanawa, Satoshi; Iyoku, Tatsuo

    2001-08-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2001-03-01

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

  1. 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

  2. 3rd Semester and Master's Thesis Ideas

    DEFF Research Database (Denmark)

    Clausen, Johan

    The following pages contain a list of project ideas proposed by the scientific staff at the department of Civil Engineering, Aalborg University, and a number of companies. Most of the project ideas in this catalouge may form the basis for long and short candidate projects as well as regular 3rd...

  3. INTRA/Mod3.2. Manual and Code Description. Volume I - Physical Modelling

    International Nuclear Information System (INIS)

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

    1999-01-01

    The INTRA Manual consists of two volumes. Volume I of the manual is a thorough description of the code INTRA, the Physical modelling of INTRA and the ruling numerical methods and volume II, the User's Manual is an input description. This document, the Physical modelling of INTRA, contains code characteristics, integration methods and applications

  4. INTRA/Mod3.2. Manual and Code Description. Volume I - Physical Modelling

    Energy Technology Data Exchange (ETDEWEB)

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

    1999-01-01

    The INTRA Manual consists of two volumes. Volume I of the manual is a thorough description of the code INTRA, the Physical modelling of INTRA and the ruling numerical methods and volume II, the User`s Manual is an input description. This document, the Physical modelling of INTRA, contains code characteristics, integration methods and applications

  5. 3rd International Conference on Transcriptomics

    OpenAIRE

    John A Daniel

    2017-01-01

    Conference Series has been instrumental in conducting international Biochemistry meetings for seven years, and very excited to expand Europe, America and Asia Pacific continents. Previous meetings were held in major cities like Philadelphia, Orlando with success the meetings again scheduled in three continents. 3rd International Conference on Transcriptomics to be held during October 30 - November 01, 2017 at Bangkok, Thailand The Global Transcriptomics business sector to develop at a C...

  6. 3rd annual biomass energy systems conference

    Energy Technology Data Exchange (ETDEWEB)

    1979-10-01

    The main objectives of the 3rd Annual Biomass Energy Systems Conference were (1) to review the latest research findings in the clean fuels from biomass field, (2) to summarize the present engineering and economic status of Biomass Energy Systems, (3) to encourage interaction and information exchange among people working or interested in the field, and (4) to identify and discuss existing problems relating to ongoing research and explore opportunities for future research. Abstracts for each paper presented were edited separately. (DC)

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

    International Nuclear Information System (INIS)

    Watanabe, Norio; Kiyota, Mikio.

    1992-06-01

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

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

    International Nuclear Information System (INIS)

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

    2002-01-01

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

  9. MACSIS User's Manual and Code Description

    Energy Technology Data Exchange (ETDEWEB)

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

    2000-03-01

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

  10. 3rd MeTrApp Conference

    CERN Document Server

    Lovasz, Erwin-Christian; Hüsing, Mathias

    2015-01-01

    This volume deals with topics such as mechanism and machine design, biomechanics and medical engineering, gears, mechanical transmissions, mechatronics, computational and experimental methods, dynamics of mechanisms and machines, micromechanisms and microactuators, and history of mechanisms and transmissions. Following MeTrApp 2011 and 2013, held under the auspices of the IFToMM, these proceedings of the 3rd Conference on Mechanisms, Transmissions and Applications offer a platform for original research presentations for researchers, scientists, industry experts and students in the fields of mechanisms and transmissions with special emphasis on industrial applications in order to stimulate the exchange of new and innovative ideas.

  11. 3rd International Conference on Multimedia Technology

    CERN Document Server

    Yang, Jian; Jiao, Feng

    2014-01-01

    Proceedings of the 3rd International Conference on Multimedia Technology (ICMT2013) focuses on both the theory and applications of multimedia technology. The recent advances, new research findings and applications in the fields of theoretical, experimental and applied image & video processing and multimedia technology presented at the conference are brought together in this book. It will serve as a valuable reference for scientists and engineers working in multimedia and related fields. Prof. Aly A. Farag works at the University of Louisville, USA; Prof. Jian Yang works at Tsinghua University, China; Dr. Feng Jiao works at Nanjing University of Information Science & Technology, China.

  12. The cogeneration and small power production manual. 3rd edition

    International Nuclear Information System (INIS)

    Spiewak, S.A.

    1990-01-01

    This book is divided into six sections covering regulations, environmental issues, engineering, contract, financing, and taxes. The edition adds a comprehensive 80-page chapter outlining how to prepare for electric power shortages, including details on rate structure, tariff negotiation, contract-based rates, partial requirement service, supplementary, backup, and interruptible rates, and retail sale of electric power. The engineering section covers optimum cogeneration system design, operational considerations, and energy efficiency. Combustion turbines, diesel engines, gas engines, rotary engines, steam turbines, and electric generators are covered in detail

  13. Code manual for CONTAIN 2.0: A computer code for nuclear reactor containment analysis

    Energy Technology Data Exchange (ETDEWEB)

    Murata, K.K.; Williams, D.C.; Griffith, R.O.; Gido, R.G.; Tadios, E.L.; Davis, F.J.; Martinez, G.M.; Washington, K.E. [Sandia National Labs., Albuquerque, NM (United States); Tills, J. [J. Tills and Associates, Inc., Sandia Park, NM (United States)

    1997-12-01

    The CONTAIN 2.0 computer code is an integrated analysis tool used for predicting the physical conditions, chemical compositions, and distributions of radiological materials inside a containment building following the release of material from the primary system in a light-water reactor accident. It can also predict the source term to the environment. CONTAIN 2.0 is intended to replace the earlier CONTAIN 1.12, which was released in 1991. The purpose of this Code Manual is to provide full documentation of the features and models in CONTAIN 2.0. Besides complete descriptions of the models, this Code Manual provides a complete description of the input and output from the code. CONTAIN 2.0 is a highly flexible and modular code that can run problems that are either quite simple or highly complex. An important aspect of CONTAIN is that the interactions among thermal-hydraulic phenomena, aerosol behavior, and fission product behavior are taken into account. The code includes atmospheric models for steam/air thermodynamics, intercell flows, condensation/evaporation on structures and aerosols, aerosol behavior, and gas combustion. It also includes models for reactor cavity phenomena such as core-concrete interactions and coolant pool boiling. Heat conduction in structures, fission product decay and transport, radioactive decay heating, and the thermal-hydraulic and fission product decontamination effects of engineered safety features are also modeled. To the extent possible, the best available models for severe accident phenomena have been incorporated into CONTAIN, but it is intrinsic to the nature of accident analysis that significant uncertainty exists regarding numerous phenomena. In those cases, sensitivity studies can be performed with CONTAIN by means of user-specified input parameters. Thus, the code can be viewed as a tool designed to assist the knowledge reactor safety analyst in evaluating the consequences of specific modeling assumptions.

  14. Code manual for CONTAIN 2.0: A computer code for nuclear reactor containment analysis

    International Nuclear Information System (INIS)

    Murata, K.K.; Williams, D.C.; Griffith, R.O.; Gido, R.G.; Tadios, E.L.; Davis, F.J.; Martinez, G.M.; Washington, K.E.; Tills, J.

    1997-12-01

    The CONTAIN 2.0 computer code is an integrated analysis tool used for predicting the physical conditions, chemical compositions, and distributions of radiological materials inside a containment building following the release of material from the primary system in a light-water reactor accident. It can also predict the source term to the environment. CONTAIN 2.0 is intended to replace the earlier CONTAIN 1.12, which was released in 1991. The purpose of this Code Manual is to provide full documentation of the features and models in CONTAIN 2.0. Besides complete descriptions of the models, this Code Manual provides a complete description of the input and output from the code. CONTAIN 2.0 is a highly flexible and modular code that can run problems that are either quite simple or highly complex. An important aspect of CONTAIN is that the interactions among thermal-hydraulic phenomena, aerosol behavior, and fission product behavior are taken into account. The code includes atmospheric models for steam/air thermodynamics, intercell flows, condensation/evaporation on structures and aerosols, aerosol behavior, and gas combustion. It also includes models for reactor cavity phenomena such as core-concrete interactions and coolant pool boiling. Heat conduction in structures, fission product decay and transport, radioactive decay heating, and the thermal-hydraulic and fission product decontamination effects of engineered safety features are also modeled. To the extent possible, the best available models for severe accident phenomena have been incorporated into CONTAIN, but it is intrinsic to the nature of accident analysis that significant uncertainty exists regarding numerous phenomena. In those cases, sensitivity studies can be performed with CONTAIN by means of user-specified input parameters. Thus, the code can be viewed as a tool designed to assist the knowledge reactor safety analyst in evaluating the consequences of specific modeling assumptions

  15. 3rd International Conference Nanotechnology and Nanomaterials

    CERN Document Server

    Yatsenko, Leonid

    2016-01-01

    This book presents some of the latest achievements in nanotechnology and nanomaterials from leading researchers in Ukraine, Europe, and beyond. It features contributions from participants in the 3rd International Science and Practice Conference Nanotechnology and Nanomaterials (NANO2015) held in Lviv, Ukraine on August 26-30, 2015. The International Conference was organized jointly by the Institute of Physics of the National Academy of Sciences of Ukraine, University of Tartu (Estonia), Ivan Franko National University of Lviv (Ukraine), University of Turin (Italy), Pierre and Marie Curie University (France), and European Profiles A.E. (Greece). Internationally recognized experts from a wide range of universities and research institutions share their knowledge and key results on topics ranging from nanooptics, nanoplasmonics, and interface studies to energy storage and biomedical applications. Presents cutting-edge advances in nanocomposites and carbon and silicon-based nanomaterials for a wide range of engine...

  16. Performance of automated and manual coding systems for occupational data: a case study of historical records.

    Science.gov (United States)

    Patel, Mehul D; Rose, Kathryn M; Owens, Cindy R; Bang, Heejung; Kaufman, Jay S

    2012-03-01

    Occupational data are a common source of workplace exposure and socioeconomic information in epidemiologic research. We compared the performance of two occupation coding methods, an automated software and a manual coder, using occupation and industry titles from U.S. historical records. We collected parental occupational data from 1920-40s birth certificates, Census records, and city directories on 3,135 deceased individuals in the Atherosclerosis Risk in Communities (ARIC) study. Unique occupation-industry narratives were assigned codes by a manual coder and the Standardized Occupation and Industry Coding software program. We calculated agreement between coding methods of classification into major Census occupational groups. Automated coding software assigned codes to 71% of occupations and 76% of industries. Of this subset coded by software, 73% of occupation codes and 69% of industry codes matched between automated and manual coding. For major occupational groups, agreement improved to 89% (kappa = 0.86). Automated occupational coding is a cost-efficient alternative to manual coding. However, some manual coding is required to code incomplete information. We found substantial variability between coders in the assignment of occupations although not as large for major groups.

  17. 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

  18. Tokamak plasma power balance calculation code (TPC code) outline and operation manual

    International Nuclear Information System (INIS)

    Fujieda, Hirobumi; Murakami, Yoshiki; Sugihara, Masayoshi.

    1992-11-01

    This report is a detailed description on the TPC code, that calculates the power balance of a tokamak plasma according to the ITER guidelines. The TPC code works on a personal computer (Macintosh or J-3100/ IBM-PC). Using input data such as the plasma shape, toroidal magnetic field, plasma current, electron temperature, electron density, impurities and heating power, TPC code can determine the operation point of the fusion reactor (Ion temperature is assumed to be equal to the electron temperature). Supplied flux (Volt · sec) and burn time are also estimated by coil design parameters. Calculated energy confinement time is compared with various L-mode scaling laws and the confinement enhancement factor (H-factor) is evaluated. Divertor heat load is predicted by using simple scaling models (constant-χ, Bohm-type-χ and JT-60U empirical scaling models). Frequently used data can be stored in a 'device file' and used as the default values. TPC code can generate 2-D mesh data and the POPCON plot is drawn by a contour line plotting program (CONPLT). The operation manual about CONPLT code is also described. (author)

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

    International Nuclear Information System (INIS)

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

    1999-04-01

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

  20. SSC-K code user's manual

    Energy Technology Data Exchange (ETDEWEB)

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

    2000-07-01

    The Supper System Code of KAERI (SSC-K) is a best-estimate system code for analyzing a variety of off-normal or accidents in the heat transport system of a pool type LMR design. It is being developed at Korea Atomic Energy Research Inititution (KAERI) on the basis of SSC-L, originally developed at BNL to analyze loop-type LMR transients. SSC-K can handle both designs of loop and pool type LMRs. SSC-K contains detailed mechanistic models of transient thermal, hydraulic, neutronic, and mechanical phenomena to describe the response of the reactor core, coolant, fuel elements, and structures to accident conditions. This report provides an overview of recent model developmentsvfor the SSC-K computer code, focusing on phenomenological model descriptions for new thermal, hydraulic, neutronic, and mechnaical modules. A comprehensive description of the models for pool-type reactor is given in Chapters 2 and 3; the steady-state plant characterization, prior to the initiation of transient is described in Chapter 2 and their transient counterparts are discussed in Chapter 3. In Chapter 4, a discussion on the intermediate heat exchanger (IHX) is presented. The IHX model of SSC-K is similar to that used in the SSC-L, except for some changes required for the pool-type configuration of reactor vessel. In Chapter 5, an electromagnetic (EM) pump is modeled as a component. There are two pump choices available in SSC-K; a centrifugal pump which was originally imbedded into the SSC-L, and an EM pump which was introduced for the KALIMER design. In Chapter 6, a model of passive safety decay heat removal system(PSDRS) is discussed, which removes decay heat through the reactor and containment vessel walls to the ambient air heat sink. In Chapter 7, models for various reactivity feedback effects are discussed. Reactivity effects of importance in fast reactor include the Doppler effect, effects of sodium density changes, effects of dimensional changes in core geometry. Finally in Chapter 8

  1. BACODINE/3rd Interplanetary Network burst localization

    International Nuclear Information System (INIS)

    Hurley, K.; Barthelmy, S.; Butterworth, P.; Cline, T.; Sommer, M.; Boer, M.; Niel, M.; Kouveliotou, C.; Fishman, G.; Meegan, C.

    1996-01-01

    Even with only two widely separated spacecraft (Ulysses and GRO), 3rd Interplanetary Network (IPN) localizations can reduce the areas of BATSE error circles by two orders of magnitude. Therefore it is useful to disseminate them as quickly as possible following BATSE bursts. We have implemented a system which transmits the light curves of BACODINE/BATSE bursts directly by e-mail to UC Berkeley immediately after detection. An automatic e-mail parser at Berkeley watches for these notices, determines the Ulysses crossing time window, and initiates a search for the burst data on the JPL computer as they are received. In ideal cases, it is possible to retrieve the Ulysses data within a few hours of a burst, generate an annulus of arrival directions, and e-mail it out to the astronomical community by local nightfall. Human operators remain in this loop, but we are developing a fully automated routine which should remove them, at least for intense events, and reduce turn-around times to an absolute minimum. We explain the current operations, the data types used, and the speed/accuracy tradeoffs

  2. Energy Code Enforcement Training Manual : Covering the Washington State Energy Code and the Ventilation and Indoor Air Quality Code.

    Energy Technology Data Exchange (ETDEWEB)

    Washington State Energy Code Program

    1992-05-01

    This manual is designed to provide building department personnel with specific inspection and plan review skills and information on provisions of the 1991 edition of the Washington State Energy Code (WSEC). It also provides information on provisions of the new stand-alone Ventilation and Indoor Air Quality (VIAQ) Code.The intent of the WSEC is to reduce the amount of energy used by requiring energy-efficient construction. Such conservation reduces energy requirements, and, as a result, reduces the use of finite resources, such as gas or oil. Lowering energy demand helps everyone by keeping electricity costs down. (It is less expensive to use existing electrical capacity efficiently than it is to develop new and additional capacity needed to heat or cool inefficient buildings.) The new VIAQ Code (effective July, 1991) is a natural companion to the energy code. Whether energy-efficient or not, an homes have potential indoor air quality problems. Studies have shown that indoor air is often more polluted than outdoor air. The VIAQ Code provides a means of exchanging stale air for fresh, without compromising energy savings, by setting standards for a controlled ventilation system. It also offers requirements meant to prevent indoor air pollution from building products or radon.

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

    International Nuclear Information System (INIS)

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

    1979-02-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1979-02-01

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

  5. The DAΦNE 3RD harmonic cavity

    International Nuclear Information System (INIS)

    Alesini, D.; Boni, R.; Clozza, A.; Gallo, A.; Guiducci, S.; Marcellini, F.; Migliorati, M.; Palumbo, L.; Pellegrino, L.; Sgamma, F.; Zobov, M.

    2001-01-01

    The installation of a passive 3rd harmonic cavity in both the e + and e - rings of the Frascati Φ-factory DAΦNE has been decided in order to improve the Touschek lifetime by increasing the bunch length. The implications of the RF harmonic system on the beam dynamics, in particular those related to the gap in the bunch filling pattern, have been carefully studied by means of analytical and numerical tools. A single-cell cavity incorporating a ferrite ring for the HOM damping has been designed through the extensive use of MAFIA and HFSS simulation codes. One cavity prototype has been built and extensively bench tested, while the fabrication of the two final cavities is almost completed. A description of the design and construction activities, and a set of experimental measurements are reported in this paper

  6. Electronic manual of the nuclear characteristics analysis code-set for FBR

    International Nuclear Information System (INIS)

    Makino, Tohru

    2001-03-01

    Reactor Physics Gr., System Engineering Technology Division, O-arai Engineering Center has consolidated the nuclear design database to improve analytical methods and prediction accuracy for large fast breeder cores such as demonstration or commercial FBRs from the previous research. The up-to-date information about usage of the nuclear characteristics analysis code-set was compiled as a part of the improvement of basic design data base for FBR core. The outlines of the electronic manual are as follows; (1) The electronic manual includes explanations of following codes: JOINT : Code Interface Program. SLAROM, CASUP : Effective Cross Section Calculation Code. CITATION-FBR : Diffusion Analysis Code. PERKY : Perturbative Diffusion Analysis Code. SNPERT, SNPERT-3D : Perturbative Transport Analysis Code. SAGEP, SAGEP-3D : Sensitivity Coefficient Calculation Code. NSHEX : Transport Analysis Code using Nodal Method. ABLE : Cross Section Adjustment Calculation Code. ACCEPT : Predicting Accuracy Evaluation Code. (2) The electronic manual is described using HTML file format and PDF file for easy maintenance, updating and for easy referring through JNC Intranet. User can refer manual pages by usual Web browser software without any special setup. (3) Many of manual pages include link-tags to jump to related pages. String search is available in both HTML and PDF documents. (4) User can download source code, sample input data and shell script files to carry out each analysis from download page of each code (JNC inside only). (5) Usage of the electronic manual and maintenance/updating process are described in this report and it makes possible to enroll new code or new information in the electronic manual. Since the information has been taken into account about modifications and error fixings, added to each code after the last consolidation in 1994, the electronic manual would cover most recent status of the nuclear characteristics analysis code-set. One of other advantages of use

  7. User's manual of the REFLA-1D/MODE4 reflood thermo-hydrodynamic analysis code

    International Nuclear Information System (INIS)

    Hojo, Tsuneyuki; Iguchi, Tadashi; Okubo, Tsutomu; Murao, Yoshio; Sugimoto, Jun.

    1986-01-01

    REFLA-1D/MODE4 code has been developed by incorporating local power effect model and fuel temperature profile effect model into REFLA-1D/MODE3 code. This code can calculate the temperature transient of local rod by considering radial power profile effect in core and simulate the thermal characteristics of the nuclear fuel rod. This manual describes the outline of incorporated models, modification of the code with incorporating models and provides application information required to utilize the code. (author)

  8. Users' manual for the FTDRAW (Fault Tree Draw) code

    International Nuclear Information System (INIS)

    Oikawa, Tetsukuni; Hikawa, Michihiro; Tanabe, Syuichi; Nakamura, Norihiro

    1985-02-01

    This report provides the information needed to use the FTDRAW (Fault Tree Draw) code, which is designed for drawing a fault tree. The FTDRAW code has several optional functions, such as the overview of a fault tree output, fault tree output in English description, fault tree output in Japanese description and summary tree output. Inputs for the FTDRAW code are component failure rate information and gate information which are filed out by a execution of the FTA-J (Fault Tree Analysis-JAERI) code system and option control data. Using the FTDRAW code, we can get drawings of fault trees which is easy to see, efficiently. (author)

  9. The TESS [Tandem Experiment Simulation Studies] computer code user's manual

    International Nuclear Information System (INIS)

    Procassini, R.J.

    1990-01-01

    TESS (Tandem Experiment Simulation Studies) is a one-dimensional, bounded particle-in-cell (PIC) simulation code designed to investigate the confinement and transport of plasma in a magnetic mirror device, including tandem mirror configurations. Mirror plasmas may be modeled in a system which includes an applied magnetic field and/or a self-consistent or applied electrostatic potential. The PIC code TESS is similar to the PIC code DIPSI (Direct Implicit Plasma Surface Interactions) which is designed to study plasma transport to and interaction with a solid surface. The codes TESS and DIPSI are direct descendants of the PIC code ES1 that was created by A. B. Langdon. This document provides the user with a brief description of the methods used in the code and a tutorial on the use of the code. 10 refs., 2 tabs

  10. 18 CFR 410.1 - Basin regulations-Water Code and Administrative Manual-Part III Water Quality Regulations.

    Science.gov (United States)

    2010-04-01

    ... Code and Administrative Manual-Part III Water Quality Regulations. 410.1 Section 410.1 Conservation of... CODE AND ADMINISTRATIVE MANUAL-PART III WATER QUALITY REGULATIONS § 410.1 Basin regulations—Water Code and Administrative Manual—Part III Water Quality Regulations. (a) The Water Code of the Delaware River...

  11. User manual for the KfK code PCROSS

    International Nuclear Information System (INIS)

    Ravndal, S.; Oblozinsky, P.; Kelzenberg, S.; Cierjacks, S.

    1991-08-01

    The PCROSS code calculates the so-called 'pseudo' cross sections for sequential (x,n) reactions and merges them together with 'collapsed' cross sections for neutron induced reactions into one file of cross sections. The file is tailored to provide an input for the FISPACT inventory code that calculates the activation and related radiological quantities of material irradiated in a neutron flux. The present report describes the structure of the KfK code PCROSS, outlines the role of subroutines, and provides necessary information for a practical user of the code. (orig.) [de

  12. A Manual for Coding Teacher's Enacted Interpersonal Understanding.

    Science.gov (United States)

    DeVries, Rheta; And Others

    This manual was developed in order to study the sociomoral atmospheres of three kindergarten classrooms. Previous research by Robert Selman et al. conceptualized developmental levels of interpersonal understanding in terms of two types of experiences: negotiation, where the developmental goal is identity separate from others; and shared…

  13. BOOK REVIEW: Modern Physics, 3rd edn

    Science.gov (United States)

    Lovett, David

    1999-09-01

    an attractive chapter it is a pity that it is not printed within the book. Although viewing the chapter on the Web gives the benefit of full colour, it is not easy to read the textual information off the screen. Within the printed material, there are good diagrams with the addition of a single colour, burgundy, a colour that is wasted on those of us who are red-green colour-blind! Each chapter is provided with an impressive number of graded problems (it is not easy to provide such a comprehensive range of problems at this level) and numerical answers are given in the back for every third problem. There is a student solution manual available for these problems and a complete instructor's solution manual has also been produced. It is therefore a useful book for both students and lecturers.

  14. Input/output manual of light water reactor fuel performance code FEMAXI-7 and its related codes

    Energy Technology Data Exchange (ETDEWEB)

    Suzuki, Motoe; Udagawa, Yutaka; Nagase, Fumihisa [Japan Atomic Energy Agency, Nuclear Safety Research Center, Tokai, Ibaraki (Japan); Saitou, Hiroaki [ITOCHU Techno-Solutions Corp., Tokyo (Japan)

    2012-07-15

    A light water reactor fuel analysis code FEMAXI-7 has been developed for the purpose of analyzing the fuel behavior in normal conditions and in anticipated transient conditions. Numerous functional improvements and extensions have been incorporated in FEMAXI-7, which has been fully disclosed in the code model description published recently as JAEA-Data/Code 2010-035. The present manual, which is the counterpart of this description, gives detailed explanations of operation method of FEMAXI-7 code and its related codes, methods of Input/Output, methods of source code modification, features of subroutine modules, and internal variables in a specific manner in order to facilitate users to perform a fuel analysis with FEMAXI-7. This report includes some descriptions which are modified from the original contents of JAEA-Data/Code 2010-035. A CD-ROM is attached as an appendix. (author)

  15. Input/output manual of light water reactor fuel performance code FEMAXI-7 and its related codes

    International Nuclear Information System (INIS)

    Suzuki, Motoe; Udagawa, Yutaka; Nagase, Fumihisa; Saitou, Hiroaki

    2012-07-01

    A light water reactor fuel analysis code FEMAXI-7 has been developed for the purpose of analyzing the fuel behavior in normal conditions and in anticipated transient conditions. Numerous functional improvements and extensions have been incorporated in FEMAXI-7, which has been fully disclosed in the code model description published recently as JAEA-Data/Code 2010-035. The present manual, which is the counterpart of this description, gives detailed explanations of operation method of FEMAXI-7 code and its related codes, methods of Input/Output, methods of source code modification, features of subroutine modules, and internal variables in a specific manner in order to facilitate users to perform a fuel analysis with FEMAXI-7. This report includes some descriptions which are modified from the original contents of JAEA-Data/Code 2010-035. A CD-ROM is attached as an appendix. (author)

  16. VIPRE-01: a thermal-hydraulic code for reactor cores. Volume 3: programmer's manual (Revision 2)

    International Nuclear Information System (INIS)

    Stewart, C.W.; Koontz, A.S.; Cuta, J.M.; Montgomery, S.D.

    1985-07-01

    The VIPRE thermal-hydraulic computer code for PWR and BWR core analysis has undergone a detailed design review by a committee of experts. A new version of the code, incorporating the committee's recommendations, has been submitted for NRC review and issuance of a safety evaluation report. The changes in the programmers's manual are given

  17. The Gift Code User Manual. Volume I. Introduction and Input Requirements

    Science.gov (United States)

    1975-07-01

    REPORT & PERIOD COVERED ‘TII~ GIFT CODE USER MANUAL; VOLUME 1. INTRODUCTION AND INPUT REQUIREMENTS FINAL 6. PERFORMING ORG. REPORT NUMBER ?. AuTHOR(#) 8...reverua side if neceaeary and identify by block number] (k St) The GIFT code is a FORTRANcomputerprogram. The basic input to the GIFT ode is data called

  18. Developing Product Lines with 3rd-party components

    NARCIS (Netherlands)

    De Jonge, M.

    2007-01-01

    The trends toward product line development and toward adopting more 3rd-party software are hard to combine. The reason is that productlines demand fine control over the software (e.g., for diversity management), while 3rd-party software (almost by definition) provides only little or no control. A

  19. BWR plant dynamic analysis code BWRDYN user's manual

    International Nuclear Information System (INIS)

    Yokobayashi, Masao; Yoshida, Kazuo; Fujiki, Kazuo

    1989-06-01

    Computer code BWRDYN has been developed for thermal-hydraulic analysis of a BWR plant. It can analyze the various types of transient caused by not only small but also large disturbances such as operating mode changes and/or system malfunctions. The verification of main analytical models of the BWRDYN code has been performed with measured data of actual BWR plant. Furthermore, the installation of BOP (Balance of Plant) model has made it possible to analyze the effect of BOP on reactor system. This report describes on analytical models and instructions for user of the BWRDYN code. (author)

  20. Reference manual for the KfK code PCROSS

    International Nuclear Information System (INIS)

    Ravndal, S.; Oblozinsky, P.; Kelzenberg, S.; Cierjacks, S.

    1991-12-01

    The PCROSS code calculates the so-called 'pseudo' cross sections for sequential (x,n) reactions and merges them together with 'effective' cross section for neutron induced reactions into one file of 'collapsed' cross sections. The file is tailored to provide an input for the FISPACT inventory code that calculates the activation and related radiological quantities of material irradiated in given neutron fields. The report summarizes calculational procedure and provides the reader with essential technical details of the code PCROSS (version 1.0) such as description of parameters, common blocks and subroutines. (orig.) [de

  1. User manual for the probabilistic fuel performance code FRP

    International Nuclear Information System (INIS)

    Friis Jensen, J.; Misfeldt, I.

    1980-10-01

    This report describes the use of the probabilistic fuel performance code FRP. Detailed description of both input to and output from the program are given. The use of the program is illustrated by an example. (author)

  2. The computer code EURDYN-1M (release 2). User's manual

    International Nuclear Information System (INIS)

    1982-01-01

    EURDYN-1M is a finite element computer code developed at J.R.C. Ispra to compute the response of two-dimensional coupled fluid-structure configurations to transient dynamic loading for reactor safety studies. This report gives instructions for preparing input data to EURDYN-1M, release 2, and describes a test problem in order to illustrate both the input and the output of the code

  3. Manual for IRS Coding. Joint IAEA/NEA International Reporting System for Operating Experience

    International Nuclear Information System (INIS)

    2011-01-01

    The International Reporting System for Operating Experience (IRS) is jointly operated by the International Atomic Energy Agency (IAEA) and the Nuclear Energy Agency of the Organisation for Economic Co-operation and Development (OECD/NEA). In early 2010, the IAEA and OECD/NEA jointly issued the IRS Guidelines, which described the reporting system and process and gave users the necessary elements to enable them to produce IRS reports to a high standard of quality while retaining the effectiveness of the system expected by all Member States operating nuclear power plants. The purpose of the present Manual for IRS Coding is to provide supplementary guidance specifically on the coding element of IRS reports to ensure uniform coding of events that are reported through IRS. This Coding Manual does not supersede the IRS Guidelines, but rather, supports users and preparers in achieving a consistent and high level of quality in their IRS reports. Consistency and high quality in the IRS reports allow stakeholders to search and retrieve specific event information with ease. In addition, well-structured reports also enhance the efficient management of the IRS database. This Coding Manual will give specific guidance on the application of each section of the IRS codes, with examples where necessary, of when and how these codes are to be applied. As this reporting system is owned by the Member States, this manual has been developed and approved by the IRS National Coordinators with the assistance of the IAEA and NEA secretariats

  4. Input/output manual of light water reactor fuel analysis code FEMAXI-7 and its related codes

    Energy Technology Data Exchange (ETDEWEB)

    Suzuki, Motoe; Udagawa, Yutaka; Nagase, Fumihisa [Japan Atomic Energy Agency, Nuclear Safety Research Center, Tokai, Ibaraki (Japan); Saitou, Hiroaki [ITOCHU Techno-Solutions Corporation, Tokyo (Japan)

    2013-10-15

    A light water reactor fuel analysis code FEMAXI-7 has been developed, as an extended version from the former version FEMAXI-6, for the purpose of analyzing the fuel behavior in normal conditions and in anticipated transient conditions. Numerous functional improvements and extensions have been incorporated in FEMAXI-7, which are fully disclosed in the code model description published in the form of another JAEA-Data/Code report. The present manual, which is the very counterpart of this description document, gives detailed explanations of files and operation method of FEMAXI-7 code and its related codes, methods of input/output, sample Input/Output, methods of source code modification, subroutine structure, and internal variables in a specific manner in order to facilitate users to perform fuel analysis by FEMAXI-7. (author)

  5. Input/output manual of light water reactor fuel analysis code FEMAXI-7 and its related codes

    International Nuclear Information System (INIS)

    Suzuki, Motoe; Udagawa, Yutaka; Nagase, Fumihisa; Saitou, Hiroaki

    2013-10-01

    A light water reactor fuel analysis code FEMAXI-7 has been developed, as an extended version from the former version FEMAXI-6, for the purpose of analyzing the fuel behavior in normal conditions and in anticipated transient conditions. Numerous functional improvements and extensions have been incorporated in FEMAXI-7, which are fully disclosed in the code model description published in the form of another JAEA-Data/Code report. The present manual, which is the very counterpart of this description document, gives detailed explanations of files and operation method of FEMAXI-7 code and its related codes, methods of input/output, sample Input/Output, methods of source code modification, subroutine structure, and internal variables in a specific manner in order to facilitate users to perform fuel analysis by FEMAXI-7. (author)

  6. NASA Lewis steady-state heat pipe code users manual

    International Nuclear Information System (INIS)

    Tower, L.K.

    1992-06-01

    The NASA Lewis heat pipe code has been developed to predict the performance of heat pipes in the steady state. The code can be used as a design tool on a personal computer or, with a suitable calling routine, as a subroutine for a mainframe radiator code. A variety of wick structures, including a user input option, can be used. Heat pipes with multiple evaporators, condensers, and adiabatic sections in series and with wick structures that differ among sections can be modeled. Several working fluids can be chosen, including potassium, sodium, and lithium, for which the monomer-dimer equilibrium is considered. The code incorporates a vapor flow algorithm that treats compressibility and axially varying heat input. This code facilitates the determination of heat pipe operating temperatures and heat pipe limits that may be encountered at the specified heat input and environment temperature. Data are input to the computer through a user-interactive input subroutine. Output, such as liquid and vapor pressures and temperatures, is printed at equally spaced axial positions along the pipe as determined by the user

  7. Code manual for MACCS2: Volume 1, user's guide

    International Nuclear Information System (INIS)

    Chanin, D.I.; Young, M.L.

    1997-03-01

    This report describes the use of the MACCS2 code. The document is primarily a user's guide, though some model description information is included. MACCS2 represents a major enhancement of its predecessor MACCS, the MELCOR Accident Consequence Code System. MACCS, distributed by government code centers since 1990, was developed to evaluate the impacts of severe accidents at nuclear power plants on the surrounding public. The principal phenomena considered are atmospheric transport and deposition under time-variant meteorology, short- and long-term mitigative actions and exposure pathways, deterministic and stochastic health effects, and economic costs. No other U.S. code that is publicly available at present offers all these capabilities. MACCS2 was developed as a general-purpose tool applicable to diverse reactor and nonreactor facilities licensed by the Nuclear Regulatory Commission or operated by the Department of Energy or the Department of Defense. The MACCS2 package includes three primary enhancements: (1) a more flexible emergency-response model, (2) an expanded library of radionuclides, and (3) a semidynamic food-chain model. Other improvements are in the areas of phenomenological modeling and new output options. Initial installation of the code, written in FORTRAN 77, requires a 486 or higher IBM-compatible PC with 8 MB of RAM

  8. SCDAP/RELAP5/MOD2 code manual

    International Nuclear Information System (INIS)

    Allison, C.M.; Johnson, E.C.

    1989-09-01

    The SCDAP/RELAP5 code has been developed for best-estimate transient simulation of light water reactor coolant systems during a severe accident. The code models the coupled behavior of the reactor coolant system, the core, and the fission products and aerosols in the system during a severe accident transient as well as large and small break loss-of-coolant accidents, operational transients such as anticipated transient without SCRAM, loss of offsite power, loss of feedwater, and loss of flow. A generic modeling approach is used that permits as much of a particular system to be modeled as necessary. Control system and secondary system components are included to permit modeling of plant controls, turbines, condensers, and secondary feedwater conditioning systems. The modeling theory and associated numerical schemes are documented in Volumes I and II to acquaint the user with the modeling base and thus aid in effective use of the code

  9. User's manual for the radioactive decay and accumulation code RADAC

    International Nuclear Information System (INIS)

    Salmon, R.; Loghry, S.L.; Ashline, R.C.

    1995-11-01

    The RADAC computer code calculates radioactive decay and accumulation of decayed products using an algorithm based on the direct use of the Bateman equations and referred to here as the yield factor method. This report explains the yield factor method, gives an overview of the various modules in the RADAC code system, and describes the decay and accumulation code in detail. The RADAC code has capacity for two waste types and can accommodate up to 60 years of annual waste inputs. Decay times as high as 1 million years can be calculated. The user supplies the undecayed composition and radioactivity of the waste placed in storage each year. The code calculates the decayed composition, radioactivity, and thermal power of the accumulated waste at the end of each year and gives the results in terms of grams and curies of individual radionuclides. Calculations can be made for up to 19 waste storage sites in a single run. For each site and each waste type, calculations can be made by 1-year steps up to 60 years, by 10-year steps to 160 years, and by 6 discrete steps to 1 million years. Detailed outputs can be printed for each waste site and each time step by individual radionuclides. Summarized outputs are also available. Excluding data-preparation time, RADAC requires about 2 min to run 19 waste sites with two types of transuranic waste at each site, using a 486 DX computer with a clock speed of 33 MHz. Because RADAC uses a preselected set of decay times and does not make in-reactor calculations, it should not be viewed as a substitute for ORIGEN2. RADAC is intended for use in applications in which accumulations at the decay times provided by the code are sufficient for the user's purposes

  10. ELCOS: the PSI code system for LWR core analysis. Part II: user's manual for the fuel assembly code BOXER

    International Nuclear Information System (INIS)

    Paratte, J.M.; Grimm, P.; Hollard, J.M.

    1996-02-01

    ELCOS is a flexible code system for the stationary simulation of light water reactor cores. It consists of the four computer codes ETOBOX, BOXER, CORCOD and SILWER. The user's manual of the second one is presented here. BOXER calculates the neutronics in cartesian geometry. The code can roughly be divided into four stages: - organisation: choice of the modules, file manipulations, reading and checking of input data, - fine group fluxes and condensation: one-dimensional calculation of fluxes and computation of the group constants of homogeneous materials and cells, - two-dimensional calculations: geometrically detailed simulation of the configuration in few energy groups, - burnup: evolution of the nuclide densities as a function of time. This manual shows all input commands which can be used while running the different modules of BOXER. (author) figs., tabs., refs

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

    International Nuclear Information System (INIS)

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

    1977-02-01

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

  12. User's manual for the FLORA equilibrium and stability code

    International Nuclear Information System (INIS)

    Freis, R.P.; Cohen, B.I.

    1985-01-01

    This document provides a user's guide to the content and use of the two-dimensional axisymmetric equilibrium and stability code FLORA. FLORA addresses the low-frequency MHD stability of long-thin axisymmetric tandem mirror systems with finite pressure and finite-larmor-radius effects. FLORA solves an initial-value problem for interchange, rotational, and ballooning stability

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

    Science.gov (United States)

    Wright, William B.

    1999-01-01

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

  14. Reference manual for the POISSON/SUPERFISH Group of Codes

    Energy Technology Data Exchange (ETDEWEB)

    1987-01-01

    The POISSON/SUPERFISH Group codes were set up to solve two separate problems: the design of magnets and the design of rf cavities in a two-dimensional geometry. The first stage of either problem is to describe the layout of the magnet or cavity in a way that can be used as input to solve the generalized Poisson equation for magnets or the Helmholtz equations for cavities. The computer codes require that the problems be discretized by replacing the differentials (dx,dy) by finite differences ({delta}X,{delta}Y). Instead of defining the function everywhere in a plane, the function is defined only at a finite number of points on a mesh in the plane.

  15. Colloid transport code-nuclear user`s manual

    Energy Technology Data Exchange (ETDEWEB)

    Jain, R. [New Mexico Univ., Albuquerque, NM (United States)

    1992-04-03

    This report describes the CTCN computer code, designed to solve the equations of transient colloidal transport of radionuclides in porous and fractured media. This Fortran 77 package solves systems of coupled nonlinear differential equations with a wide range of boundary conditions. The package uses the Method of Lines technique with a special section which forms finite-difference discretizations in up to four spatial dimensions to automatically convert the system into a set of ordinary differential equations. The CTCN code then solves these equations using a robust, efficient ODE solver. Thus CTCN can be used to solve population balance equations along with the usual transport equations to model colloid transport processes or as a general problem solver to treat up to four-dimensional differential systems.

  16. SCDAP/RELAP5/MOD2 code manual

    International Nuclear Information System (INIS)

    Allison, C.M.; Johnson, E.C.

    1989-09-01

    The SCDAP/RELAP5 code has been developed for best-estimate transient simulation of light water reactor coolant systems during a severe accident. The code models the coupled behavior of the reactor coolant system, the core, and the fission products and aerosols in the system during a severe accident transient as well as large and small break loss-of-coolant accidents, operational transients such as anticipated transient without SCRAM, loss of offsite power, loss of feedwater, and loss of flow. A generic modeling approach is used that permits as much of a particular system to be modeled as necessary. Control system and secondary system components are included to permit modeling of plant controls, turbines, condensers, and secondary feedwater conditioning systems. The modeling theory and associated numerical schemes are documented in Volumes I and in this document, Volume II, to acquaint the user with the modeling base and thus aid in effective use of the code. 135 refs., 48 figs., 8 tabs

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

    International Nuclear Information System (INIS)

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

    2005-01-01

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

  18. Consistency and accuracy of diagnostic cancer codes generated by automated registration: comparison with manual registration

    Directory of Open Access Journals (Sweden)

    Codazzi Tiziana

    2006-09-01

    Full Text Available Abstract Background Automated procedures are increasingly used in cancer registration, and it is important that the data produced are systematically checked for consistency and accuracy. We evaluated an automated procedure for cancer registration adopted by the Lombardy Cancer Registry in 1997, comparing automatically-generated diagnostic codes with those produced manually over one year (1997. Methods The automatically generated cancer cases were produced by Open Registry algorithms. For manual registration, trained staff consulted clinical records, pathology reports and death certificates. The social security code, present and checked in both databases in all cases, was used to match the files in the automatic and manual databases. The cancer cases generated by the two methods were compared by manual revision. Results The automated procedure generated 5027 cases: 2959 (59% were accepted automatically and 2068 (41% were flagged for manual checking. Among the cases accepted automatically, discrepancies in data items (surname, first name, sex and date of birth constituted 8.5% of cases, and discrepancies in the first three digits of the ICD-9 code constituted 1.6%. Among flagged cases, cancers of female genital tract, hematopoietic system, metastatic and ill-defined sites, and oropharynx predominated. The usual reasons were use of specific vs. generic codes, presence of multiple primaries, and use of extranodal vs. nodal codes for lymphomas. The percentage of automatically accepted cases ranged from 83% for breast and thyroid cancers to 13% for metastatic and ill-defined cancer sites. Conclusion Since 59% of cases were accepted automatically and contained relatively few, mostly trivial discrepancies, the automatic procedure is efficient for routine case generation effectively cutting the workload required for routine case checking by this amount. Among cases not accepted automatically, discrepancies were mainly due to variations in coding practice.

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

    Energy Technology Data Exchange (ETDEWEB)

    Ahnert, C

    1979-07-01

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

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

    International Nuclear Information System (INIS)

    Ahnert, C.

    1979-01-01

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

  1. The computer code Eurdyn - 1 M. (Release 1) Part 2: User's Manual

    International Nuclear Information System (INIS)

    Donea, J.; Giuliani, S.

    1979-01-01

    This report is the user's manual for the computer code Eurdyn-1 M developed at the J.R.C. Ispra for use in containment and fuel subassembly analyses for fast reactor safety studies. The input data are defined and a test problem is presented to illustrate both the input and the output of results

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

    International Nuclear Information System (INIS)

    Anhert, C.

    1979-01-01

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

  3. User's manual for BINIAC: A computer code to translate APET bins

    International Nuclear Information System (INIS)

    Gough, S.T.

    1994-03-01

    This report serves as the user's manual for the FORTRAN code BINIAC. BINIAC is a utility code designed to format the output from the Defense Waste Processing Facility (DWPF) Accident Progression Event Tree (APET) methodology. BINIAC inputs the accident progression bins from the APET methodology, converts the frequency from occurrences per hour to occurrences per year, sorts the progression bins, and converts the individual dimension character codes into facility attributes. Without the use of BINIAC, this process would be done manually at great time expense. BINIAC was written under the quality assurance control of IQ34 QAP IV-1, revision 0, section 4.1.4. Configuration control is established through the use of a proprietor and a cognizant users list

  4. User's manual for the Heat Pipe Space Radiator design and analysis Code (HEPSPARC)

    Science.gov (United States)

    Hainley, Donald C.

    1991-01-01

    A heat pipe space radiatior code (HEPSPARC), was written for the NASA Lewis Research Center and is used for the design and analysis of a radiator that is constructed from a pumped fluid loop that transfers heat to the evaporative section of heat pipes. This manual is designed to familiarize the user with this new code and to serve as a reference for its use. This manual documents the completed work and is intended to be the first step towards verification of the HEPSPARC code. Details are furnished to provide a description of all the requirements and variables used in the design and analysis of a combined pumped loop/heat pipe radiator system. A description of the subroutines used in the program is furnished for those interested in understanding its detailed workings.

  5. The CAIN computer code for the generation of MABEL input data sets: a user's manual

    International Nuclear Information System (INIS)

    Tilley, D.R.

    1983-03-01

    CAIN is an interactive FORTRAN computer code designed to overcome the substantial effort involved in manually creating the thermal-hydraulics input data required by MABEL-2. CAIN achieves this by processing output from either of the whole-core codes, RELAP or TRAC, interpolating where necessary, and by scanning RELAP/TRAC output in order to generate additional information. This user's manual describes the actions required in order to create RELAP/TRAC data sets from magnetic tape, to create the other input data sets required by CAIN, and to operate the interactive command procedure for the execution of CAIN. In addition, the CAIN code is described in detail. This programme of work is part of the Nuclear Installations Inspectorate (NII)'s contribution to the United Kingdom Atomic Energy Authority's independent safety assessment of pressurized water reactors. (author)

  6. Impressions from the 3rd Nordcode Seminar & Workshop

    DEFF Research Database (Denmark)

    Lenau, Torben Anker; Boelskifte, Per; Hansen, Claus Thorp

    2005-01-01

    This paper summarises the purpose and contents of the 3rd Nordcode Seminar and Workshop. First, the workshop assignments are described. Second, the paper briefly presents the topics of the keynote speeches and all presentations of the working papers that took place in the seminar.......This paper summarises the purpose and contents of the 3rd Nordcode Seminar and Workshop. First, the workshop assignments are described. Second, the paper briefly presents the topics of the keynote speeches and all presentations of the working papers that took place in the seminar....

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

    International Nuclear Information System (INIS)

    Suzuki, Motoe; Saitou, Hiroaki.

    1997-11-01

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

  8. Integrated Fuel-Coolant Interaction (IFCI 7.0) Code User's Manual

    Energy Technology Data Exchange (ETDEWEB)

    Young, Michael F.

    1999-05-01

    The integrated fuel-coolant interaction (IFCI) computer code is being developed at Sandia National Laboratories to investigate the fuel-coolant interaction (FCI) problem at large scale using a two-dimensional, three-field hydrodynamic framework and physically based models. IFCI will be capable of treating all major FCI processes in an integrated manner. This document is a description of IFCI 7.0. The user's manual describes the hydrodynamic method and physical models used in IFCI 7.0. Appendix A is an input manual provided for the creation of working decks.

  9. Integrated Fuel-Coolant Interaction (IFCI 7.0) Code User's Manual

    International Nuclear Information System (INIS)

    Young, Michael F.

    1999-01-01

    The integrated fuel-coolant interaction (IFCI) computer code is being developed at Sandia National Laboratories to investigate the fuel-coolant interaction (FCI) problem at large scale using a two-dimensional, three-field hydrodynamic framework and physically based models. IFCI will be capable of treating all major FCI processes in an integrated manner. This document is a description of IFCI 7.0. The user's manual describes the hydrodynamic method and physical models used in IFCI 7.0. Appendix A is an input manual provided for the creation of working decks

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

    Science.gov (United States)

    Wright, William B.

    2002-01-01

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

  11. 3rd Semester and Master’s Thesis Ideas 2011

    DEFF Research Database (Denmark)

    The report contain a list of project ideas proposed by the scientific staff at the Department of Civil Engineering, Aalborg University, and a number of companies. Most of the project ideas in this catalogue may form the basis for long and short candidate projects as well as regular 3rd semester...

  12. 3rd Semester and Master’s Thesis Ideas 2013

    DEFF Research Database (Denmark)

    The following pages contain a list of project ideas proposed by the scientific staff at the Department of Civil Engineering, Aalborg University, and a number of companies. Most of the project ideas in this catalogue may form the basis for long and short master projects as well as regular 3rd...

  13. 3rd Semester and Master’s Thesis Ideas 2012

    DEFF Research Database (Denmark)

    Clausen, Johan

    The report contain a list of project ideas proposed by the scientific staff at the Department of Civil Engineering, Aalborg University, and a number of companies. Most of the project ideas in this catalogue may form the basis for long and short candidate projects as well as regular 3rd semester...

  14. Magnet Free Generators - 3rd Generation Wind Turbine Generators

    DEFF Research Database (Denmark)

    Jensen, Bogi Bech; Mijatovic, Nenad; Henriksen, Matthew Lee

    2013-01-01

    This paper presents an introduction to superconducting wind turbine generators, which are often referred to as 3rd generation wind turbine generators. Advantages and challenges of superconducting generators are presented with particular focus on possible weight and efficiency improvements. A comp...

  15. 3rd Session of the Sant Cugat Forum on Astrophysics

    CERN Document Server

    Gravitational wave astrophysics

    2015-01-01

    This book offers review chapters written by invited speakers of the 3rd Session of the Sant Cugat Forum on Astrophysics — Gravitational Waves Astrophysics. All chapters have been peer reviewed. The book goes beyond normal conference proceedings in that it provides a wide panorama of the astrophysics of gravitational waves and serves as a reference work for researchers in the field.

  16. Proceedings of the 3rd Symposium on Laser Spectroscopy

    International Nuclear Information System (INIS)

    1995-11-01

    This proceedings contains articles of the 3rd Symposium on Laser Spectroscopy. It was held on Nov 10-11, 1995 in Taejeon, Korea. The main topics are as follows: Laser Isotope, Laser Spectroscopy, Laser Fusion, Laser Applications and so on. (Yi, J. H.)

  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. User's manual for computer code RIBD-II, a fission product inventory code

    International Nuclear Information System (INIS)

    Marr, D.R.

    1975-01-01

    The computer code RIBD-II is used to calculate inventories, activities, decay powers, and energy releases for the fission products generated in a fuel irradiation. Changes from the earlier RIBD code are: the expansion to include up to 850 fission product isotopes, input in the user-oriented NAMELIST format, and run-time choice of fuels from an extensively enlarged library of nuclear data. The library that is included in the code package contains yield data for 818 fission product isotopes for each of fourteen different fissionable isotopes, together with fission product transmutation cross sections for fast and thermal systems. Calculational algorithms are little changed from those in RIBD. (U.S.)

  19. RELAP5/MOD3 code manual: Code structure, system models, and solution methods. Volume 1

    International Nuclear Information System (INIS)

    1995-08-01

    The RELAP5 code has been developed for best estimate transient simulation of light water reactor coolant systems during postulated accidents. The code models the coupled behavior of the reactor coolant system and the core for loss-of-coolant accidents, and operational transients, such as anticipated transient without scram, loss of offsite power, loss of feedwater, and loss of flow. A generic modeling, approach is used that permits simulating a variety of thermal hydraulic systems. Control system and secondary system components are included to permit modeling of plant controls, turbines, condensers, and secondary feedwater systems. RELAP5/MOD3 code documentation is divided into seven volumes: Volume I provides modeling theory and associated numerical schemes

  20. MATADOR (Methods for the Analysis of Transport And Deposition Of Radionuclides) code description and User's Manual

    International Nuclear Information System (INIS)

    Avci, H.I.; Raghuram, S.; Baybutt, P.

    1985-04-01

    A new computer code called MATADOR (Methods for the Analysis of Transport And Deposition Of Radionuclides) has been developed to replace the CORRAL-2 computer code which was written for the Reactor Safety Study (WASH-1400). This report is a User's Manual for MATADOR. MATADOR is intended for use in system risk studies to analyze radionuclide transport and deposition in reactor containments. The principal output of the code is information on the timing and magnitude of radionuclide releases to the environment as a result of severely degraded core accidents. MATADOR considers the transport of radionuclides through the containment and their removal by natural deposition and by engineered safety systems such as sprays. It is capable of analyzing the behavior of radionuclides existing either as vapors or aerosols in the containment. The code requires input data on the source terms into the containment, the geometry of the containment, and thermal-hydraulic conditions in the containment

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

    Energy Technology Data Exchange (ETDEWEB)

    Hanawa, Satoshi; Iyoku, Tatsuo [Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment

    2001-08-01

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

  2. A user input manual for single fuel rod behaviour analysis code FEMAXI-III

    International Nuclear Information System (INIS)

    Saito, Hiroaki; Yanagisawa, Kazuaki; Fujita, Misao.

    1983-03-01

    Principal objectives of Safety related research in connection with lighr water reactor fuel rods under normal operating condition are mainly addressed 1) to assess fuel integrity under steady state condition and 2) to generate initial condition under hypothetical accident. These assessments have to be relied principally upon steady state fuel behaviour computing code that is able to calculate fuel conditions to tbe occurred in a various manner. To achieve these objectives, efforts have been made to develope analytical computer code that calculates in-reactor fuel rod behaviour in best estimate manner. The computer code developed for the prediction of the long-term burnup response of single fuel rod under light water reactor condition is the third in a series of code versions:FEMAMI-III. The code calculates temperature, rod internal gas pressure, fission gas release and pellet-cladding interaction related rod deformation as a function of time-dependent fuel rod power and coolant boundary conditions. This document serves as a user input manual for the code FEMAMI-III which has opened to the public in year of 1982. A general description of the code input and output are included together with typical examples of input data. A detailed description of structures, analytical submodels and solution schemes in the code shall be given in the separate document to be published. (author)

  3. ABAQUS-EPGEN: a general-purpose finite element code. Volume 3. Example problems manual

    International Nuclear Information System (INIS)

    Hibbitt, H.D.; Karlsson, B.I.; Sorensen, E.P.

    1983-03-01

    This volume is the Example and Verification Problems Manual for ABAQUS/EPGEN. Companion volumes are the User's, Theory and Systems Manuals. This volume contains two major parts. The bulk of the manual (Sections 1-8) contains worked examples that are discussed in detail, while Appendix A documents a large set of basic verification cases that provide the fundamental check of the elements in the code. The examples in Sections 1-8 illustrate and verify significant aspects of the program's capability. Most of these problems provide verification, but they have also been chosen to allow discussion of modeling and analysis techniques. Appendix A contains basic verification cases. Each of these cases verifies one element in the program's library. The verification consists of applying all possible load or flux types (including thermal loading of stress elements), and all possible foundation or film/radiation conditions, and checking the resulting force and stress solutions or flux and temperature results. This manual provides program verification. All of the problems described in the manual are run and the results checked, for each release of the program, and these verification results are made available

  4. 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…

  5. ATHENA code manual. Volume 1. Code structure, system models, and solution methods

    International Nuclear Information System (INIS)

    Carlson, K.E.; Roth, P.A.; Ransom, V.H.

    1986-09-01

    The ATHENA (Advanced Thermal Hydraulic Energy Network Analyzer) code has been developed to perform transient simulation of the thermal hydraulic systems which may be found in fusion reactors, space reactors, and other advanced systems. A generic modeling approach is utilized which permits as much of a particular system to be modeled as necessary. Control system and secondary system components are included to permit modeling of a complete facility. Several working fluids are available to be used in one or more interacting loops. Different loops may have different fluids with thermal connections between loops. The modeling theory and associated numerical schemes are documented in Volume I in order to acquaint the user with the modeling base and thus aid effective use of the code. The second volume contains detailed instructions for input data preparation

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

    International Nuclear Information System (INIS)

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

    2002-03-01

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

  7. 3rd International Conference on Ecosystem Assessment Management

    CERN Document Server

    Ma, Sheng-Quan; Cao, Hu-hua; Ecosystem Assessment and Fuzzy Systems Management

    2014-01-01

    “Ecosystem Assessment and Fuzzy Systems Management” is the edited outcome of the 3rd International Conference on Ecosystem Assessment Management (ICEAM) and the Workshop on the Construction of an Early Warning Platform for Eco-tourism (WCEWPE) in Hainan on May 5-12, 2013, Haikou, China. The 3rd ICEAM and the WCEWPE, built on the success of previous conferences, are major Symposiums for scientists, engineers and logistic management researchers presenting their the latest achievements, developments and applications in all areas of Ecosystem Assessment Management, Early Warning Platform for Eco-tourism and fuzziology. It aims to strengthen relations between industry research laboratories and universities, and to create a primary symposium for world scientists. The book, containing 47 papers, is divided into five parts: “Ecosystem Assessment, Management and Information”; “Intelligent Algorithm, Fuzzy Optimization and Engineering Application”; “Spatial Data Analysis and Intelligent Information Proces...

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2001-03-01

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

  9. SHEAT: a computer code for probabilistic seismic hazard analysis, user's manual

    International Nuclear Information System (INIS)

    Ebisawa, Katsumi; Kondo, Masaaki; Abe, Kiyoharu; Tanaka, Toshiaki; Takani, Michio.

    1994-08-01

    The SHEAT code developed at Japan Atomic Energy Research Institute is for probabilistic seismic hazard analysis which is one of the tasks needed for seismic Probabilistic Safety Assessment (PSA) of a nuclear power plant. Seismic hazard is defined as an annual exceedance frequency of occurrence of earthquake ground motions at various levels of intensity at a given site. With the SHEAT code, seismic hazard is calculated by the following two steps: (1) Modeling of earthquake generation around a site. Future earthquake generation (locations, magnitudes and frequencies of postulated earthquakes) is modelled based on the historical earthquake records, active fault data and expert judgement. (2) Calculation of probabilistic seismic hazard at the site. An earthquake ground motion is calculated for each postulated earthquake using an attenuation model taking into account its standard deviation. Then the seismic hazard at the site is calculated by summing the frequencies of ground motions by all the earthquakes. This document is the user's manual of the SHEAT code. It includes: (1) Outlines of the code, which include overall concept, logical process, code structure, data file used and special characteristics of the code, (2) Functions of subprograms and analytical models in them, (3) Guidance of input and output data, and (4) Sample run results. The code has widely been used at JAERI to analyze seismic hazard at various nuclear power plant sites in japan. (author)

  10. The CFEST-INV stochastic hydrology code: Mathematical formulation, application, and user's manual

    International Nuclear Information System (INIS)

    Devary, J.L.

    1987-06-01

    Performance assessments of a nuclear waste repository must consider the hydrologic, thermal, mechanical, and geochemical environments of a candidate site. Predictions of radionuclide transport requires estimating water movement as a function of pressure, temperature, and solute concentration. CFEST (Coupled Fluid, Energy, and Solute Transport), is a finite-element based groundwater code that can be used to simultaneously solve the partial differential equations for pressure head, solute temperature, and solute concentration. The CFEST code has been designed to support site, repository, and waste package subsystem assessments. CFEST-INV is a stochastic hydrology code that was developed to augment the CFEST code in data processing; model calibration; performance prediction; error propagation; and data collection guidance. The CFEST-INV code utilizes kriging, finite-element modeling, adjoint-sensitivity, statistical-inverse, first-order variance, and Monte-Carlo techniques to develop performance (measure) driven data collection schemes and to determine the waste isolation capabilities (including uncertainties) of candidate repository sites. This report contains the basic physical and numerical principles of the CFEST-INV code, its input parameters, verification exercises, a user's manual, and the code's application history. 18 refs., 16 figs., 6 tabs

  11. User's manuals of probabilistic fracture mechanics analysis code for aged piping, PASCAL-SP

    International Nuclear Information System (INIS)

    Itoh, Hiroto; Nishikawa, Hiroyuki; Onizawa, Kunio; Kato, Daisuke; Osakabe, Kazuya

    2010-03-01

    As a part of research on the material degradation and structural integrity assessment for aged LWR components, a PFM (Probabilistic Fracture Mechanics) analysis code PASCAL-SP (PFM Analysis of Structural Components in Aging LWR - Stress Corrosion Cracking at Welded Joints of Piping) has been developed. This code evaluates the failure probabilities at welded joints of aged piping by a Monte Carlo method. PASCAL-SP treats stress corrosion cracking (SCC) and fatigue crack growth in piping, according to the approaches of NISA and JSME FFS Code. The development of the code has been aimed to improve the accuracy and reliability of analysis by introducing new analysis methodologies and algorithms considering the latest knowledge in the SCC assessment and fracture criteria of piping. In addition, the accuracy of flaw detection and sizing at in-service inspection and residual stress distribution were modeled based on experimental data and introduced into PASCAL-SP. This code has been developed for a cross-check use by the regulatory body in Japan. In addition to this, this code can also be used for a research purpose by researchers in academia and industries. This report provides the user's manual and theoretical background of the code. (author)

  12. 3rd International Multidisciplinary Microscopy and Microanalysis Congress

    CERN Document Server

    Oral, Zehra

    2017-01-01

    The 3rd International Multidisciplinary Microscopy Congress (InterM2015), held from 19 to 23 October 2015, focused on the latest developments concerning applications of microscopy in the biological, physical and chemical sciences at all dimensional scales, advances in instrumentation, techniques in and educational materials on microscopy. These proceedings gather 17 peer-reviewed technical papers submitted by leading academic and research institutions from nine countries and representing some of the most cutting-edge research available.

  13. 3rd International Conference on Computer & Communication Technologies

    CERN Document Server

    Bhateja, Vikrant; Raju, K; Janakiramaiah, B

    2017-01-01

    The book is a compilation of high-quality scientific papers presented at the 3rd International Conference on Computer & Communication Technologies (IC3T 2016). The individual papers address cutting-edge technologies and applications of soft computing, artificial intelligence and communication. In addition, a variety of further topics are discussed, which include data mining, machine intelligence, fuzzy computing, sensor networks, signal and image processing, human-computer interaction, web intelligence, etc. As such, it offers readers a valuable and unique resource.

  14. 3rd Interplanetary Network Gamma-Ray Burst Website

    Science.gov (United States)

    Hurley, Kevin

    1998-05-01

    We announce the opening of the 3rd Interplanetary Network web site at http://ssl.berkeley.edu/ipn3/index.html This site presently has four parts: 1. A bibliography of over 3000 publications on gamma-ray bursts, 2. IPN data on all bursts triangulated up to February 1998, 3. A master list showing which spacecraft observed which bursts, 4. Preliminary IPN data on the latest bursts observed.

  15. Sandia National Laboratories environmental fluid dynamics code. Marine Hydrokinetic Module User's Manual

    Energy Technology Data Exchange (ETDEWEB)

    James, Scott Carlton; Roberts, Jesse D

    2014-03-01

    This document describes the marine hydrokinetic (MHK) input file and subroutines for the Sandia National Laboratories Environmental Fluid Dynamics Code (SNL-EFDC), which is a combined hydrodynamic, sediment transport, and water quality model based on the Environmental Fluid Dynamics Code (EFDC) developed by John Hamrick [1], formerly sponsored by the U.S. Environmental Protection Agency, and now maintained by Tetra Tech, Inc. SNL-EFDC has been previously enhanced with the incorporation of the SEDZLJ sediment dynamics model developed by Ziegler, Lick, and Jones [2-4]. SNL-EFDC has also been upgraded to more accurately simulate algae growth with specific application to optimizing biomass in an open-channel raceway for biofuels production [5]. A detailed description of the input file containing data describing the MHK device/array is provided, along with a description of the MHK FORTRAN routine. Both a theoretical description of the MHK dynamics as incorporated into SNL-EFDC and an explanation of the source code are provided. This user manual is meant to be used in conjunction with the original EFDC [6] and sediment dynamics SNL-EFDC manuals [7]. Through this document, the authors provide information for users who wish to model the effects of an MHK device (or array of devices) on a flow system with EFDC and who also seek a clear understanding of the source code, which is available from staff in the Water Power Technologies Department at Sandia National Laboratories, Albuquerque, New Mexico.

  16. User's manual for SPLPLOT-2: a computer code for data plotting and editing in conversational mode

    International Nuclear Information System (INIS)

    Muramatsu, Ken; Matsumoto, Kiyoshi; Kohsaka, Atsuo; Maniwa, Masaki.

    1985-07-01

    The computer code SPLPLOT-2 for plotting and data editing has been developed as a part of the code package: SPLPACK-1. The SPLPLOT-2 code has capabilities of both conversational and batch processings. This report describes the user's manual for SPLPLOT-2. The following improvements have been made in the SPLPLOT-2. (1) It has capabilities of both conversational and batch processings, (2) function of conversion of files from the input SPL (Standard PLotter) files to internal work files have been implemented to reduce number of time consuming access to the input SPL files, (3) user supplied subroutines can be assigned for data editing from the SPL files, (4) in addition to the two-dimensional graphs, streamline graphs, contour line graphs and bird's-eye view graphs can be drawn. (author)

  17. VIPRE-01: a thermal-hydraulic analysis code for reactor cores. Volume 2. User's manual

    International Nuclear Information System (INIS)

    Cuta, J.M.; Koontz, A.S.; Stewart, C.W.; Montgomery, S.D.

    1983-04-01

    VIPRE (Versatile Internals and Component Program for Reactors; EPRI) has been developed for nuclear power utility thermal-hydraulic analysis applications. It is designed to help evaluate nuclear energy reactor core safety limits including minimum departure from nucleate boiling ratio (MDNBR), critical power ratio (CPR), fuel and clad temperatures, and coolant state in normal operation and assumed accident conditions. This volume (Volume 2: User's Manual) describes the input requirements of VIPRE and its auxiliary programs, SPECSET, ASP and DECCON, and lists the input instructions for each code

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

    International Nuclear Information System (INIS)

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

    2005-01-01

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

  19. A user's manual for the three-dimensional Monte Carlo transport code SPARTAN

    International Nuclear Information System (INIS)

    Bending, R.C.; Heffer, P.J.H.

    1975-09-01

    SPARTAN is a general-purpose Monte Carlo particle transport code intended for neutron or gamma transport problems in reactor physics, health physics, shielding, and safety studies. The code used a very general geometry system enabling a complex layout to be described and allows the user to obtain physics data from a number of different types of source library. Special tracking and scoring techniques are used to improve the quality of the results obtained. To enable users to run SPARTAN, brief descriptions of the facilities available in the code are given and full details of data input and job control language, as well as examples of complete calculations, are included. It is anticipated that changes may be made to SPARTAN from time to time, particularly in those parts of the code which deal with physics data processing. The load module is identified by a version number and implementation date, and updates of sections of this manual will be issued when significant changes are made to the code. (author)

  20. 3rd International Conference on Intelligent Technologies and Engineering Systems

    CERN Document Server

    2016-01-01

    This book includes the original, peer reviewed research from the 3rd International Conference on Intelligent Technologies and Engineering Systems (ICITES2014), held in December, 2014 at Cheng Shiu University in Kaohsiung, Taiwan. Topics covered include: Automation and robotics, fiber optics and laser technologies, network and communication systems, micro and nano technologies, and solar and power systems. This book also Explores emerging technologies and their application in a broad range of engineering disciplines Examines fiber optics and laser technologies Covers biomedical, electrical, industrial, and mechanical systems Discusses multimedia systems and applications, computer vision and image & video signal processing.

  1. 3rd Workshop on "Combinations of Intelligent Methods and Applications"

    CERN Document Server

    Palade, Vasile

    2013-01-01

    The combination of different intelligent methods is a very active research area in Artificial Intelligence (AI). The aim is to create integrated or hybrid methods that benefit from each of their components.  The 3rd Workshop on “Combinations of Intelligent Methods and Applications” (CIMA 2012) was intended to become a forum for exchanging experience and ideas among researchers and practitioners who are dealing with combining intelligent methods either based on first principles or in the context of specific applications. CIMA 2012 was held in conjunction with the 22nd European Conference on Artificial Intelligence (ECAI 2012).This volume includes revised versions of the papers presented at CIMA 2012.  .

  2. 3rd Conference on Ignition Systems for Gasoline Engines

    CERN Document Server

    Sens, Marc

    2017-01-01

    The volume includes selected and reviewed papers from the 3rd Conference on Ignition Systems for Gasoline Engines in Berlin in November 2016. Experts from industry and universities discuss in their papers the challenges to ignition systems in providing reliable, precise ignition in the light of a wide spread in mixture quality, high exhaust gas recirculation rates and high cylinder pressures. Classic spark plug ignition as well as alternative ignition systems are assessed, the ignition system being one of the key technologies to further optimizing the gasoline engine.

  3. The 3rd Sino-Japan nuclear medicine conference

    International Nuclear Information System (INIS)

    1999-01-01

    The 3rd Sino-Japan Nuclear Medicine Conference was hold on May 11-13, 1999 in Xi'an of China by Chinese Society of Nuclear Medicine, Japanese Society of Nuclear Medicine, Chinese Medicine Association and Japan-China Medicine Association. 62 articles were published in the proceeding of the conference. The contents of the articles include development and application of the radioisotopes (such as Tc-99, I-125, I-131, F-18, In-111, Tl-201, Ga-67, Sm-153, Re-188) and its radiopharmaceuticals, but application also include radiotherapy and diagnosis in the oncology and pathology by SPECT and PET

  4. Proceedings of the 3rd Symposium on Engineering Sciences

    International Nuclear Information System (INIS)

    Ahmed, J.; Rizvi, S.Z.H.; Ahmad, R.; Saleem, M.

    2010-01-01

    The 3rd symposium on engineering sciences was held from March 10-12, 2010 in Lahore, Pakistan. More than twenty academic institutions and six industries participated in this conference. The foreign and Pakistani experts delivered their keynotes talk, contributor lectures and poster presentation on the conference topics. In three days of the symposium, Fifty four papers presented on different topics of Engineering Sciences including chemical engineering, energy engineering, metallurgy engineering, material engineering and electrical engineering. This symposium provided an ideal opportunity for exchange of information amongst scientists, engineers and researchers from all over Pakistan and other countries of the world. (A.B)

  5. 3rd International Conference on Movement, Health and Exercise 2016

    CERN Document Server

    Cheong, Jadeera; Usman, Juliana; Ahmad, Mohd; Razman, Rizal; Selvanayagam, Victor

    2017-01-01

    This volume presents the proceedings of the 3rd International Conference on Movement, Health and Exercise 2016 (MoHE2016). The conference was jointly organized by the Biomedical Engineering Department and Sports Centre, University of Malaya. It was held in Malacca, from 28-30 September 2016. MoHE 2016 provided a good opportunity for speakers and participants to actively discuss about recent developments in a wide range of topics in the area of sports and exercise science. In total, 83 presenters and 140 participants took part in this successful conference. .

  6. Manual of a suite of computer codes, EXPRESS (EXact PREparedness Supporting System)

    International Nuclear Information System (INIS)

    Chino, Masamichi

    1992-06-01

    The emergency response supporting system EXPRESS (EXact PREparedness Supporting System) is constructed in JAERI for low cost engineering work stations under the UNIX operation. The purpose of this system is real-time predictions of affected areas due to radioactivities discharged into atmosphere from nuclear facilities. The computational models in EXPRESS are the mass-consistent wind field model EXPRESS-I and the particle dispersion model EXPRESS-II for atmospheric dispersions. In order to attain the quick response even when the codes are used in a small-scale computer, a high-speed iteration method MILUCR (Modified Incomplete Linear Unitary Conjugate Residual) is applied to EXPRESS-I and kernel density method is to EXPRESS-II. This manual describes the model configurations, code structures, related files, namelists and sample outputs of EXPRESS-I and -II. (author)

  7. User's manual for the BNW-II optimization code for dry/wet-cooled power plants

    International Nuclear Information System (INIS)

    Braun, D.J.; Bamberger, J.A.; Braun, D.J.; Faletti, D.W.; Wiles, L.E.

    1978-05-01

    The User's Manual describes how to operate BNW-II, a computer code developed by the Pacific Northwest Laboratory (PNL) as a part of its activities under the Department of Energy (DOE) Dry Cooling Enhancement Program. The computer program offers a comprehensive method of evaluating the cost savings potential of dry/wet-cooled heat rejection systems. Going beyond simple ''figure-of-merit'' cooling tower optimization, this method includes such items as the cost of annual replacement capacity, and the optimum split between plant scale-up and replacement capacity, as well as the purchase and operating costs of all major heat rejection components. Hence the BNW-II code is a useful tool for determining potential cost savings of new dry/wet surfaces, new piping, or other components as part of an optimized system for a dry/wet-cooled plant

  8. Detailed description and user`s manual of high burnup fuel analysis code EXBURN-I

    Energy Technology Data Exchange (ETDEWEB)

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

    1997-11-01

    EXBURN-I has been developed for the analysis of LWR high burnup fuel behavior in normal operation and power transient conditions. In the high burnup region, phenomena occur which are different in quality from those expected for the extension of behaviors in the mid-burnup region. To analyze these phenomena, EXBURN-I has been formed by the incorporation of such new models as pellet thermal conductivity change, burnup-dependent FP gas release rate, and cladding oxide layer growth to the basic structure of low- and mid-burnup fuel analysis code FEMAXI-IV. The present report describes in detail the whole structure of the code, models, and materials properties. Also, it includes a detailed input manual and sample output, etc. (author). 55 refs.

  9. 3rd International Conference on X-ray Technique

    Science.gov (United States)

    Potrakhov, N. N.; Gryaznov, A. Yu; Lisenkov, A. A.; Kostrin, D. K.

    2017-02-01

    In this preface a brief history, modern aspects and future tendencies in development of the X-ray technique as seen from the 3rd International Conference on X-ray Technique that was held on 24-25 November 2016 in Saint Petersburg, Russia are described On 24-25 November 2016 in Saint Petersburg on the basis of Saint Petersburg State Electrotechnical University “LETI” n. a. V. I. Ulyanov (Lenin) was held the 3rd International Conference on X-ray Technique. The tradition to hold a similar conference in our country was laid in Soviet times. The last of them, the All-Union Conference on the Prospects of X-ray Tubes and Equipment was organized and held more than a quarter century ago - on 21-23 November 1999, at the initiative and under the leadership of the chief engineer of the Leningrad association of electronic industry “Svetlana” Borovsky Alexander Ivanovich and the chief of special design bureau of X-ray devices of “Svetlana” Shchukin Gennady Anatolievich. The most active part in the organization and work of the conference played members of the department of X-ray and electron beam instruments of Leningrad Electrotechnical Institute “LETI” (the former name of Saint Petersburg State Electrotechnical University “LETI”), represented by head of the department professor Ivanov Stanislav Alekseevich.

  10. Microstructure Modeling of 3rd Generation Disk Alloys

    Science.gov (United States)

    Jou, Herng-Jeng

    2010-01-01

    The objective of this program is to model, validate, and predict the precipitation microstructure evolution, using PrecipiCalc (QuesTek Innovations LLC) software, for 3rd generation Ni-based gas turbine disc superalloys during processing and service, with a set of logical and consistent experiments and characterizations. Furthermore, within this program, the originally research-oriented microstructure simulation tool will be further improved and implemented to be a useful and user-friendly engineering tool. In this report, the key accomplishment achieved during the second year (2008) of the program is summarized. The activities of this year include final selection of multicomponent thermodynamics and mobility databases, precipitate surface energy determination from nucleation experiment, multiscale comparison of predicted versus measured intragrain precipitation microstructure in quench samples showing good agreement, isothermal coarsening experiment and interaction of grain boundary and intergrain precipitates, primary microstructure of subsolvus treatment, and finally the software implementation plan for the third year of the project. In the following year, the calibrated models and simulation tools will be validated against an independently developed experimental data set, with actual disc heat treatment process conditions. Furthermore, software integration and implementation will be developed to provide material engineers valuable information in order to optimize the processing of the 3rd generation gas turbine disc alloys.

  11. 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

  12. User's manual of SECOM2: a computer code for seismic system reliability analysis

    International Nuclear Information System (INIS)

    Uchiyama, Tomoaki; Oikawa, Tetsukuni; Kondo, Masaaki; Tamura, Kazuo

    2002-03-01

    This report is the user's manual of seismic system reliability analysis code SECOM2 (Seismic Core Melt Frequency Evaluation Code Ver.2) developed at the Japan Atomic Energy Research Institute for systems reliability analysis, which is one of the tasks of seismic probabilistic safety assessment (PSA) of nuclear power plants (NPPs). The SECOM2 code has many functions such as: Calculation of component failure probabilities based on the response factor method, Extraction of minimal cut sets (MCSs), Calculation of conditional system failure probabilities for given seismic motion levels at the site of an NPP, Calculation of accident sequence frequencies and the core damage frequency (CDF) with use of the seismic hazard curve, Importance analysis using various indicators, Uncertainty analysis, Calculation of the CDF taking into account the effect of the correlations of responses and capacities of components, and Efficient sensitivity analysis by changing parameters on responses and capacities of components. These analyses require the fault tree (FT) representing the occurrence condition of the system failures and core damage, information about response and capacity of components and seismic hazard curve for the NPP site as inputs. This report presents the models and methods applied in the SECOM2 code and how to use those functions. (author)

  13. 3rd Workshop on Branching Processes and their Applications

    CERN Document Server

    González, Miguel; Gutiérrez, Cristina; Martínez, Rodrigo; Minuesa, Carmen; Molina, Manuel; Mota, Manuel; Ramos, Alfonso; WBPA15

    2016-01-01

    This volume gathers papers originally presented at the 3rd Workshop on Branching Processes and their Applications (WBPA15), which was held from 7 to 10 April 2015 in Badajoz, Spain (http://branching.unex.es/wbpa15/index.htm). The papers address a broad range of theoretical and practical aspects of branching process theory. Further, they amply demonstrate that the theoretical research in this area remains vital and topical, as well as the relevance of branching concepts in the development of theoretical approaches to solving new problems in applied fields such as Epidemiology, Biology, Genetics, and, of course, Population Dynamics. The topics covered can broadly be classified into the following areas: 1. Coalescent Branching Processes 2. Branching Random Walks 3. Population Growth Models in Varying and Random Environments 4. Size/Density/Resource-Dependent Branching Models 5. Age-Dependent Branching Models 6. Special Branching Models 7. Applications in Epidemiology 8. Applications in Biology and Genetics Offer...

  14. EMCS upgrade to 3rd generation not an easy task

    International Nuclear Information System (INIS)

    Neal, C.E.

    1993-01-01

    The Energy Management Control System (EMCS) for Sheppard AFB was started in 1976 with contract completion in 1981. With other additions the system grew to over 8,000 points with 350 Field Panels. Over 35 miles of coax for data transmission were installed. In 1987 an effort was started to move to the open-quotes newclose quotes generation for the central system. At the same time coax replacement with fiber optics was started. This paper discusses the problems encountered which caused a change in plans and a move to 3rd generation system. There are many things to consider when attempting an upgrade. Conflicting information will make the task that much harder. This paper will attempt to show some of the problems encountered and lessons learned to help others avoid such difficulties

  15. Report from the 3rd Workshop on Extremely Large Databases

    Directory of Open Access Journals (Sweden)

    Jacek Becla

    2010-02-01

    Full Text Available Academic and industrial users are increasingly facing the challenge of petabytes of data, but managing and analyzing such large data sets still remains a daunting task. Both the database and the map/reduce communities worldwide are working on addressing these issues. The 3rdExtremely Large Databases workshop was organized to examine the needs of scientific communities beginning to face these issues, to reach out to European communities working on extremely large scale data challenges, and to brainstorm possible solutions. The science benchmark that emerged from the 2nd workshop in this series was also debated. This paper is the final report of the discussions and activities at this workshop.

  16. 3rd Symposium on Space Optical Instruments and Applications

    CERN Document Server

    Zhang, Guangjun

    2017-01-01

    This volume contains selected and expanded contributions presented at the 3rd Symposium on Space Optical Instruments and Applications in Beijing, China June 28 – 29, 2016. This conference series is organised by the Sino-Holland Space Optical Instruments Laboratory, a cooperation platform between China and the Netherlands. The symposium focused on key technological problems of optical instruments and their applications in a space context. It covered the latest developments, experiments and results regarding theory, instrumentation and applications in space optics. The book is split across five topical sections. The first section covers space optical remote sensing system design, the second advanced optical system design, the third remote sensor calibration and measurement. Remote sensing data processing and information extraction is then presented, followed by a final section on remote sensing data applications. .

  17. 3rd International Conference on Computational Mathematics and Computational Geometry

    CERN Document Server

    Ravindran, Anton

    2016-01-01

    This volume presents original research contributed to the 3rd Annual International Conference on Computational Mathematics and Computational Geometry (CMCGS 2014), organized and administered by Global Science and Technology Forum (GSTF). Computational Mathematics and Computational Geometry are closely related subjects, but are often studied by separate communities and published in different venues. This volume is unique in its combination of these topics. After the conference, which took place in Singapore, selected contributions chosen for this volume and peer-reviewed. The section on Computational Mathematics contains papers that are concerned with developing new and efficient numerical algorithms for mathematical sciences or scientific computing. They also cover analysis of such algorithms to assess accuracy and reliability. The parts of this project that are related to Computational Geometry aim to develop effective and efficient algorithms for geometrical applications such as representation and computati...

  18. 3rd Computer Science On-line Conference

    CERN Document Server

    Senkerik, Roman; Oplatkova, Zuzana; Silhavy, Petr; Prokopova, Zdenka

    2014-01-01

    This book is based on the research papers presented in the 3rd Computer Science On-line Conference 2014 (CSOC 2014).   The conference is intended to provide an international forum for discussions on the latest high-quality research results in all areas related to Computer Science. The topics addressed are the theoretical aspects and applications of Artificial Intelligences, Computer Science, Informatics and Software Engineering.   The authors provide new approaches and methods to real-world problems, and in particular, exploratory research that describes novel approaches in their field. Particular emphasis is laid on modern trends in selected fields of interest. New algorithms or methods in a variety of fields are also presented.   This book is divided into three sections and covers topics including Artificial Intelligence, Computer Science and Software Engineering. Each section consists of new theoretical contributions and applications which can be used for the further development of knowledge of everybod...

  19. 3rd International Workshop on Turbulent Spray Combustion

    CERN Document Server

    Gutheil, Eva

    2014-01-01

    This book reflects the results of the 2nd and 3rd International Workshops on Turbulent Spray Combustion. The focus is on progress in experiments and numerical simulations for two-phase flows, with emphasis on spray combustion. Knowledge of the dominant phenomena and their interactions allows development of predictive models and their use in combustor and gas turbine design. Experts and young researchers present the state-of-the-art results, report on the latest developments and exchange ideas in the areas of experiments, modelling and simulation of reactive multiphase flows. The first chapter reflects on flame structure, auto-ignition and atomization with reference to well-characterized burners, to be implemented by modellers with relative ease. The second chapter presents an overview of first simulation results on target test cases, developed at the occasion of the 1st International Workshop on Turbulent Spray Combustion. In the third chapter, evaporation rate modelling aspects are covered, while the fourth ...

  20. 3rd International Symposium for Intelligent Transportation and Smart City

    CERN Document Server

    Xie, Xiongyao; Sun, Jian; Ma, Limin; Chen, Yinong; ITASC

    2017-01-01

    This book presents research advances in intelligent transportation and smart cities in detail, mainly focusing on green traffic and urban utility tunnels, presented at the 3rd International Symposium for Intelligent Transportation and Smart City (ITASC) held at Tongji University, Shanghai, on May 19–20, 2017. It discusses a number of hot topics, such as the 2BMW system (Bus, Bike, Metro and Walking), transportation safety and environmental protection, urban utility design and application, as well as the application of BIM (Building Information Modeling) in city design. By connecting the theory and applications of intelligent transportation in smart cities, it enhances traffic efficiency and quality. The book gathers numerous selected papers and lectures, including contributions from respected scholars and the latest engineering advances, to provide guidance to researchers in the field of transportation and urban planning at universities and in related industries. The first conference in the ITASC series sta...

  1. 3rd International Conference on Nanotechnologies and Biomedical Engineering

    CERN Document Server

    Tiginyanu, Ion

    2016-01-01

    This volume presents the proceedings of the 3rd International Conference on Nanotechnologies and Biomedical Engineering which was held on September 23-26, 2015 in Chisinau, Republic of Moldova. ICNBME-2015 continues the series of International Conferences in the field of nanotechnologies and biomedical engineering. It aims at bringing together scientists and engineers dealing with fundamental and applied research for reporting on the latest theoretical developments and applications involved in the fields. Topics include Nanotechnologies and nanomaterials Plasmonics and metamaterials Bio-micro/nano technologies Biomaterials Biosensors and sensors systems Biomedical instrumentation Biomedical signal processing Biomedical imaging and image processing Molecular, cellular and tissue engineering Clinical engineering, health technology management and assessment; Health informatics, e-health and telemedicine Biomedical engineering education Nuclear and radiation safety and security Innovations and technology transfer...

  2. 3rd International Conference on Robot Intelligence Technology and Applications

    CERN Document Server

    Yang, Weimin; Jo, Jun; Sincak, Peter; Myung, Hyun

    2015-01-01

    This book covers all aspects of robot intelligence from perception at sensor level and reasoning at cognitive level to behavior planning at execution level for each low level segment of the machine. It also presents the technologies for cognitive reasoning, social interaction with humans, behavior generation, ability to cooperate with other robots, ambience awareness, and an artificial genome that can be passed on to other robots. These technologies are to materialize cognitive intelligence, social intelligence, behavioral intelligence, collective intelligence, ambient intelligence and genetic intelligence. The book aims at serving researchers and practitioners with a timely dissemination of the recent progress on robot intelligence technology and its applications, based on a collection of papers presented at the 3rd International Conference on Robot Intelligence Technology and Applications (RiTA), held in Beijing, China, November 6 - 8, 2014. For better readability, this edition has the total 74 papers group...

  3. Organizational Knowledge Communication – a Nascent 3rd Order Disciplinarity

    DEFF Research Database (Denmark)

    Kastberg, Peter

    2014-01-01

    There is an emerging tendency that the organizational communication functions of larger companies enter into a symbiotic relationship with the companies’ Knowledge Management function. A tendency this journal has labelled Organizational Knowledge Communication. This should come as no surprise...... to neither the researcher nor the practitioner; after all who can say where a corporation’s knowledge work ends and where its organizational communication begins – and vice versa? In this paper I will present a theoretical account of the three disciplinary trajectories that, in my view, have given rise...... to Organizational Knowledge Communication, i.e., organization studies, communication theory and Knowledge Management, respectively. In their synthesis the three trajectories form a disciplinary triple helix, a triple helix which, in turn, gives rise to Organizational Knowledge Communication as a novel, 3rd order...

  4. 3rd grade English language learners making sense of sound

    Science.gov (United States)

    Suarez, Enrique; Otero, Valerie

    2013-01-01

    Despite the extensive body of research that supports scientific inquiry and argumentation as cornerstones of physics learning, these strategies continue to be virtually absent in most classrooms, especially those that involve students who are learning English as a second language. This study presents results from an investigation of 3rd grade students' discourse about how length and tension affect the sound produced by a string. These students came from a variety of language backgrounds, and all were learning English as a second language. Our results demonstrate varying levels, and uses, of experiential, imaginative, and mechanistic reasoning strategies. Using specific examples from students' discourse, we will demonstrate some of the productive aspects of working within multiple language frameworks for making sense of physics. Conjectures will be made about how to utilize physics as a context for English Language Learners to further conceptual understanding, while developing their competence in the English language.

  5. APPLE-3: improvement of APPLE for neutron and gamma-ray flux, spectrum and reaction rate plotting code, and of its code manual

    International Nuclear Information System (INIS)

    Kawasaki, Hiromitu; Maki, Koichi; Seki, Yasushi.

    1991-03-01

    A code APPLE was produced in 1976 for calculating and plotting tritium breeding ratio and tritium production rate distributions. That code was improved as 'APPLE-2' in 1982, to calculate and plot not only tritium breeding ratio but also distributions of neutron and gamma-ray fluxes, their spectra, nuclear heating rates and other reaction rates, and dose rate distributions during operation and after shutdown in 1982. The code APPLE-2 can calculate and plot these nuclear properties derived from neutron and gamma-ray fluxes by ANISN (one dimensional transport code), DOT3.5 (two dimensional transport code) and MORSE (three dimensional Monte Carlo code). We revised the code APPLE-2 as 'APPLE-3' by adding many functions to the APPLE-2 code in accordance with users' requirements proposed in recent progress of fusion reaction nuclear design. With minor modification of APPLE-2, a number of inconsistencies have been found between the code manual and the input data in the code. In the present report, the new functions added to APPLE-2 and improved users' manual are explained. (author)

  6. Results from the UK 3rd generation programme: Albion

    Science.gov (United States)

    McEwen, R. K.; Axcell, C.; Knowles, P.; Hoade, K. P.; Wilson, M.; Dennis, P. N. J.; Backhouse, P.; Gordon, N. T.

    2008-10-01

    Following the development of 1st Generation systems in the 1970s, thermal imaging has been in service with the UK armed forces for over 25 years and has proven itself to be a battle winning technology. More recently the wider accessibility to similar technologies within opposing forces has reduced the military advantage provided by these 1st Generation systems and a clear requirement has been identified by the UK MOD for thermal imaging sensors providing increased detection, recognition and identification (DRI) ranges together with a simplified logistical deployment burden and reduced through-life costs. In late 2005, the UK MOD initiated a programme known as "Albion" to develop high performance 3rd Generation single waveband infrared detectors to meet this requirement. At the same time, under a separate programme supporting higher risk technology, a dual waveband infrared detector was also developed. The development phase of the Albion programme has now been completed and prototype detectors are now available and have been integrated into demonstration thermal imaging cameras. The Albion programme has now progressed into the second phase, incorporating both single and dual waveband devices, focussing on low rate initial production (LRIP) and qualification of the devices for military applications. All of the detectors have been fabricated using cadmium mercury telluride material (CMT), grown by metal organic vapour phase epitaxy (MOVPE) on low cost, gallium arsenide (GaAs) substrates and bump bonded to the silicon read out circuit (ROIC). This paper discusses the design features of the 3rd Generation detectors developed in the UK together with the results obtained from the prototype devices both in the laboratory and when integrated into field deployable thermal imaging cameras.

  7. User and reference manual for the KfK code INS

    International Nuclear Information System (INIS)

    Daum, E.

    1993-09-01

    The INS code (Intense Neutron Source) serves to calculate uncollided neutron flux contours, neutron flux volumes and spatial-dependent neutron flux spectra in the test cell of an intense neutron source, of the t-H 2 O or d-Li concept. With the information of the neutron flux spectra the neutron irradiation damage like displacements per atom (DPA), H- and He-production rates and the generation of foreign elements by transmutations can be calculated for any element at any position in the test cell. This manual gives an introduction into the theory of neutron flux calculation of thick targets and neutron irradiation damage calculations. It is explained how the code is working and the handling of the input and output parameters. For each application of the several code modules an example is given. The results like contours, spectra, flux volumes and damage rates are summarized in tabular form and graphically. Damage and element transmutation data have been calculated for 23 isotopes and compared with the DEMO 1st wall values. (orig./HP) [de

  8. 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.

  9. A computer code to estimate accidental fire and radioactive airborne releases in nuclear fuel cycle facilities: User's manual for FIRIN

    International Nuclear Information System (INIS)

    Chan, M.K.; Ballinger, M.Y.; Owczarski, P.C.

    1989-02-01

    This manual describes the technical bases and use of the computer code FIRIN. This code was developed to estimate the source term release of smoke and radioactive particles from potential fires in nuclear fuel cycle facilities. FIRIN is a product of a broader study, Fuel Cycle Accident Analysis, which Pacific Northwest Laboratory conducted for the US Nuclear Regulatory Commission. The technical bases of FIRIN consist of a nonradioactive fire source term model, compartment effects modeling, and radioactive source term models. These three elements interact with each other in the code affecting the course of the fire. This report also serves as a complete FIRIN user's manual. Included are the FIRIN code description with methods/algorithms of calculation and subroutines, code operating instructions with input requirements, and output descriptions. 40 refs., 5 figs., 31 tabs

  10. FORIG: a computer code for calculating radionuclide generation and depletion in fusion and fission reactors. User's manual

    International Nuclear Information System (INIS)

    Blink, J.A.

    1985-03-01

    In this manual we describe the use of the FORIG computer code to solve isotope-generation and depletion problems in fusion and fission reactors. FORIG runs on a Cray-1 computer and accepts more extensive activation cross sections than ORIGEN2 from which it was adapted. This report is an updated and a combined version of the previous ORIGEN2 and FORIG manuals. 7 refs., 15 figs., 13 tabs

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

    International Nuclear Information System (INIS)

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

    2001-01-01

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

  12. Theoretical background and user's manual for the computer code on groundwater flow and radionuclide transport calculation in porous rock

    International Nuclear Information System (INIS)

    Shirakawa, Toshihiko; Hatanaka, Koichiro

    2001-11-01

    In order to document a basic manual about input data, output data, execution of computer code on groundwater flow and radionuclide transport calculation in heterogeneous porous rock, we investigated the theoretical background about geostatistical computer codes and the user's manual for the computer code on groundwater flow and radionuclide transport which calculates water flow in three dimension, the path of moving radionuclide, and one dimensional radionuclide migration. In this report, based on above investigation we describe the geostatistical background about simulating heterogeneous permeability field. And we describe construction of files, input and output data, a example of calculating of the programs which simulates heterogeneous permeability field, and calculates groundwater flow and radionuclide transport. Therefore, we can document a manual by investigating the theoretical background about geostatistical computer codes and the user's manual for the computer code on groundwater flow and radionuclide transport calculation. And we can model heterogeneous porous rock and analyze groundwater flow and radionuclide transport by utilizing the information from this report. (author)

  13. The 3rd colloquium on process simulation. Proceedings

    Energy Technology Data Exchange (ETDEWEB)

    Jokilaakso, A. [ed.

    1996-12-31

    The presentations collected in this volume were presented at the 3rd Colloquium on Process Simulation held at Helsinki University of Technology, Espoo, Finland, June 12-14, 1996. In the more developed industrial nations, the processes for producing chemicals, energy, and materials encounter environmental concern and laws which challenge engineers to develop the processes towards more efficient, economical and safe operation. This necessitates more thorough understanding of the processes and phenomena involved. Formerly, the development of the processes was largely based on trial and error, whereas today, the development of computer performance together with the diversification of modelling software enables simulation of the processes. The increased capacity and possibilities for modelling the processes brought by the improved hardware and software, have generated a strong demand for more accurate mathematical descriptions of the processes. Especially, the coupling of computational fluid dynamics and chemical kinetics, combustion, and thermodynamics is of current interest in process oriented technology. This colloquium attempts to give examples of modelling efforts in operation in different universities, research institutes and companies. Furthermore, the aim of this colloquium is to offer an annual opportunity to the researchers to come together and discuss their common problems and the state of their investigations

  14. The 3rd colloquium on process simulation. Proceedings

    Energy Technology Data Exchange (ETDEWEB)

    Jokilaakso, A [ed.

    1997-12-31

    The presentations collected in this volume were presented at the 3rd Colloquium on Process Simulation held at Helsinki University of Technology, Espoo, Finland, June 12-14, 1996. In the more developed industrial nations, the processes for producing chemicals, energy, and materials encounter environmental concern and laws which challenge engineers to develop the processes towards more efficient, economical and safe operation. This necessitates more thorough understanding of the processes and phenomena involved. Formerly, the development of the processes was largely based on trial and error, whereas today, the development of computer performance together with the diversification of modelling software enables simulation of the processes. The increased capacity and possibilities for modelling the processes brought by the improved hardware and software, have generated a strong demand for more accurate mathematical descriptions of the processes. Especially, the coupling of computational fluid dynamics and chemical kinetics, combustion, and thermodynamics is of current interest in process oriented technology. This colloquium attempts to give examples of modelling efforts in operation in different universities, research institutes and companies. Furthermore, the aim of this colloquium is to offer an annual opportunity to the researchers to come together and discuss their common problems and the state of their investigations

  15. 3rd Course of the International School of Advanced Geodesy

    CERN Document Server

    Sansò, Fernando

    1985-01-01

    During the period April 25th to May 10th, 1984 the 3rd Course of the International School of Advanced Geodesy entitled "Optimization and Design of Geodetic Networks" took place in Erice. The main subject of the course is clear from the title and consisted mainly of that particular branch of network analysis, which results from applying general concepts of mathematical optimization to the design of geodetic networks. As al­ ways when dealing with optimization problems, there is an a-priori choice of the risk (or gain) function which should be minimized (or maximized) according to the specific interest of the "designer", which might be either of a scientific or of an economic nature or even of both. These aspects have been reviewed in an intro­ ductory lecture in which the particular needs arising in a geodetic context and their analytical representations are examined. Subsequently the main body of the optimization problem, which has been conven­ tionally divided into zero, first, second and third order desi...

  16. Development of the 3rd Generation ECR ion source

    International Nuclear Information System (INIS)

    Lyneis, C.M.; Xie, Z.Q.; Taylor, C.E.

    1997-09-01

    The LBNL 3rd Generation ECR ion source has progressed from a concept to the fabrication of a full scale prototype superconducting magnet structure. This new ECR ion source will combine the recent ECR ion source techniques that significantly enhance the production of high charge state ions. The design includes a plasma chamber made from aluminum to provide additional cold electrons, three separate microwave feeds to allow multiple-frequency plasma heating (at 10, 14 and 18 GHz or at 6, 10 and 14 GHz) and very high magnetic mirror fields. The design calls for mirror fields of 4 T at injection and 3 T at extraction and for a radial field strength at the wall of 2.4 T. The prototype superconducting magnet structure which consists of three solenoid coils and six race track coils with iron poles forming the sextupole has been tested in a vertical dewar. After training, the sextupole magnet reached 105% of its design current with the solenoids off. With the solenoids operating at approximately 70% of their full design field, the sextuple coils operated at 95% of the design value which corresponds to a sextupole field strength at the plasma wall of more than 2.1 T

  17. The 3rd irradiation test plan of DUPIC fuel

    Energy Technology Data Exchange (ETDEWEB)

    Yang, Myung Seung; Song, K. C.; Park, J. H. and others

    2001-05-01

    The objective of the 3rd irradiation test of DUPIC fuel at the HANARO is to estimate the in-core behaviour of a DUPIC pellet that is irradiated up to more than average burnup of CANDU fuel. The irradiation of DUPIC fuel is planned to start at May 21, 2001, and will be continued at least for 8 months. The burnup of DUPIC fuel through this irradiation test is thought to be more than 7,000 MWd/tHE. The DUPIC irradiation rig instrumented with three SPN detectors will be used to accumulate the experience for the instrumented irradiation and to estimate the burnup of irradiated DUPIC fuel more accurately. Under normal operating condition, the maximum linear power of DUPIC fuel was estimated as 55.06 kW/m, and the centerline temperature of a pellet was calculated as 2510 deg C. In order to assess the integrity of DUPIC fuel under the accident condition postulated at the HANARO, safety analyses on the locked rotor and reactivity insertion accidents were carried out. The maximum centerline temperature of DUPIC fuel was estimated 2590 deg C and 2094 deg C for each accident, respectively. From the results of the safety analysis, the integrity of DUPIC fuel during the HANARO irradiation test will be secured. The irradiated DUPIC fuel will be transported to the IMEF. The post-irradiation examinations are planned to be performed at the PIEF and IMEF.

  18. Academic Training: 3rd Term - 01 April - 30 June 2005

    CERN Multimedia

    Françoise Benz

    2005-01-01

    2004 - 2005 ACADEMIC TRAINING PROGRAMME 3rd Term - 01 April - 30 June 2005 REGULAR LECTURE PROGRAMME Monte Carlo generators fot the LHC by T. Sjostrand / CERN-PH 4, 5, 6, 7 April The LHC machine experiment interface by S. Tapprogge / Univ. Gutenberg, Mainz, D R. Assmann, CERN-AB, E. Tsesmelis and D. Macina / CERN-TS 18, 19, 20, 21, 22 April Cosmology for particle physicists by S. Carroll / Univ. of Chicago, USA 9, 10, 11, 12, 13 May The ITER projects: technological challenges by P. Bruzzone / EPFL CRPP, Zürich, CH J. Lister / EPFL CRPP, Lausanne, CH 30, 31 May, 1, 2, 3 June String theory by C. Johnson / Univ. of Southern California, USA 6, 7, 8, 9, 10 June Small may be beautiful By M. Davier / LAL, Orsay, F. T. Soldner / ILL, Grenoble, F. 13, 14, 15, 16, 17 June Climate change and challenges for the environment by C. Schluchter / Univ. Bern. CH 20, 21, 22 June LECTURE SERIES FOR POSTGRADUATE STUDENTS Particle detectors - principles and techniques by C. Joram, L. Ropelewski, M. Moll, C. ...

  19. 3rd CEAS Specialist Conference on Guidance, Navigation and Control

    CERN Document Server

    Drouin, Antoine; Roos, Clément

    2015-01-01

    The two first CEAS (Council of European Aerospace Societies) Specialist Conferences on Guidance, Navigation and Control (CEAS EuroGNC) were held in Munich, Germany in 2011 and in Delft, The Netherlands in 2013. ONERA The French Aerospace Lab, ISAE (Institut Supérieur de l’Aéronautique et de l’Espace) and ENAC (Ecole Nationale de l’Aviation Civile) accepted the challenge of jointly organizing the 3rd edition. The conference aims at promoting new advances in aerospace GNC theory and technologies for enhancing safety, survivability, efficiency, performance, autonomy and intelligence of aerospace systems. It represents a unique forum for communication and information exchange between specialists in the fields of GNC systems design and operation, including air traffic management. This book contains the forty best papers and gives an interesting snapshot of the latest advances over the following topics: l  Control theory, analysis, and design l  Novel navigation, estimation, and tracking methods l  Aircr...

  20. Prophyrin identification by 3rd derivative UV/VIS spectroscopy

    International Nuclear Information System (INIS)

    Freeman, D.H.; Saint Martin, D.C.; Boreham, C.J.

    1992-01-01

    This patent describes the Soret band wavelength of nickel and vanadyl porphyrins λ Soret, which identifies etic DPEP/di-DPEP, propano and butano structure types. The approach is based upon routine diode array uv/vis spectra taken to their 3rd derivative. an interpolated zero crossing gives λ max within 0.1 nm. Accordingly, reference spectral properties of 27 well characterized metalloporphyrins were determined. When λSoret, λα and λβ and molecular mass data were combined, each of the DPEP and di-DPEP nickel complexes were distinct. In addition, λSoret was able to classify nickel etioporphyrins according to the number of beta hydrogens. To illustrate the many possible applications, two substances were isolated by HPLC from a Messel Shale extract based on known HPLC C18 retentions. Comparison of wavelength and mass between isolated and reference counterparts showed precise agreement. Thus uv/vic spectroscopy helps to classify porphyrin structure, and to facilitate identification by matching to reference data

  1. Four-D propagation code for high-energy laser beams: a user's manual

    Energy Technology Data Exchange (ETDEWEB)

    Morris, J.R.

    1976-08-05

    This manual describes the use and structure of the June 30, 1976 version of the Four-D propagation code for high energy laser beams. It provides selected sample output from a typical run and from several debug runs. The Four-D code now includes the important noncoplanar scenario feature. Many problems that required excessive computer time can now be meaningfully simulated as steady-state noncoplanar problems with short run times.

  2. ELCOS: the PSI code system for LWR core analysis. Part II: user`s manual for the fuel assembly code BOXER

    Energy Technology Data Exchange (ETDEWEB)

    Paratte, J.M.; Grimm, P.; Hollard, J.M. [Paul Scherrer Inst. (PSI), Villigen (Switzerland)

    1996-02-01

    ELCOS is a flexible code system for the stationary simulation of light water reactor cores. It consists of the four computer codes ETOBOX, BOXER, CORCOD and SILWER. The user`s manual of the second one is presented here. BOXER calculates the neutronics in cartesian geometry. The code can roughly be divided into four stages: - organisation: choice of the modules, file manipulations, reading and checking of input data, - fine group fluxes and condensation: one-dimensional calculation of fluxes and computation of the group constants of homogeneous materials and cells, - two-dimensional calculations: geometrically detailed simulation of the configuration in few energy groups, - burnup: evolution of the nuclide densities as a function of time. This manual shows all input commands which can be used while running the different modules of BOXER. (author) figs., tabs., refs.

  3. Test Methods for Evaluating Solid Waste, Physical/Chemical Methods. First Update. (3rd edition)

    International Nuclear Information System (INIS)

    Friedman; Sellers.

    1988-01-01

    The proposed Update is for Test Methods for Evaluating Solid Waste, Physical/Chemical Methods, SW-846, Third Edition. Attached to the report is a list of methods included in the proposed update indicating whether the method is a new method, a partially revised method, or a totally revised method. Do not discard or replace any of the current pages in the SW-846 manual until the proposed update I package is promulgated. Until promulgation of the update package, the methods in the update package are not officially part of the SW-846 manual and thus do not carry the status of EPA-approved methods. In addition to the proposed Update, six finalized methods are included for immediate inclusion into the Third Edition of SW-846. Four methods, originally proposed October 1, 1984, will be finalized in a soon to be released rulemaking. They are, however, being submitted to subscribers for the first time in the update. These methods are 7211, 7381, 7461, and 7951. Two other methods were finalized in the 2nd Edition of SW-846. They were inadvertantly omitted from the 3rd Edition and are not being proposed as new. These methods are 7081 and 7761

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

    International Nuclear Information System (INIS)

    Ahnert, C.; Aragones, J. M.

    1981-01-01

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

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

    International Nuclear Information System (INIS)

    Ahnert, C.; Aragones, J.M.

    1981-01-01

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

  6. Manual versus automated coding of free-text self-reported medication data in the 45 and Up Study: a validation study.

    Science.gov (United States)

    Gnjidic, Danijela; Pearson, Sallie-Anne; Hilmer, Sarah N; Basilakis, Jim; Schaffer, Andrea L; Blyth, Fiona M; Banks, Emily

    2015-03-30

    Increasingly, automated methods are being used to code free-text medication data, but evidence on the validity of these methods is limited. To examine the accuracy of automated coding of previously keyed in free-text medication data compared with manual coding of original handwritten free-text responses (the 'gold standard'). A random sample of 500 participants (475 with and 25 without medication data in the free-text box) enrolled in the 45 and Up Study was selected. Manual coding involved medication experts keying in free-text responses and coding using Anatomical Therapeutic Chemical (ATC) codes (i.e. chemical substance 7-digit level; chemical subgroup 5-digit; pharmacological subgroup 4-digit; therapeutic subgroup 3-digit). Using keyed-in free-text responses entered by non-experts, the automated approach coded entries using the Australian Medicines Terminology database and assigned corresponding ATC codes. Based on manual coding, 1377 free-text entries were recorded and, of these, 1282 medications were coded to ATCs manually. The sensitivity of automated coding compared with manual coding was 79% (n = 1014) for entries coded at the exact ATC level, and 81.6% (n = 1046), 83.0% (n = 1064) and 83.8% (n = 1074) at the 5, 4 and 3-digit ATC levels, respectively. The sensitivity of automated coding for blank responses was 100% compared with manual coding. Sensitivity of automated coding was highest for prescription medications and lowest for vitamins and supplements, compared with the manual approach. Positive predictive values for automated coding were above 95% for 34 of the 38 individual prescription medications examined. Automated coding for free-text prescription medication data shows very high to excellent sensitivity and positive predictive values, indicating that automated methods can potentially be useful for large-scale, medication-related research.

  7. PREFACE: 3rd International Symposium ''Optics and its Applications''

    Science.gov (United States)

    Calvo, M. L.; Dolganova, I. N.; Gevorgyan, N.; Guzman, A.; Papoyan, A.; Sarkisyan, H.; Yurchenko, S.

    2016-01-01

    The SPIE.FOCUS Armenia: 3rd International Symposium ''Optics and its Applications'' (OPTICS-2015) http://rau.am/optics2015/ was held in Yerevan, Armenia, in the period October 1 - 5, 2015. The symposium was organized by the International Society for Optics and Photonics (SPIE), the Armenian SPIE student chapter with collaboration of the Armenian TC of ICO, the Russian-Armenian University (RAU), the Institute for Physical Research of National Academy of Sciences of Armenia (IPR of NAS), the Greek-Armenian industrial company LT-PYRKAL, and the Yerevan State University (YSU). The Symposium was co-organized by the SPIE & OSA student chapters of BMSTU, the Armenian OSA student chapter, and the SPIE student chapters of Lund University and Wroclaw University of Technology. The symposium OPTICS-2015 was dedicated to the International Year of Light and Light-Based Technologies. OPTICS-2015 was devoted to modern topics and optical technologies such as: optical properties of nanostructures, silicon photonics, quantum optics, singular optics & its applications, laser spectroscopy, strong field optics, biomedical optics, nonlinear & ultrafast optics, photonics & fiber optics, and mathematical methods in optics. OPTICS-2015 was attended by 100 scientists and students representing 17 countries: Armenia, China, Czech Republic, France, Georgia, Germany, India, Iran, Italy, Latvia, Mexico, Poland, Russia, Saudi Arabia, Sweden, Ukraine, and USA. Such a broad international community confirmed the important mission of science to be a uniting force between different countries, religions, and nations. We hope that OPTICS-2015 inspired and motivated students and young scientists to work in optics and in science in general. The present volume of Journal of Physics: Conference Series includes proceedings of the symposium covering various aspects of modern problems in optics. We are grateful to all people who were involved in the organization process. We gratefully acknowledge support from

  8. Reading Improvement through Art Replicator Manual of Instruction, 3rd Edition

    Science.gov (United States)

    Corwin, Sylvia K., Ed.

    2013-01-01

    Reading Improvement Through Art (RITA) program is an interdisciplinary approach to literacy that blends visual art with reading comprehension, evaluated in nine New York City urban high schools. 240 problem readers participating in the pilot program were pre- and post-tested in the Fall 1975 and Spring 1976 semesters. The testing showed the 9th…

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1997-11-01

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

  10. JEMs and incompatible occupational coding systems: Effect of manual and automatic recoding of job codes on exposure assignment

    NARCIS (Netherlands)

    Koeman, T.; Offermans, N.S.M.; Christopher-De Vries, Y.; Slottje, P.; Brandt, P.A. van den; Goldbohm, R.A.; Kromhout, H.; Vermeulen, R.

    2013-01-01

    Background: In epidemiological studies, occupational exposure estimates are often assigned through linkage of job histories to job-exposure matrices (JEMs). However, available JEMs may have a coding system incompatible with the coding system used to code the job histories, necessitating a

  11. SCDAP/RELAP5/MOD 3.1 code manual: User's guide and input manual. Volume 3

    International Nuclear Information System (INIS)

    Coryell, E.W.; Johnsen, E.C.; Allison, C.M.

    1995-06-01

    The SCDAP/RELAP5 code has been developed for best estimate transient simulation of light water reactor coolant systems during a severe accident. The code models the coupled behavior of the reactor coolant system, core, fission product released during a severe accident transient as well as large and small break loss of coolant accidents, operational transients such as anticipated transient without SCRAM, loss of offsite power, loss of feedwater, and loss of flow. A generic modeling approach is used that permits as much of a particular system to be modeled as necessary. Control system and secondary system components are included to permit modeling of plant controls, turbines, condensers, and secondary feedwater conditioning systems. This volume provides guidelines to code users based upon lessons learned during the developmental assessment process. A description of problem control and the installation process is included. Appendix a contains the description of the input requirements

  12. RELAP5/MOD3 code manual: Summaries and reviews of independent code assessment reports. Volume 7, Revision 1

    International Nuclear Information System (INIS)

    Moore, R.L.; Sloan, S.M.; Schultz, R.R.; Wilson, G.E.

    1996-10-01

    Summaries of RELAP5/MOD3 code assessments, a listing of the assessment matrix, and a chronology of the various versions of the code are given. Results from these code assessments have been used to formulate a compilation of some of the strengths and weaknesses of the code. These results are documented in the report. Volume 7 was designed to be updated periodically and to include the results of the latest code assessments as they become available. Consequently, users of Volume 7 should ensure that they have the latest revision available

  13. PREFACE: 3rd International Congress on Ceramics (ICC3)

    Science.gov (United States)

    Niihara, Koichi; Ohji, Tatsuki; Sakka, Yoshio

    2011-10-01

    Early in 2005, the American Ceramic Society, the European Ceramic Society and the Ceramic Society of Japan announced a collaborative effort to provide leadership for the global ceramics community that would facilitate the use of ceramic and glass materials. That effort resulted in an agreement to organize a new biennial series of the International Congress on Ceramics, convened by the International Ceramic Federation (ICF). In order to share ideas and visions of the future for ceramic and glass materials, the 1st International Congress on Ceramics (ICC1) was held in Canada, 2006, under the organization of the American Ceramic Society, and the 2nd Congress (ICC2) was held in Italy, 2008, hosted by the European Ceramic Society. Organized by the Ceramic Society of Japan, the 3rd Congress (ICC3) was held in Osaka, Japan, 14-18 November 2010. Incorporating the 23rd Fall Meeting of the Ceramic Society of Japan and the 20th Iketani Conference, ICC3 was also co-organized by the Iketani Science and Technology Foundation, and was endorsed and supported by ICF, Asia-Oceania Ceramic Federation (AOCF) as well as many other organizations. Following the style of the previous two successful Congresses, the program was designed to advance ceramic and glass technologies to the next generation through discussion of the most recent advances and future perspectives, and to engage the worldwide ceramics community in a collective effort to expand the use of these materials in both conventional as well as new and exciting applications. ICC3 consisted of 22 voluntarily organized symposia in the most topical and essential themes of ceramic and glass materials, including Characterization, design and processing technologies Electro, magnetic and optical ceramics and devices Energy and environment related ceramics and systems Bio-ceramics and bio-technologies Ceramics for advanced industry and safety society Innovation in traditional ceramics It also contained the Plenary Session and the

  14. GENII (Generation II): The Hanford Environmental Radiation Dosimetry Software System: Volume 3, Code maintenance manual: Hanford Environmental Dosimetry Upgrade Project

    Energy Technology Data Exchange (ETDEWEB)

    Napier, B.A.; Peloquin, R.A.; Strenge, D.L.; Ramsdell, J.V.

    1988-09-01

    The Hanford Environmental Dosimetry Upgrade Project was undertaken to incorporate the internal dosimetry models recommended by the International Commission on Radiological Protection (ICRP) in updated versions of the environmental pathway analysis models used at Hanford. The resulting second generation of Hanford environmental dosimetry computer codes is compiled in the Hanford Environmental Dosimetry System (Generation II, or GENII). This coupled system of computer codes is intended for analysis of environmental contamination resulting from acute or chronic releases to, or initial contamination of, air, water, or soil, on through the calculation of radiation doses to individuals or populations. GENII is described in three volumes of documentation. This volume is a Code Maintenance Manual for the serious user, including code logic diagrams, global dictionary, worksheets to assist with hand calculations, and listings of the code and its associated data libraries. The first volume describes the theoretical considerations of the system. The second volume is a Users' Manual, providing code structure, users' instructions, required system configurations, and QA-related topics. 7 figs., 5 tabs.

  15. GENII [Generation II]: The Hanford Environmental Radiation Dosimetry Software System: Volume 3, Code maintenance manual: Hanford Environmental Dosimetry Upgrade Project

    International Nuclear Information System (INIS)

    Napier, B.A.; Peloquin, R.A.; Strenge, D.L.; Ramsdell, J.V.

    1988-09-01

    The Hanford Environmental Dosimetry Upgrade Project was undertaken to incorporate the internal dosimetry models recommended by the International Commission on Radiological Protection (ICRP) in updated versions of the environmental pathway analysis models used at Hanford. The resulting second generation of Hanford environmental dosimetry computer codes is compiled in the Hanford Environmental Dosimetry System (Generation II, or GENII). This coupled system of computer codes is intended for analysis of environmental contamination resulting from acute or chronic releases to, or initial contamination of, air, water, or soil, on through the calculation of radiation doses to individuals or populations. GENII is described in three volumes of documentation. This volume is a Code Maintenance Manual for the serious user, including code logic diagrams, global dictionary, worksheets to assist with hand calculations, and listings of the code and its associated data libraries. The first volume describes the theoretical considerations of the system. The second volume is a Users' Manual, providing code structure, users' instructions, required system configurations, and QA-related topics. 7 figs., 5 tabs

  16. 3rd International Workshop on Critical Systems Development with UML

    OpenAIRE

    Jan Jürjens; Eduardo B. Fernandez; Robert France; Bernhard Rumpe

    2017-01-01

    Topics of the Workshop include: --- Applications of UML to real-time systems security-critical systems dependable / safety-critical systems performance-critical systems embedded systems hybrid systems reactive systems --- Extensions of UML (UML-RT, UMLsec, Automotive UML, Embedded UML, ...) and new developments (UML 2.0, MDA) --- Modeling, synthesis, model transformation, code generation, testing, validation, and verification of critical systems using UML --- Aspect-oriented or Component-base...

  17. Data of evolutionary structure change: 1ONAD-2D3RD [Confc[Archive

    Lifescience Database Archive (English)

    Full Text Available 1ONAD-2D3RD 1ONA 2D3R D D ADTIVAVELDTYPNTDIGDPSYPHIGIDIKSVRSKKTAK...WNMQNGKVGTAHIIYNSVDKRLSAVVSYPNADSATVSYDVDLDNVLPEWVRVGLSASTGLYKETNTILSWSFTSKLK------TNALHFMFNQFSKDQKDLILQGDAT...n> 1ONA D 1ONAD TRVS

  18. 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)

  19. VIPRE-01: a thermal-hydraulic analysis code for reactor cores. Volume 3. Programmer's manual. Final report

    International Nuclear Information System (INIS)

    Stewart, C.W.; Koontz, A.S.; Cuta, J.M.; Montgomery, S.D.

    1983-05-01

    VIPRE (Versatile Internals and Component Program for Reactors; EPRI) has been developed for nuclear power utility thermal-hydraulic analysis applications. It is designed to help evaluate nuclear-reactor-core safety limits including minimum departure from nucleate boiling ratio (MDNBR), critical power ratio (CPR), fuel and clad temperatures, and coolant state in normal operation and assumed accident conditions. This is Volume 3, the Programmer's Manual. It explains the codes' structures and the computer interfaces

  20. BIGIF: fracture mechanics code for structures. Manual 1: introduction and theoretical background

    International Nuclear Information System (INIS)

    Besuner, P.M.; Rau, S.A.; Davis, C.S.; Rogers, G.W.; Grover, J.L.; Peters, D.C.

    1981-04-01

    This report is a general description manual documenting the current version of BIGIF, a computer program designed to calculate cracked growth in a flawed structure. The first of three, this manual provides a general understanding of the program's present capabilities and includes enough information to decide whether or not to use BIGIF

  1. Chondromyxoid fibroma of distal 1/3 rd of fibula a rare tumour at rare ...

    African Journals Online (AJOL)

    Chondromyxoid fibromas are rare, benign tumours account for <1% of primary bone neoplasms. Most commonly affected in 2nd and 3rdof life. We report one such case of chondromyxoid fibroma in distal fibula of a 15-year-old girl. The patient was managed with lower 3rd fibulectomy and fibular turnoplasty from middle 3rd ...

  2. Exercises in statistics for HA & HA(dat.) & BSc(B), 3rd semester

    DEFF Research Database (Denmark)

    The booklet contains excercises to be used for the tutorials related to the 3rd semester course in statistics on the bachelors progarmme at the Aarhus School of Business.......The booklet contains excercises to be used for the tutorials related to the 3rd semester course in statistics on the bachelors progarmme at the Aarhus School of Business....

  3. RAMONA-4B a computer code with three-dimensional neutron kinetics for BWR and SBWR system transient - user's manual

    International Nuclear Information System (INIS)

    Rohatgi, U.S.; Cheng, H.S.; Khan, H.J.; Mallen, A.N.; Neymotin, L.Y.

    1998-03-01

    This document is the User's Manual for the Boiling Water Reactor (BWR), and Simplified Boiling Water Reactor (SBWR) systems transient code RAMONA-4B. The code uses a three-dimensional neutron-kinetics model coupled with a multichannel, nonequilibrium, drift-flux, phase-flow model of the thermal hydraulics of the reactor vessel. The code is designed to analyze a wide spectrum of BWR core and system transients. Chapter 1 gives an overview of the code's capabilities and limitations; Chapter 2 describes the code's structure, lists major subroutines, and discusses the computer requirements. Chapter 3 is on code, auxillary codes, and instructions for running RAMONA-4B on Sun SPARC and IBM Workstations. Chapter 4 contains component descriptions and detailed card-by-card input instructions. Chapter 5 provides samples of the tabulated output for the steady-state and transient calculations and discusses the plotting procedures for the steady-state and transient calculations. Three appendices contain important user and programmer information: lists of plot variables (Appendix A) listings of input deck for sample problem (Appendix B), and a description of the plotting program PAD (Appendix C). 24 refs., 18 figs., 11 tabs

  4. A User's Manual for MASH V1.5 - A Monte Carlo Adjoint Shielding Code System

    Energy Technology Data Exchange (ETDEWEB)

    C. O. Slater; J. M. Barnes; J. O. Johnson; J.D. Drischler

    1998-10-01

    The Monte Carlo ~djoint ~ielding Code System, MASH, calculates neutron and gamma- ray environments and radiation protection factors for armored military vehicles, structures, trenches, and other shielding configurations by coupling a forward discrete ordinates air- over-ground transport calculation with an adjoint Monte Carlo treatment of the shielding geometry. Efficiency and optimum use of computer time are emphasized. The code system includes the GRTUNCL and DORT codes for air-over-ground transport calculations, the MORSE code with the GIFT5 combinatorial geometry package for adjoint shielding calculations, and several peripheral codes that perform the required data preparations, transformations, and coupling functions. The current version, MASH v 1.5, is the successor to the original MASH v 1.0 code system initially developed at Oak Ridge National Laboratory (ORNL). The discrete ordinates calculation determines the fluence on a coupling surface surrounding the shielding geometry due to an external neutron/gamma-ray source. The Monte Carlo calculation determines the effectiveness of the fluence at that surface in causing a response in a detector within the shielding geometry, i.e., the "dose importance" of the coupling surface fluence. A coupling code folds the fluence together with the dose importance, giving the desired dose response. The coupling code can determine the dose response as a function of the shielding geometry orientation relative to the source, distance from the source, and energy response of the detector. This user's manual includes a short description of each code, the input required to execute the code along with some helpful input data notes, and a representative sample problem.

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

    International Nuclear Information System (INIS)

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

    2000-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2000-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2000-07-01

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

  8. Book of abstracts of the 3rd International conference and the 3rd International School for young scientists Interaction of hydrogen isotopes with structural materials. IHISM-07

    International Nuclear Information System (INIS)

    2007-01-01

    The book involves abstracts of presentations at the 3rd International Conference and the 3rd International School for Young Scientists Interaction of Hydrogen Isotopes with Structural Materials (IHISM-07). The activities of Russian and foreign scientific centers associated with the use of hydrogen isotopes in power engineering, national economy and basic research are considered. The presentations cover the following areas: kinetics and interaction between hydrogen isotopes and solids including effects of radiogenic helium accumulation, hydrides and hydride transformations; structural transformations and mechanical properties; equipment and research techniques [ru

  9. Electrical safety code manual a plan language guide to national electrical code, OSHA and NFPA 70E

    CERN Document Server

    Keller, Kimberley

    2010-01-01

    Safety in any workplace is extremely important. In the case of the electrical industry, safety is critical and the codes and regulations which determine safe practices are both diverse and complicated. Employers, electricians, electrical system designers, inspectors, engineers and architects must comply with safety standards listed in the National Electrical Code, OSHA and NFPA 70E. Unfortunately, the publications which list these safety requirements are written in very technically advanced terms and the average person has an extremely difficult time understanding exactly what they need to

  10. JASMINE-pro: A computer code for the analysis of propagation process in steam explosions. User's manual

    Energy Technology Data Exchange (ETDEWEB)

    Yang, Yanhua; Nilsuwankosit, Sunchai; Moriyama, Kiyofumi; Maruyama, Yu; Nakamura, Hideo; Hashimoto, Kazuichiro [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2000-12-01

    A steam explosion is a phenomenon where a high temperature liquid gives its internal energy very rapidly to another low temperature volatile liquid, causing very strong pressure build up due to rapid vaporization of the latter. In the field of light water reactor safety research, steam explosions caused by the contact of molten core and coolant has been recognized as a potential threat which could cause failure of the pressure vessel or the containment vessel during a severe accident. A numerical simulation code JASMINE was developed at Japan Atomic Energy Research Institute (JAERI) to evaluate the impact of steam explosions on the integrity of reactor boundaries. JASMINE code consists of two parts, JASMINE-pre and -pro, which handle the premixing and propagation phases in steam explosions, respectively. JASMINE-pro code simulates the thermo-hydrodynamics in the propagation phase of a steam explosion on the basis of the multi-fluid model for multiphase flow. This report, 'User's Manual', gives the usage of JASMINE-pro code as well as the information on the code structures which should be useful for users to understand how the code works. (author)

  11. JASMINE-pro: A computer code for the analysis of propagation process in steam explosions. User's manual

    International Nuclear Information System (INIS)

    Yang, Yanhua; Nilsuwankosit, Sunchai; Moriyama, Kiyofumi; Maruyama, Yu; Nakamura, Hideo; Hashimoto, Kazuichiro

    2000-12-01

    A steam explosion is a phenomenon where a high temperature liquid gives its internal energy very rapidly to another low temperature volatile liquid, causing very strong pressure build up due to rapid vaporization of the latter. In the field of light water reactor safety research, steam explosions caused by the contact of molten core and coolant has been recognized as a potential threat which could cause failure of the pressure vessel or the containment vessel during a severe accident. A numerical simulation code JASMINE was developed at Japan Atomic Energy Research Institute (JAERI) to evaluate the impact of steam explosions on the integrity of reactor boundaries. JASMINE code consists of two parts, JASMINE-pre and -pro, which handle the premixing and propagation phases in steam explosions, respectively. JASMINE-pro code simulates the thermo-hydrodynamics in the propagation phase of a steam explosion on the basis of the multi-fluid model for multiphase flow. This report, 'User's Manual', gives the usage of JASMINE-pro code as well as the information on the code structures which should be useful for users to understand how the code works. (author)

  12. The 3rd ATLAS Domestic Standard Problem for Improvement of Safety Analysis Technology

    International Nuclear Information System (INIS)

    Choi, Ki-Yong; Kang, Kyoung-Ho; Park, Yusun; Kim, Jongrok; Bae, Byoung-Uhn; Choi, Nam-Hyun

    2014-01-01

    The third ATLAS DSP (domestic standard problem exercise) was launched at the end of 2012 in response to the strong need for continuation of the ATLAS DSP. A guillotine break of a main steam line without LOOP at a zero power condition was selected as a target scenario, and it was successfully completed in the beginning of 2014. In the 3 rd ATLAS DSP, comprehensive utilization of the integral effect test data was made by dividing analysis with three topics; 1. scale-up where extrapolation of ATLAS IET data was investigated 2. 3D analysis where how much improvement can be obtained by 3D modeling was studied 3. 1D sensitivity analysis where the key phenomena affecting the SLB simulation were identified and the best modeling guideline was achieved. Through such DSP exercises, it has been possible to effectively utilize high-quality ATLAS experimental data of to enhance thermal-hydraulic understanding and to validate the safety analysis codes. A strong human network and technical expertise sharing among the various nuclear experts are also important outcomes from this program

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

    International Nuclear Information System (INIS)

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

    1995-03-01

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

  14. GASFLOW: A Computational Fluid Dynamics Code for Gases, Aerosols, and Combustion, Volume 2: User's Manual

    Energy Technology Data Exchange (ETDEWEB)

    Nichols, B. D.; Mueller, C.; Necker, G. A.; Travis, J. R.; Spore, J. W.; Lam, K. L.; Royl, P.; Wilson, T. L.

    1998-10-01

    Los Alamos National Laboratory (LANL) and Forschungszentrum Karlsruhe (FzK) are developing GASFLOW, a three-dimensional (3D) fluid dynamics field code as a best-estimate tool to characterize local phenomena within a flow field. Examples of 3D phenomena include circulation patterns; flow stratification; hydrogen distribution mixing and stratification; combustion and flame propagation; effects of noncondensable gas distribution on local condensation and evaporation; and aerosol entrainment, transport, and deposition. An analysis with GASFLOW will result in a prediction of the gas composition and discrete particle distribution in space and time throughout the facility and the resulting pressure and temperature loadings on the walls and internal structures with or without combustion. A major application of GASFLOW is for predicting the transport, mixing, and combustion of hydrogen and other gases in nuclear reactor containment and other facilities. It has been applied to situations involving transporting and distributing combustible gas mixtures. It has been used to study gas dynamic behavior in low-speed, buoyancy-driven flows, as well as sonic flows or diffusion dominated flows; and during chemically reacting flows, including deflagrations. The effects of controlling such mixtures by safety systems can be analyzed. The code version described in this manual is designated GASFLOW 2.1, which combines previous versions of the United States Nuclear Regulatory Commission code HMS (for Hydrogen Mixing Studies) and the Department of Energy and FzK versions of GASFLOW. The code was written in standard Fortran 90. This manual comprises three volumes. Volume I describes the governing physical equations and computational model. Volume II describes how to use the code to set up a model geometry, specify gas species and material properties, define initial and boundary conditions, and specify different outputs, especially graphical displays. Sample problems are included. Volume III

  15. User's manual for the G.T.M.-1 computer code

    International Nuclear Information System (INIS)

    Prado-Herrero, P.

    1992-01-01

    This document describes the GTM-1 ( Geosphere Transport Model, release-1) computer code and is intended to provide the reader with enough detailed information in order to use the code. GTM-1 was developed for the assessment of radionuclide migration by the ground water through geologic deposits whose properties can change along the pathway.GTM-1 solves the transport equation by the finite differences method ( Crank-Nicolson scheme ). It was developped for specific use within Probabilistic System Assessment (PSA) Monte Carlo Method codes; in this context the first application of GTM-1 was within the LISA (Long Term Isolation System Assessment) code. GTM-1 is also available as an independent model, which includes various submodels simulating a multi-barrier disposal system. The code has been tested with the PSACOIN ( Probabilistic System Assessment Codes intercomparison) benchmarks exercises from PSAC User Group (OECD/NEA). 10 refs., 6 Annex., 2 tabs

  16. User manual for semi-circular compact range reflector code: Version 2

    Science.gov (United States)

    Gupta, Inder J.; Burnside, Walter D.

    1987-01-01

    A computer code has been developed at the Ohio State University ElectroScience Laboratory to analyze a semi-circular paraboloidal reflector with or without a rolled edge at the top and a skirt at the bottom. The code can be used to compute the total near field of the reflector or its individual components at a given distance from the center of the paraboloid. The code computes the fields along a radial, horizontal, vertical or axial cut at that distance. Thus, it is very effective in computing the size of the sweet spot for a semi-circular compact range reflector. This report describes the operation of the code. Various input and output statements are explained. Some results obtained using the computer code are presented to illustrate the code's capability as well as being samples of input/output sets.

  17. The MELTSPREAD Code for Modeling of Ex-Vessel Core Debris Spreading Behavior, Code Manual – Version3-beta

    Energy Technology Data Exchange (ETDEWEB)

    Farmer, M. T. [Argonne National Lab. (ANL), Argonne, IL (United States)

    2017-09-01

    MELTSPREAD3 is a transient one-dimensional computer code that has been developed to predict the gravity-driven flow and freezing behavior of molten reactor core materials (corium) in containment geometries. Predictions can be made for corium flowing across surfaces under either dry or wet cavity conditions. The spreading surfaces that can be selected are steel, concrete, a user-specified material (e.g., a ceramic), or an arbitrary combination thereof. The corium can have a wide range of compositions of reactor core materials that includes distinct oxide phases (predominantly Zr, and steel oxides) plus metallic phases (predominantly Zr and steel). The code requires input that describes the containment geometry, melt “pour” conditions, and cavity atmospheric conditions (i.e., pressure, temperature, and cavity flooding information). For cases in which the cavity contains a preexisting water layer at the time of RPV failure, melt jet breakup and particle bed formation can be calculated mechanistically given the time-dependent melt pour conditions (input data) as well as the heatup and boiloff of water in the melt impingement zone (calculated). For core debris impacting either the containment floor or previously spread material, the code calculates the transient hydrodynamics and heat transfer which determine the spreading and freezing behavior of the melt. The code predicts conditions at the end of the spreading stage, including melt relocation distance, depth and material composition profiles, substrate ablation profile, and wall heatup. Code output can be used as input to other models such as CORQUENCH that evaluate long term core-concrete interaction behavior following the transient spreading stage. MELTSPREAD3 was originally developed to investigate BWR Mark I liner vulnerability, but has been substantially upgraded and applied to other reactor designs (e.g., the EPR), and more recently to the plant accidents at Fukushima Daiichi. The most recent round of

  18. User's manual for the code STAPRE as implemented at Lawrence Livermore National Laboratory

    International Nuclear Information System (INIS)

    Vonach, H.

    1982-01-01

    This report gives a detailed description of the input and output of the statistical model code STAPRE for compound-nucleus reactions including a special section on the various level density options of the code. It is to be used in conjunction with the report IRK 76/01 + Add 76 + Add 78 by B. Strohmaier and M. Uhl which describes in detail the physical models on which the code is based and its general organization and structure

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

    International Nuclear Information System (INIS)

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

    2003-01-01

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

  20. Operation results of 3-rd generation nuclear fuel WWER-440 in initial period

    International Nuclear Information System (INIS)

    Adeev, V.; Panov, A.

    2011-01-01

    On unit 4 of Kola NPP trial operation of 3-rd generation's fuel began in 2010. Fuel assemblies of 3-rd generation (FA-3) have a number of design features that provide better operational characteristics. Concise description of a design and the basic advantages of fuel of 3-rd generation are described in articles. Increasing of efficiency of nuclear fuel usage will be achieved by reduction of the parasitic capture of thermal neutrons in constructional materials (weight of zirconium is reduced), optimization of uranium-water relation (increase in fuel elements step), increasing of uranium loading (usage of fuel pellets with increased diameter and without central hole in them). By results of trial operation mass transition to use of given type of assemblies in WWER-440 is possible. This report presents the basic outcomes of the trial operation, a brief survey of the obtained data. The basic characteristics of the reactor core with fuel of 3-rd generation are resulted in work. (authors)

  1. VIPRE-01: a thermal-hydraulic code for reactor cores. Volume 2: user's manual (Revision 2)

    International Nuclear Information System (INIS)

    Cuta, J.M.; Koontz, A.S.; Stewart, C.W.; Montgomery, S.D.; Nomura, K.K.

    1985-07-01

    Revisions to the VIPRE code documents for Volume 2 are presented. These revisions conform to the changes made to VIPRE-01, CYCLE-00 to produce the new version of the code denoted by VIPRE-01, CYCLE-01. The first pages of the revisions specify where the replacement pages are to be inserted and which pages of the original documents should be retained

  2. User's manual for the BNW-II optimization code for dry/wet-cooled power plants

    Energy Technology Data Exchange (ETDEWEB)

    Braun, D.J.; Bamberger, J.A.; Braun, D.J.; Faletti, D.W.; Wiles, L.E.

    1978-05-01

    The User's Manual describes how to operate BNW-II, a computer code developed by the Pacific Northwest Laboratory (PNL) as a part of its activities under the Department of Energy (DOE) Dry Cooling Enhancement Program. The computer program offers a comprehensive method of evaluating the cost savings potential of dry/wet-cooled heat rejection systems. Going beyond simple ''figure-of-merit'' cooling tower optimization, this method includes such items as the cost of annual replacement capacity, and the optimum split between plant scale-up and replacement capacity, as well as the purchase and operating costs of all major heat rejection components. Hence the BNW-II code is a useful tool for determining potential cost savings of new dry/wet surfaces, new piping, or other components as part of an optimized system for a dry/wet-cooled plant.

  3. Multiple-canister flow and transport code in 2-dimensional space. MCFT2D: user's manual

    International Nuclear Information System (INIS)

    Lim, Doo-Hyun

    2006-03-01

    A two-dimensional numerical code, MCFT2D (Multiple-Canister Flow and Transport code in 2-Dimensional space), has been developed for groundwater flow and radionuclide transport analyses in a water-saturated high-level radioactive waste (HLW) repository with multiple canisters. A multiple-canister configuration and a non-uniform flow field of the host rock are incorporated in the MCFT2D code. Effects of heterogeneous flow field of the host rock on migration of nuclides can be investigated using MCFT2D. The MCFT2D enables to take into account the various degrees of the dependency of canister configuration for nuclide migration in a water-saturated HLW repository, while the dependency was assumed to be either independent or perfectly dependent in previous studies. This report presents features of the MCFT2D code, numerical simulation using MCFT2D code, and graphical representation of the numerical results. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1998-06-01

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

  5. RELAP5/MOD3 code manual: User's guide and input requirements. Volume 2

    International Nuclear Information System (INIS)

    1995-08-01

    The RELAP5 code has been developed for best estimate transient simulation of light water reactor coolant systems during postulated accidents. The code models the coupled behavior of the reactor coolant system and the core for loss-of-coolant accidents, and operational transients, such as anticipated transient without scram, loss of offsite power, loss of feedwater, and loss of flow. A generic modeling approach is used that permits simulating a variety of thermal hydraulic systems. Control system and secondary system components are included to permit modeling of plant controls, turbines, condensers, and secondary feedwater systems. Volume II contains detailed instructions for code application and input data preparation

  6. A theory manual for multi-physics code coupling in LIME.

    Energy Technology Data Exchange (ETDEWEB)

    Belcourt, Noel; Bartlett, Roscoe Ainsworth; Pawlowski, Roger Patrick; Schmidt, Rodney Cannon; Hooper, Russell Warren

    2011-03-01

    The Lightweight Integrating Multi-physics Environment (LIME) is a software package for creating multi-physics simulation codes. Its primary application space is when computer codes are currently available to solve different parts of a multi-physics problem and now need to be coupled with other such codes. In this report we define a common domain language for discussing multi-physics coupling and describe the basic theory associated with multiphysics coupling algorithms that are to be supported in LIME. We provide an assessment of coupling techniques for both steady-state and time dependent coupled systems. Example couplings are also demonstrated.

  7. User's Manual for the FEHM Application-A Finite-Element Heat- and Mass-Transfer Code

    Energy Technology Data Exchange (ETDEWEB)

    George A. Zyvoloski; Bruce A. Robinson; Zora V. Dash; Lynn L. Trease

    1997-07-07

    This document is a manual for the use of the FEHM application, a finite-element heat- and mass-transfer computer code that can simulate nonisothermal multiphase multicomponent flow in porous media. The use of this code is applicable to natural-state studies of geothermal systems and groundwater flow. A primary use of the FEHM application will be to assist in the understanding of flow fields and mass transport in the saturated and unsaturated zones below the proposed Yucca Mountain nuclear waste repository in Nevada. The equations of heat and mass transfer for multiphase flow in porous and permeable media are solved in the FEHM application by using the finite-element method. The permeability and porosity of the medium are allowed to depend on pressure and temperature. The code also has provisions for movable air and water phases and noncoupled tracers; that is, tracer solutions that do not affect the heat- and mass-transfer solutions. The tracers can be passive or reactive. The code can simulate two-dimensional, two-dimensional radial, or three-dimensional geometries. In fact, FEHM is capable of describing flow that is dominated in many areas by fracture and fault flow, including the inherently three-dimensional flow that results from permeation to and from faults and fractures. The code can handle coupled heat and mass-transfer effects, such as boiling, dryout, and condensation that can occur in the near-field region surrounding the potential repository and the natural convection that occurs through Yucca Mountain due to seasonal temperature changes. The code is also capable of incorporating the various adsorption mechanisms, ranging from simple linear relations to nonlinear isotherms, needed to describe the very complex transport processes at Yucca Mountain. This report outlines the uses and capabilities of the FEHM application, initialization of code variables, restart procedures, and error processing. The report describes all the data files, the input data

  8. Data Parallel Line Relaxation (DPLR) Code User Manual: Acadia - Version 4.01.1

    Science.gov (United States)

    Wright, Michael J.; White, Todd; Mangini, Nancy

    2009-01-01

    Data-Parallel Line Relaxation (DPLR) code is a computational fluid dynamic (CFD) solver that was developed at NASA Ames Research Center to help mission support teams generate high-value predictive solutions for hypersonic flow field problems. The DPLR Code Package is an MPI-based, parallel, full three-dimensional Navier-Stokes CFD solver with generalized models for finite-rate reaction kinetics, thermal and chemical non-equilibrium, accurate high-temperature transport coefficients, and ionized flow physics incorporated into the code. DPLR also includes a large selection of generalized realistic surface boundary conditions and links to enable loose coupling with external thermal protection system (TPS) material response and shock layer radiation codes.

  9. SCDAP/RELAP5/MOD 3.1 code manual: Interface theory. Volume 1

    International Nuclear Information System (INIS)

    Coryell, E.W.

    1995-06-01

    The SCDAP/RELAP5 code has been developed for best estimate transient simulation of light water reactor coolant systems during a severe accident. The code models the coupled behavior of the reactor coolant system, core, fission product released during a severe accident transient as well as large and small break loss of coolant accidents, operational transients such as anticipated transient without SCRAM, loss of off-site power, loss of feedwater, and loss of flow. A generic modeling approach is used that permits as much of a particular system to be modeled as necessary. Control system and secondary system components are included to permit modeling of plant controls, turbines, condensers, and secondary feedwater conditioning systems. This volume describes the organization and manner of the interface between severe accident models which are resident in the SCDAP portion of the code and hydrodynamic models which are resident in the RELAP5 portion of the code. A description of the organization and structure of SCDAP/RELAP5 is presented. Additional information is provided regarding the manner in which models in one portion of the code impact other parts of the code, and models which are dependent on and derive information from other subcodes

  10. Light water reactor fuel analysis code. FEMAXI-6 (Ver.1). Detailed structure and user's manual

    International Nuclear Information System (INIS)

    Suzuki, Motoe; Saitou, Hiroaki

    2006-02-01

    A light water reactor fuel analysis code FEMAXI-6 is an advanced version which has been produced by integrating the former version FEMAXI-V with numerous functional improvements and extensions. In particular, the FEMAXI-6 code has attained a complete coupled solution of thermal analysis and mechanical analysis, enabling an accurate prediction of pellet-clad gap size and PCMI in high burnup fuel rods. Also, such new models have been implemented as pellet-clad bonding and fission gas bubble swelling, and linkage function with detailed burning analysis code has been enhanced. Furthermore, a number of new materials properties and parameters have been introduced. With these advancements, the FEMAXI-6 code has been upgraded to a versatile analytical tool for high burnup fuel behavior not only in the normal operation but also in anticipated transient conditions. This report describes in detail the design, basic theory and structure, models and numerical method, improvements and extensions, and method of model modification. In order to facilitate effective and wide-ranging application of the code, formats and methods of input/output of the code are also described, and a sample output in an actual form is included. (author)

  11. RELAP5/MOD3 code manual. Volume 4, Models and correlations

    International Nuclear Information System (INIS)

    1995-08-01

    The RELAP5 code has been developed for best-estimate transient simulation of light water reactor coolant systems during postulated accidents. The code models the coupled behavior of the reactor coolant system and the core for loss-of-coolant accidents and operational transients such as anticipated transient without scram, loss of offsite power, loss of feedwater, and loss of flow. A generic modeling approach is used that permits simulating a variety of thermal hydraulic systems. Control system and secondary system components are included to permit modeling of plant controls, turbines, condensers, and secondary feedwater systems. RELAP5/MOD3 code documentation is divided into seven volumes: Volume I presents modeling theory and associated numerical schemes; Volume II details instructions for code application and input data preparation; Volume III presents the results of developmental assessment cases that demonstrate and verify the models used in the code; Volume IV discusses in detail RELAP5 models and correlations; Volume V presents guidelines that have evolved over the past several years through the use of the RELAP5 code; Volume VI discusses the numerical scheme used in RELAP5; and Volume VII presents a collection of independent assessment calculations

  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. Code manual for MACCS2: Volume 1, user`s guide

    Energy Technology Data Exchange (ETDEWEB)

    Chanin, D.I.; Young, M.L.

    1997-03-01

    This report describes the use of the MACCS2 code. The document is primarily a user`s guide, though some model description information is included. MACCS2 represents a major enhancement of its predecessor MACCS, the MELCOR Accident Consequence Code System. MACCS, distributed by government code centers since 1990, was developed to evaluate the impacts of severe accidents at nuclear power plants on the surrounding public. The principal phenomena considered are atmospheric transport and deposition under time-variant meteorology, short- and long-term mitigative actions and exposure pathways, deterministic and stochastic health effects, and economic costs. No other U.S. code that is publicly available at present offers all these capabilities. MACCS2 was developed as a general-purpose tool applicable to diverse reactor and nonreactor facilities licensed by the Nuclear Regulatory Commission or operated by the Department of Energy or the Department of Defense. The MACCS2 package includes three primary enhancements: (1) a more flexible emergency-response model, (2) an expanded library of radionuclides, and (3) a semidynamic food-chain model. Other improvements are in the areas of phenomenological modeling and new output options. Initial installation of the code, written in FORTRAN 77, requires a 486 or higher IBM-compatible PC with 8 MB of RAM.

  14. GO software version 3.0: Volume 1, Overview: Computer Code Manual

    International Nuclear Information System (INIS)

    1988-06-01

    The GO Methodology is a success-oriented probabilistic system performance analysis technique. The methodology can be used to quantify system reliability and availability, identify and rank critical components and the contributors to system failure, construct event trees, perform statistical uncertainty analysis, and evaluate the effects of external events and common cause failures on system performance. This Overview Manual provides a description of the GO methodology, how it can be used, the benefits of using it in the analysis of complex systems, and a comparison of the methodology with fault tree analysis. 14 refs., 35 figs., 9 tabs

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

    Science.gov (United States)

    Chang, Chau-Lyan

    2004-01-01

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

  16. User's manual for DSTAR MOD1: A comprehensive tokamak disruption code

    International Nuclear Information System (INIS)

    Merrill, B.J.; Jardin, S.J.

    1986-01-01

    A computer code, DSTAR, has recently been developed to quantify the surface erosion and induced forces that can occur during major tokamak plasma disruptions. The DSTAR code development effort has been accomplished by coupling a recently developed free boundary tokamak plasma transport computational model with other models developed to predict impurity transport and radiation, and the electromagnetic and thermal dynamic response of vacuum vessel components. The combined model, DSTAR, is a unique tool for predicting the consequences of tokamak disruptions. This informal report discusses the sequence of events of a resistive disruption, models developed to predict plasma transport and electromagnetic field evolution, the growth of the stochastic region of the plasma, the transport and nonequilibrium ionization/emitted radiation of the ablated vacuum vessel material, the vacuum vessel thermal and magnetic response, and user input and code output

  17. RELAP/MOD3 code manual: User's guidelines. Volume 5, Revision 1

    International Nuclear Information System (INIS)

    Fletcher, C.D.; Schultz, R.R.

    1995-08-01

    The RELAP5 code has been developed for best estimate transient simulation of light water reactor coolant systems during postulated accidents. The code models the coupled behavior of the reactor coolant system and the core for loss-of-coolant accidents, and operational transients, such as anticipated transient without scram, loss of offsite power, loss of feedwater, and loss of flow. A generic modeling approach is used that permits simulating a variety of thermal hydraulic systems. Control system and secondary system components are included to permit modeling of plant controls, turbines, condensers, and secondary feedwater systems. Volume V contains guidelines that have solved over the past several years through the use of the RELAP5 code

  18. RELAP/MOD3 code manual: User`s guidelines. Volume 5, Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Fletcher, C.D.; Schultz, R.R. [Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)

    1995-08-01

    The RELAP5 code has been developed for best estimate transient simulation of light water reactor coolant systems during postulated accidents. The code models the coupled behavior of the reactor coolant system and the core for loss-of-coolant accidents, and operational transients, such as anticipated transient without scram, loss of offsite power, loss of feedwater, and loss of flow. A generic modeling approach is used that permits simulating a variety of thermal hydraulic systems. Control system and secondary system components are included to permit modeling of plant controls, turbines, condensers, and secondary feedwater systems. Volume V contains guidelines that have solved over the past several years through the use of the RELAP5 code.

  19. Description and user's manual of light water reactor fuel analysis code FEMAXI-IV (Ver.2)

    International Nuclear Information System (INIS)

    Suzuki, Motoe; Saitou, Hiroaki.

    1997-03-01

    FEMAXI-IV is an advanced version of FEMAXI-III, the analysis code of light water reactor fuel behavior in which various functions and improvements have been incorporated. The present report describes in detail the basic theories and structure, the models and numerical solutions applied, and the material properties adopted in the version 2 which is an improved version of the first version of FEMAXI-IV. In FEMAXI-IV (Ver.2), bugs have been fixed, pellet thermal conductivity properties have been updated, and thermal-stress-induced FP gas release model have been incorporated. In order to facilitate effective and wide-ranging application of the code, types and methods of input/output of the code are also described, and a sample output in an actual form is included. (author)

  20. SIERRA Code Coupling Module: Arpeggio User Manual Version 4.44

    Energy Technology Data Exchange (ETDEWEB)

    Sierra Thermal/Fluid Team

    2017-04-01

    The SNL Sierra Mechanics code suite is designed to enable simulation of complex multiphysics scenarios. The code suite is composed of several specialized applications which can operate either in standalone mode or coupled with each other. Arpeggio is a supported utility that enables loose coupling of the various Sierra Mechanics applications by providing access to Framework services that facilitate the coupling. More importantly Arpeggio orchestrates the execution of applications that participate in the coupling. This document describes the various components of Arpeggio and their operability. The intent of the document is to provide a fast path for analysts interested in coupled applications via simple examples of its usage.

  1. 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)

  2. The Role of Training and Promotion to Increase The 3rd Party Funds Indonesian Islamic Banking

    Directory of Open Access Journals (Sweden)

    Rahmat Hidayat

    2014-03-01

    Full Text Available Objective – This study aims to determine whether the role of training is much larger than the promotion in raising third-party funds in Islamic banks in Indonesia given the cost of the training is spent is greater than the cost of promotion. This study empirically examines the relationship and impact of training and promotion to raise funds for a 3rd party in Indonesia Islamic banks.Methods – This study uses secondary data Islamic commercial banks in the form of panel (time-series and cross-section of Bank Indonesia data from 2010 until 2012. There are two independent variables training cost (X1 and promotion cost (X2 and one dependent variable is 3rd-party funds (Y. The analysis technique used path analysis to examine the role of training and the promotion of financial performance (The 3rd Party Funds.Result – Simultaneously, training and promotion gives an effect by 52%, and partially or individual training gives an insignificant negative effect, while the promotion has a significant positive impact on financial performance (financial-party funds on Islamic banking.Conclusion – The role of promotion is higher in raising The 3rd Party Funds than training. Keywords : Cost, Training, Promotion, The 3rd Party Funds 

  3. File list: Oth.Lar.10.AllAg.3rd_instar [Chip-atlas[Archive

    Lifescience Database Archive (English)

    Full Text Available Oth.Lar.10.AllAg.3rd_instar dm3 TFs and others Larvae 3rd instar SRX104963,SRX10497...4971,SRX331403 http://dbarchive.biosciencedbc.jp/kyushu-u/dm3/assembled/Oth.Lar.10.AllAg.3rd_instar.bed ...

  4. File list: Oth.Lar.20.AllAg.3rd_instar [Chip-atlas[Archive

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  5. File list: Unc.Lar.10.AllAg.3rd_instar [Chip-atlas[Archive

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  7. File list: Pol.Lar.10.AllAg.3rd_instar [Chip-atlas[Archive

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  9. File list: ALL.Lar.05.AllAg.3rd_instar [Chip-atlas[Archive

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  14. File list: ALL.Lar.10.AllAg.3rd_instar [Chip-atlas[Archive

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  17. File list: Pol.Lar.20.AllAg.3rd_instar [Chip-atlas[Archive

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    Full Text Available Pol.Lar.20.AllAg.3rd_instar dm3 RNA polymerase Larvae 3rd instar SRX287908,SRX28790...7,SRX013070,SRX013082 http://dbarchive.biosciencedbc.jp/kyushu-u/dm3/assembled/Pol.Lar.20.AllAg.3rd_instar.bed ...

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    Full Text Available Oth.Lar.05.AllAg.3rd_instar dm3 TFs and others Larvae 3rd instar SRX104964,SRX10496...1403,SRX495243 http://dbarchive.biosciencedbc.jp/kyushu-u/dm3/assembled/Oth.Lar.05.AllAg.3rd_instar.bed ...

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  1. File list: InP.Lar.50.AllAg.3rd_instar [Chip-atlas[Archive

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  2. File list: Oth.Lar.50.AllAg.3rd_instar [Chip-atlas[Archive

    Lifescience Database Archive (English)

    Full Text Available Oth.Lar.50.AllAg.3rd_instar dm3 TFs and others Larvae 3rd instar SRX318781,SRX31878...5306 http://dbarchive.biosciencedbc.jp/kyushu-u/dm3/assembled/Oth.Lar.50.AllAg.3rd_instar.bed ...

  3. Users manual for the FORSS sensitivity and uncertainty analysis code system

    International Nuclear Information System (INIS)

    Lucius, J.L.; Weisbin, C.R.; Marable, J.H.; Drischler, J.D.; Wright, R.Q.; White, J.E.

    1981-01-01

    FORSS is a code system used to study relationships between nuclear reaction cross sections, integral experiments, reactor performance parameter predictions and associated uncertainties. This report describes the computing environment and the modules currently used to implement FORSS Sensitivity and Uncertainty Methodology

  4. User's manual for the vertical axis wind turbine performance computer code darter

    Energy Technology Data Exchange (ETDEWEB)

    Klimas, P. C.; French, R. E.

    1980-05-01

    The computer code DARTER (DARrieus, Turbine, Elemental Reynolds number) is an aerodynamic performance/loads prediction scheme based upon the conservation of momentum principle. It is the latest evolution in a sequence which began with a model developed by Templin of NRC, Canada and progressed through the Sandia National Laboratories-developed SIMOSS (SSImple MOmentum, Single Streamtube) and DART (SARrieus Turbine) to DARTER.

  5. SCDAP/RELAP5/MOD 3.1 Code Manual: Developmental assessment. Volume 5

    Energy Technology Data Exchange (ETDEWEB)

    Hohorst, J.K.; Johnsen, E.C. [eds.; Allison, C.M. [Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)

    1995-06-01

    The SCDAP/RELAP5 code has been developed for best estimate transient simulation of Light Water Reactor coolant systems during a severe accident. The code models the coupled behavior of the reactor coolant system, the core, fission product released during a severe accident transient as well as large and small break loss of coolant accidents, operational transients such as anticipated transient without SCRAM, loss of offsite power, loss of feedwater, and loss of flow. A generic modeling approach is used that permits as much of a particular system to be modeled as necessary. Control system and secondary system components are included to permit modeling of plant controls, turbines, condensers, and secondary feedwater conditioning systems. This volume contains detailed code-to-data calculations performed using SCDAP/RELAP5/MOD3.1, as well as comparison calculations performed with earlier code versions. Results of full plant calculations which include Surry, TMI-2, and Browns Ferry are described. Results of a nodalization study, which accounted for both axial and radial nodalization of the core, are also reported.

  6. The Wims-Traca code for the calculation of fuel elements. User's manual and input data

    International Nuclear Information System (INIS)

    Anhert, C.

    1980-01-01

    The set of modifications and new options developped for the Wims-D code is explained. The input data of the new version Wims-Traca are described. The printed output of results is also explained. The contents and the source of the nuclear data in the basic library is exposed. (author)

  7. SCDAP/RELAP5/MOD 3.1 Code Manual: Developmental assessment. Volume 5

    International Nuclear Information System (INIS)

    Hohorst, J.K.; Johnsen, E.C.

    1995-06-01

    The SCDAP/RELAP5 code has been developed for best estimate transient simulation of Light Water Reactor coolant systems during a severe accident. The code models the coupled behavior of the reactor coolant system, the core, fission product released during a severe accident transient as well as large and small break loss of coolant accidents, operational transients such as anticipated transient without SCRAM, loss of offsite power, loss of feedwater, and loss of flow. A generic modeling approach is used that permits as much of a particular system to be modeled as necessary. Control system and secondary system components are included to permit modeling of plant controls, turbines, condensers, and secondary feedwater conditioning systems. This volume contains detailed code-to-data calculations performed using SCDAP/RELAP5/MOD3.1, as well as comparison calculations performed with earlier code versions. Results of full plant calculations which include Surry, TMI-2, and Browns Ferry are described. Results of a nodalization study, which accounted for both axial and radial nodalization of the core, are also reported

  8. Users manual for the FORSS sensitivity and uncertainty analysis code system

    Energy Technology Data Exchange (ETDEWEB)

    Lucius, J.L.; Weisbin, C.R.; Marable, J.H.; Drischler, J.D.; Wright, R.Q.; White, J.E.

    1981-01-01

    FORSS is a code system used to study relationships between nuclear reaction cross sections, integral experiments, reactor performance parameter predictions and associated uncertainties. This report describes the computing environment and the modules currently used to implement FORSS Sensitivity and Uncertainty Methodology.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1977-02-01

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

  10. User's manual and analysis methodology of probabilistic fracture mechanics analysis code PASCAL Ver.2 for reactor pressure vessel (Contract research)

    International Nuclear Information System (INIS)

    Osakabe, Kazuya; Onizawa, Kunio; Shibata, Katsuyuki; Kato, Daisuke

    2006-09-01

    As a part of the aging structural integrity research for LWR components, the probabilistic fracture mechanics (PFM) analysis code PASCAL (PFM Analysis of Structural Components in Aging LWR) has been developed in JAEA. This code evaluates the conditional probabilities of crack initiation and fracture of a reactor pressure vessel (RPV) under transient conditions such as pressurized thermal shock (PTS). The development of the code has been aimed to improve the accuracy and reliability of analysis by introducing new analysis methodologies and algorithms considering the recent development in the fracture mechanics and computer performance. PASCAL Ver.1 has functions of optimized sampling in the stratified Monte Carlo simulation, elastic-plastic fracture criterion of the R6 method, crack growth analysis models for a semi-elliptical crack, recovery of fracture toughness due to thermal annealing and so on. Since then, under the contract between the Ministry of Economy, Trading and Industry of Japan and JAEA, we have continued to develop and introduce new functions into PASCAL Ver.2 such as the evaluation method for an embedded crack, K I database for a semi-elliptical crack considering stress discontinuity at the base/cladding interface, PTS transient database, and others. A generalized analysis method is proposed on the basis of the development of PASCAL Ver.2 and results of sensitivity analyses. Graphical user interface (GUI) including a generalized method as default values has been also developed for PASCAL Ver.2. This report provides the user's manual and theoretical background of PASCAL Ver.2. (author)

  11. User's manual for the FEHM application - A finite-element heat- and mass-transfer code

    International Nuclear Information System (INIS)

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

    1997-07-01

    The use of this code is applicable to natural-state studies of geothermal systems and groundwater flow. A primary use of the FEHM application will be to assist in the understanding of flow fields and mass transport in the saturated and unsaturated zones below the proposed Yucca Mountain nuclear waste repository in Nevada. The equations of heat and mass transfer for multiphase flow in porous and permeable media are solved in the FEHM application by using the finite-element method. The permeability and porosity of the medium are allowed to depend on pressure and temperature. The code also has provisions for movable air and water phases and noncoupled tracers; that is, tracer solutions that do not affect the heat- and mass-transfer solutions. The tracers can be passive or reactive. The code can simulate two-dimensional, two-dimensional radial, or three-dimensional geometries. In fact, FEHM is capable of describing flow that is dominated in many areas by fracture and fault flow, including the inherently three-dimensional flow that results from permeation to and from faults and fractures. The code can handle coupled heat and mass-transfer effects, such as boiling, dryout, and condensation that can occur in the near-field region surrounding the potential repository and the natural convection that occurs through Yucca Mountain due to seasonal temperature changes. This report outlines the uses and capabilities of the FEHM application, initialization of code variables, restart procedures, and error processing. The report describes all the data files, the input data, including individual input records or parameters, and the various output files. The system interface is described, including the software environment and installation instructions

  12. Simulation model for wind energy storage systems. Volume II. Operation manual. [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 II, the SIMWEST operation manual, describes the usage of the SIMWEST program, the design of the library components, and a number of simple example simulations intended to familiarize the user with the program's operation. Volume II also contains a listing of each SIMWEST library subroutine.

  13. ABAQUS-EPGEN: a general-purpose finite-element code. Volume 1. User's manual

    International Nuclear Information System (INIS)

    Hibbitt, H.D.; Karlsson, B.I.; Sorensen, E.P.

    1982-10-01

    This document is the User's Manual for ABAQUS/EPGEN, a general purpose finite element computer program, designed specifically to serve advanced structural analysis needs. The program contains very general libraries of elements, materials and analysis procedures, and is highly modular, so that complex combinations of features can be put together to model physical problems. The program is aimed at production analysis needs, and for this purpose aspects such as ease-of-use, reliability, flexibility and efficiency have received maximum attention. The input language is designed to make it straightforward to describe complicated models; the analysis procedures are highly automated with the program choosing time or load increments based on user supplied tolerances and controls; and the program offers a wide range of post-processing options for display of the analysis results

  14. User manual of Visual Balan V. 1.0 Interactive code for water balances and refueling estimation

    International Nuclear Information System (INIS)

    Samper, J.; Huguet, L.; Ares, J.; Garcia, M. A.

    1999-01-01

    This document contains the Users Manual of Visual Balan V1.0, an updated version of Visual Balan V0.0 (Samper et al., 1997). Visual Balan V1.0 performs daily water balances in the soil, the unsaturated zone and the aquifer in a user-friendly environment which facilitates both the input data process and the postprocessing of results. The main inputs of the balance are rainfall and irrigation while the outputs are surface runoff, evapotranspiration, interception, inter flow and groundwater flow. The code evaluates all these components in a sequential manner by starting with rainfall and irrigation, which must be provided by the user, and continuing with interception, surface runoff, evapotranspiration, and potential recharge (water flux crossing the bottom of the soil). This potential recharge is the input to the unsaturated zone where water can flow horizontally as subsurface flow (inter flow) or vertically as percolation into the aquifer. (Author)

  15. A User’s Manual for: Electromagnetic Surface Patch Code (ESP).

    Science.gov (United States)

    1981-07-01

    common e equivalent to say physical contact, that the two (or The parameter IOVL thi 5 code intersect ove rlap, ce contin dge Inse ing...cross polarizations is shown. The phase of field field is also shown (the incident wave at the origon). For backscattering STPM = both are printed...scattered fields phi polarized. STPM = scattering cross section with incident field theta polarized and scattered field phi polarized. SPTM

  16. A probabilistic assessment code system for derivation of clearance levels of radioactive materials. PASCLR user's manual

    International Nuclear Information System (INIS)

    Takahashi, Tomoyuki; Takeda, Seiji; Kimura, Hideo

    2001-01-01

    It is indicated that some types of radioactive material generating from the development and utilization of nuclear energy do not need to be subject regulatory control because they can only give rise to trivial radiation hazards. The process to remove such materials from regulatory control is called as 'clearance'. The corresponding levels of the concentration of radionuclides are called as 'clearance levels'. In the Nuclear Safety Commission's discussion, the deterministic approach was applied to derive the clearance levels, which are the concentrations of radionuclides in a cleared material equivalent to an individual dose criterion. Basically, realistic parameter values were selected for it. If the realistic values could not be defined, reasonably conservative values were selected. Additionally, the stochastic approaches were performed to validate the results which were obtained by the deterministic calculations. We have developed a computer code system PASCLR (Probabilistic Assessment code System for derivation of Clearance Levels of Radioactive materials) by using the Monte Carlo technique for carrying out the stochastic calculations. This report describes the structure and user information for execution of PASCLR code. (author)

  17. SCDAP/RELAP5/MOD 3.1 code manual: Damage progression model theory. Volume 2

    International Nuclear Information System (INIS)

    Davis, K.L.

    1995-06-01

    The SCDAP/RELAP5 code has been developed for best estimate transient simulation of light water reactor coolant systems during a severe accident. The code models the coupled behavior of the reactor coolant system, the core, fission products released during a severe accident transient as well as large and small break loss of coolant accidents, operational transients such as anticipated transient without SCRAM, loss of offsite power, loss of feedwater, and loss of flow. A generic modeling approach is used that permits as much of a particular system to be modeled as necessary. Control system and secondary system components are included to permit modeling of plant controls, turbines, condensers, and secondary feedwater conditioning systems. This volume contains detailed descriptions of the severe accident models and correlations. It provides the user with the underlying assumptions and simplifications used to generate and implement the basic equations into the code, so an intelligent assessment of the applicability and accuracy of the resulting calculation can be made

  18. SCDAP/RELAP5/MOD 3.1 code manual: Damage progression model theory. Volume 2

    Energy Technology Data Exchange (ETDEWEB)

    Davis, K.L. [ed.; Allison, C.M.; Berna, G.A. [Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)] [and others

    1995-06-01

    The SCDAP/RELAP5 code has been developed for best estimate transient simulation of light water reactor coolant systems during a severe accident. The code models the coupled behavior of the reactor coolant system, the core, fission products released during a severe accident transient as well as large and small break loss of coolant accidents, operational transients such as anticipated transient without SCRAM, loss of offsite power, loss of feedwater, and loss of flow. A generic modeling approach is used that permits as much of a particular system to be modeled as necessary. Control system and secondary system components are included to permit modeling of plant controls, turbines, condensers, and secondary feedwater conditioning systems. This volume contains detailed descriptions of the severe accident models and correlations. It provides the user with the underlying assumptions and simplifications used to generate and implement the basic equations into the code, so an intelligent assessment of the applicability and accuracy of the resulting calculation can be made.

  19. Sequence Coding and Search System for licensee event reports: coder's manual. Volume 4

    International Nuclear Information System (INIS)

    Gallaher, R.B.; Guymon, R.H.; Mays, G.T.; Poore, W.P.; Cagle, R.J.; Harrington, K.H.; Johnson, M.P.

    1985-04-01

    Operating experience data from nuclear power plants are essential for safety and reliability analyses, especially analyses of trends and patterns. The licensee event reports (LERs) that are submitted to the Nuclear Regulatory Commission (NRC) by the nuclear power plant utilities contain much of this data. The NRC's Office for Analysis and Evaluation of Operational Data (AEOD) has developed, under contract with NSIC, a system for codifying the events reported in the LERs. The primary objective of the Sequence Coding and Search System (SCSS) is to reduce the descriptive text of the LERs to coded sequences that are both computer-readable and computer-searchable. This four volume report documents and describes SCSS in detail. Volume 3 and 4 provide a technical processor, new to SCSS, the information and methodology necessary to capture descriptive data from the LER and to codify that data into a structured format and serve as reference material for the more experienced technical processor, and contains information that is essential for the more advanced user who needs to be familiar with the intricate coding techniques in order to retrieve specific details in a sequence. This volume contains updated material through amendment 1 to revision 1 of the working version of ORNL/NSIC-223, Vol. 4

  20. Sequence Coding and Search System for licensee event reports: coder's manual. Volume 3

    International Nuclear Information System (INIS)

    Gallaher, R.B.; Guymon, R.H.; Mays, G.T.; Poore, W.P.; Cagle, R.J.; Harrington, K.H.; Johnson, M.P.

    1985-04-01

    Operating experience data from nuclear power plants are essential for safety and reliability analyses, especially analyses of trends and patterns. The licensee event reports (LERs) that are submitted to the Nuclear Regulatory Commission (NRC) by the nuclear power plant utilities contain much of this data. The NRC's Office for Analysis and Evaluation of Operational Data (AEOD) has developed, under contract with NSIC, a system for codifying the events reported in the LERs. The primary objective of the Sequence Coding and Search System (SCSS) is to reduce the descriptive text of the LERs to coded sequences that are both computer-readable and computer-searchable. This four volume report documents and describes SCSS in detail. Volumes 3 and 4 provide a technical processor, new to SCSS, the information and methodology necessary to capture descriptive data from the LER and to codify that data into a structured format and serve as reference material for the more experienced technical processor, and contains information is essential for the more advanced user who needs to be familiar with the intricate coding techniques in order to retrieve specific details in a sequence. This volume contains updated material through amendment 1 to revision 1 of the working version of ORNL/NSIC-223, Vol. 3

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

    Energy Technology Data Exchange (ETDEWEB)

    Ahnert, C; Aragones, J M

    1981-07-01

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

  2. HEFF---A user's manual and guide for the HEFF code for thermal-mechanical analysis using the boundary-element method

    International Nuclear Information System (INIS)

    St John, C.M.; Sanjeevan, K.

    1991-12-01

    The HEFF Code combines a simple boundary-element method of stress analysis with the closed form solutions for constant or exponentially decaying heat sources in an infinite elastic body to obtain an approximate method for analysis of underground excavations in a rock mass with heat generation. This manual describes the theoretical basis for the code, the code structure, model preparation, and step taken to assure that the code correctly performs its intended functions. The material contained within the report addresses the Software Quality Assurance Requirements for the Yucca Mountain Site Characterization Project. 13 refs., 26 figs., 14 tabs

  3. Manual for COMSYN: A orbit integration code for the study of beam dynamics in compact synchrotrons

    International Nuclear Information System (INIS)

    Huang, Y.

    1991-10-01

    COMSYN is a numerical integration code which is written for the study and design of the compact synchrotrons. An improved 4th-order Runge-Kutta method is used in COMSYN to integrate the exact equations of motion in a rectangular coordinate system. The magnetic field components of the dipole B x , B y and B z can be obtained from either measurement or directly computed data (MAGNUS, TOSCA). A spline interpolation method is then used to get the field value at the particle position. For standard quadrupole and sextupole, the analytical expression is employed to compute its field distribution

  4. Plasma Separation Process: Betacell (BCELL) code: User's manual. [Bipolar barrier junction

    Energy Technology Data Exchange (ETDEWEB)

    Taherzadeh, M.

    1987-11-13

    The emergence of clearly defined applications for (small or large) amounts of long-life and reliable power sources has given the design and production of betavoltaic systems a new life. Moreover, because of the availability of the plasma separation program, (PSP) at TRW, it is now possible to separate the most desirable radioisotopes for betacell power generating devices. A computer code, named BCELL, has been developed to model the betavoltaic concept by utilizing the available up-to-date source/cell parameters. In this program, attempts have been made to determine the betacell energy device maximum efficiency, degradation due to the emitting source radiation and source/cell lifetime power reduction processes. Additionally, comparison is made between the Schottky and PN junction devices for betacell battery design purposes. Certain computer code runs have been made to determine the JV distribution function and the upper limit of the betacell generated power for specified energy sources. A Ni beta emitting radioisotope was used for the energy source and certain semiconductors were used for the converter subsystem of the betacell system. Some results for a Promethium source are also given here for comparison. 16 refs.

  5. PreK-3rd: What Is the Price Tag? Policy to Action Brief. No. 2

    Science.gov (United States)

    Shore, Rima

    2009-01-01

    In an era of intense fiscal pressures, educators are focusing on those investments most likely to lift student achievement. They are also trying to make more strategic use of existing resources. To achieve these goals, a growing number of policymakers are considering integrated PreK-3rd approaches. Increasingly, they are recognizing that the first…

  6. Participants to the 3rd HEP Information Resources Summit, 6-7 May 2009

    CERN Multimedia

    Fermilab, Photo Service

    2009-01-01

    The broad theme of the 3rd HEP Information Resources Summit was "Collaboration between Information Services." As HEP increasingly borders fields such as instrumentation and astrophysics, it was discussed what potential interrelationships and communication this group have to serve this broader research community seamlessly.

  7. Using Food as a Tool to Teach Science to 3rd Grade Students in Appalachian Ohio

    Science.gov (United States)

    Duffrin, Melani W.; Hovland, Jana; Carraway-Stage, Virginia; McLeod, Sara; Duffrin, Christopher; Phillips, Sharon; Rivera, David; Saum, Diana; Johanson, George; Graham, Annette; Lee, Tammy; Bosse, Michael; Berryman, Darlene

    2010-01-01

    The Food, Math, and Science Teaching Enhancement Resource (FoodMASTER) Initiative is a compilation of programs aimed at using food as a tool to teach mathematics and science. In 2007 to 2008, a foods curriculum developed by professionals in nutrition and education was implemented in 10 3rd-grade classrooms in Appalachian Ohio; teachers in these…

  8. Malaria and fetal growth alterations in the 3(rd) trimester of pregnancy

    DEFF Research Database (Denmark)

    Schmiegelow, Christentze; Minja, Daniel Thomas; Oesterholt, Mayke

    2013-01-01

    Pregnancy associated malaria is associated with decreased birth weight, but in-utero evaluation of fetal growth alterations is rarely performed. The objective of this study was to investigate malaria induced changes in fetal growth during the 3(rd) trimester using trans-abdominal ultrasound....

  9. Developments in Processing by Severe Plastic Deformation at the 3rd Pan American Materials Congress

    Science.gov (United States)

    Figueiredo, Roberto B.; Kawasaki, Megumi; Langdon, Terence G.

    2017-10-01

    The 3rd Pan American Materials Congress in San Diego, California, February 26-March 2, 2017, provided an opportunity to bring together many participants working in the field of severe plastic deformation. This article provides a brief review of these activities.

  10. Epidemiology of 3rd generation cephalosporin-resistant Escherichia coli on dairy farms

    Science.gov (United States)

    Dairy cattle have been identified as a reservoir for 3rd generation cephalosporin (3GC)-resistant Escherichia coli. We previously identified 3GC-resistant E. coli from manure composite samples of calves and cows in a survey of 80 farms in Pennsylvania. Resistant strains were most frequently isolated...

  11. Starting Young: Massachusetts Birth-3rd Grade Policies That Support Children's Literacy Development

    Science.gov (United States)

    Cook, Shayna; Bornfreund, Laura

    2015-01-01

    Massachusetts is one of a handful of states that is often recognized as a leader in public education, and for good reason. The Commonwealth consistently outperforms most states on national reading and math tests and often leads the pack in education innovations. "Starting Young: Massachusetts Birth-3rd Grade Policies that Support Children's…

  12. 75 FR 34450 - Filing Dates for the Indiana Special Election in the 3rd Congressional District

    Science.gov (United States)

    2010-06-17

    ... 3rd Congressional District AGENCY: Federal Election Commission. ACTION: Notice of filing dates for special election. SUMMARY: Indiana has scheduled a Special General Election on November 2, 2010, to fill.... Committees required to file reports in connection with the Special General Election on November 2, 2010...

  13. Effects of Mode of Target Task Selection on Learning about Plants in a Mobile Learning Environment: Effortful Manual Selection versus Effortless QR-Code Selection

    Science.gov (United States)

    Gao, Yuan; Liu, Tzu-Chien; Paas, Fred

    2016-01-01

    This study compared the effects of effortless selection of target plants using quick respond (QR) code technology to effortful manual search and selection of target plants on learning about plants in a mobile device supported learning environment. In addition, it was investigated whether the effectiveness of the 2 selection methods was…

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

    International Nuclear Information System (INIS)

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

    1993-07-01

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

  15. User's manual for ASTERIX-2: A two-dimensional modular code system for the steady state and xenon transient analysis of a pebble bed high temperature reactor

    International Nuclear Information System (INIS)

    Wu, T.; Cowan, C.L.; Lauer, A.; Schwiegk, H.J.

    1982-03-01

    The ASTERIX modular code package was developed at KFA Laboratory-Juelich for the steady state and xenon transient analysis of a pebble bed high temperature reactor. The code package was implemented on the Stanford Linear Accelerator Center Computer in August, 1980, and a user's manual for the current version of the code, identified as ASTERIX-2, was prepared as a cooperative effort by KFA Laboratory and GE-ARSD. The material in the manual includes the requirements for accessing the program, a description of the major subroutines, a listing of the input options, and a listing of the input data for a sample problem. The material is provided in sufficient detail for the user to carry out a wide range of analysis from steady state operations to the xenon induced power transients in which the local xenon, temperature, buckling and control feedback effects have been incorporated in the problem solution. (orig.)

  16. ChemSession'06 - 3rd Seminary of Warsaw PhD Students in Chemistry. Abstracts

    International Nuclear Information System (INIS)

    Zachara, J.; Lulinski, S.; Dobrowolski, J.C.; Raczynska, E.D.; Fuks, L.; Cyranski, M.K.; Stepien, B.T.; Sawicki, M.G.

    2006-01-01

    3 rd Annual Seminary of Warsaw PhD Students in Chemistry presented the latest achievements in chemistry, obtained in all Warsaw universities and scientific institutes. In 2006 participants presented 4 plenary lectures, and 109 posters. Among others, posters covered four disciplines related to the nuclear sciences: (a) radiobiology and radiotherapy, (b) radiation chemistry and photochemistry, (c) isotopic effects in chemistry, and (d) chemical technology

  17. Tretji slovenski MoodleMoot = 3rd Slovenian MoodleMoot

    Directory of Open Access Journals (Sweden)

    Viktorija Sulčič

    2009-09-01

    Full Text Available This year, the 3rd international moodle.si conference took place in Koper and brought together Slovenian users of Moodle, an open-source learning management system. This year’s conference, which is presented in the paper, was especially interesting due to its plenary session being wholly dedicated to the national e-schooling project. An interesting addition was also Apple’s workshop about using iLife applications in education.

  18. Sandstone columns of the 3rd Nile Cataract (Nubia, Northern Sudan)

    Czech Academy of Sciences Publication Activity Database

    Cílek, Václav; Adamovič, Jiří; Suková, L.

    2015-01-01

    Roč. 59, Supplement 1 (2015), s. 151-165 ISSN 0372-8854 Grant - others:Program interní podpory projektů mezinárodní spolupráce AV ČR(CZ) M100130902 Institutional support: RVO:67985831 Keywords : Nubian sandstone * columnar jointing * Voronoi fragmentation * 3rd Nile Cataract * Sudan Subject RIV: DB - Geology ; Mineralogy Impact factor: 1.103, year: 2015

  19. Evaluation of paracavernous cranial nerves (3rd to 6th) with CT

    International Nuclear Information System (INIS)

    Tsuha, Mitsuru; Okamura, Tomomi; Abiko, Seisho; Aoki, Hideo

    1984-01-01

    We have now used CT to evaluate the cavernous sinuses, especially the 3rd, 4th, 5th, and 6th cranial nerves. adjacent to them. Twenty cases, presumably all having sellar or parasellar lesions, were examined by means of thin-slice (2-4 mm) axial and coronal (including both direct and reconstructed methods) CT studies. Moreover, three blocks of the sellar region obtained from adult cadavers were examined beforehand by CT scan, and the courses of the respective paracavernous cranial nerves were confirmed by microsurgical dissection. As a result, the following conclusions were obtained. 1. It was valuable to perform a post-enhanced direct coronal study for the definite identification of the paracavernous cranial nerves (3rd to 6th cranial nerves). 2. Also valuable was a magnified CT film of the parasellar regions, which made the identification of the parasellar cranial nerves clearer. 3. In the clinical cases showing a normal shape of the cavernous sinuses on CT, each cranial nerve was evaluated. In the axial studies (almost 10 to 15 degrees anterior to Reid's basal line), the frequencies of the identification of the 3rd, 5th, and 6th cranial nerves were 76%, 97% (as to the Gasserian ganglion), and 21% respectively. None of the 4th cranial nerve was visualized in the cases examined. On the other hand, the frequencies of the identification of the 3rd, 5th, and 6th cranial nerves were 83%, 86%, and 21% respectively in the direct coronal studies and 62%, 57%, and 4% in those of the reconstructed films. The visualization of each cranial nerve in the direct coronal study was better than when the reconstructed method was used. Finally, a schematic presentation of the cranial nerves adjacent to the cavernous sinuses was made in the axial and coronal projections. (J.P.N.)

  20. The effect of introducing increased-reliability-risk electronic components into 3rd generation telecommunications systems

    International Nuclear Information System (INIS)

    Salmela, Olli

    2005-01-01

    In this paper, the dependability of 3rd generation telecommunications network systems is studied. Special attention is paid to a case where increased-reliability-risk electronic components are introduced to the system. The paper consists of three parts: First, the reliability data of four electronic components is considered. This includes statistical analysis of the reliability test data, thermo-mechanical finite element analysis of the printed wiring board structures, and based on those, a field reliability estimate of the components is constructed. Second, the component level reliability data is introduced into the network element reliability analysis. This is accomplished by using a reliability block diagram technique and Monte Carlo simulation of the network element. The end result of the second part is a reliability estimate of the network element with and without the high-risk component. Third, the whole 3rd generation network having multiple network elements is analyzed. In this part, the criticality of introducing high-risk electronic components into a 3rd generation telecommunications network is considered

  1. The effect of introducing increased-reliability-risk electronic components into 3rd generation telecommunications systems

    Energy Technology Data Exchange (ETDEWEB)

    Salmela, Olli [Nokia Networks, P.O. Box 301, 00045 Nokia Group (Finland)]. E-mail: olli.salmela@nokia.com

    2005-08-01

    In this paper, the dependability of 3rd generation telecommunications network systems is studied. Special attention is paid to a case where increased-reliability-risk electronic components are introduced to the system. The paper consists of three parts: First, the reliability data of four electronic components is considered. This includes statistical analysis of the reliability test data, thermo-mechanical finite element analysis of the printed wiring board structures, and based on those, a field reliability estimate of the components is constructed. Second, the component level reliability data is introduced into the network element reliability analysis. This is accomplished by using a reliability block diagram technique and Monte Carlo simulation of the network element. The end result of the second part is a reliability estimate of the network element with and without the high-risk component. Third, the whole 3rd generation network having multiple network elements is analyzed. In this part, the criticality of introducing high-risk electronic components into a 3rd generation telecommunications network is considered.

  2. Development of an Information Delivery Manual for Early Stage BIM-based Energy Performance Assessment and Code Compliance as a Part of DGNB Pre-Certification

    DEFF Research Database (Denmark)

    Petrova, Ekaterina Aleksandrova; Romanska, Iva; Stamenov, Martin

    2017-01-01

    for all parties involved. However, the persistent lack of early collaboration and process standardization prevent reaching the full potential of BIM-based performance evaluation. By following buildingSMART’s methodology for development of Information Delivery Manual/Model View Definition, this paper...... presents a framework for BIM-based energy performance assessment and code compliance, as required by the Danish Building Regulations and the DGNB rating system. Standardization of the information exchange would increase efficiency and reduce manual data input, duplication of work and errors due...

  3. Technical Optimization of Cross-Platform Software Development Process quality and Usability of 3rd-Party Tools

    Directory of Open Access Journals (Sweden)

    Yevgueny Kondratyev

    2016-03-01

    Full Text Available The article exposes developer's point of view on minimizing creation, upgrade, post-release problem solving time for applications and components, targeted to multiple operating systems, while keeping high end product quality and computational performance. Non-uniformity of analogous tools and components, available on different platforms, causes strong impact on developer's productivity. In part., differences in 3rd-party component interfaces, versions, quality of distinct functions, cause frequent switching developer's attention on issues not connected (in principle with the target project. While loss of development performance because of attention specifics is more subjective value, at least physical time spent on tools/components misbehavior compensation and normal tools configuring is measurable. So, the main thesis verified is whether it's possible to increase continuity of the development process by technical improvements only, and by which value. In addition, a novel experimental tool for interactive code execution is described, allowing for deep changes in the working program without its restart. Question under research: minimizing durations of programming-build-test-correct loop and small code parts runs, in part., improving the debugging workflow for the account of combining the interactive editor and the debugger.

  4. Study on applicability of evaluation model of manpower needs for dismantling of equipments in FUGEN-1. Dismantling process in 3rd/4th feedwater heater room

    International Nuclear Information System (INIS)

    Shibahara, Yuji; Izumi, Masanori; Nanko, Takashi; Tachibana, Mitsuo; Ishigami, Tsutomu

    2010-10-01

    Manpower needs for the dismantling process on the dismantling of equipments in FUGEN 3rd/4th feedwater heater room was calculated with the management data evaluation system (PRODIA Code), and it was inspected whether the conventional evaluation model had applicability for FUGEN or not. It was confirmed that the conventional evaluation model for feedwater heater had no applicability. In comparison of the calculated value with the actual data, we found two difference: 1) the calculated value were significantly larger than the actual data, 2) the actual data for the dismantling of 3rd feedwater heater was twice larger than that of 4th feedwater heater, though these equipments were almost same weight. It was found that these were brought 1) by the difference in the work descriptions of dismantling between JPDR and FUGEN, and 2) by that in the cutting number between 3rd feedwater heater and 4th one. The manpower needs for the dismantling of both feedwater heaters were calculated with a new calculation equation reflecting the descriptions of dismantling, and it was found that these results showed the good agreement with the actual data. (author)

  5. CSTEM User Manual

    Science.gov (United States)

    Hartle, M.; McKnight, R. L.

    2000-01-01

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

  6. RAMONA-4B a computer code with three-dimensional neutron kinetics for BWR and SBWR system transient - user`s manual

    Energy Technology Data Exchange (ETDEWEB)

    Rohatgi, U.S.; Cheng, H.S.; Khan, H.J.; Mallen, A.N.; Neymotin, L.Y.

    1998-03-01

    This document is the User`s Manual for the Boiling Water Reactor (BWR), and Simplified Boiling Water Reactor (SBWR) systems transient code RAMONA-4B. The code uses a three-dimensional neutron-kinetics model coupled with a multichannel, nonequilibrium, drift-flux, phase-flow model of the thermal hydraulics of the reactor vessel. The code is designed to analyze a wide spectrum of BWR core and system transients. Chapter 1 gives an overview of the code`s capabilities and limitations; Chapter 2 describes the code`s structure, lists major subroutines, and discusses the computer requirements. Chapter 3 is on code, auxillary codes, and instructions for running RAMONA-4B on Sun SPARC and IBM Workstations. Chapter 4 contains component descriptions and detailed card-by-card input instructions. Chapter 5 provides samples of the tabulated output for the steady-state and transient calculations and discusses the plotting procedures for the steady-state and transient calculations. Three appendices contain important user and programmer information: lists of plot variables (Appendix A) listings of input deck for sample problem (Appendix B), and a description of the plotting program PAD (Appendix C). 24 refs., 18 figs., 11 tabs.

  7. Foundational Skills to Support Reading for Understanding in Kindergarten through 3rd Grade. Educator's Practice Guide. NCEE 2016-4008

    Science.gov (United States)

    Foorman, Barbara; Beyler, Nicholas; Borradaile, Kelley; Coyne, Michael; Denton, Carolyn A.; Dimino, Joseph; Furgeson, Joshua; Hayes, Lynda; Henke, Juliette; Justice, Laura; Keating, Betsy; Lewis, Warnick; Sattar, Samina; Streke, Andrei; Wagner, Richard; Wissel, Sarah

    2016-01-01

    The goal of this practice guide is to offer educators specific, evidence-based recommendations for teaching foundational reading skills to students in kindergarten through 3rd grade. This guide is a companion to the existing practice guide, "Improving Reading Comprehension in Kindergarten Through 3rd Grade", and as a set, these guides…

  8. Summary of the 3rd workshop on the reduced-moderation water reactor

    International Nuclear Information System (INIS)

    Ishikawa, Nobuyuki; Nakatsuka, Tohru; Iwamura, Takamichi

    2000-06-01

    The research activities of a Reduced-Moderation Water Reactor (RMWR) are being performed for a development of the next generation water-cooled reactor. A workshop on the RMWR was held on March 3rd 2000 aiming to exchange information between JAERI and other organizations such as universities, laboratories, utilities and vendors. This report summarizes the contents of lectures and discussions on the workshop. The 1st workshop was held on March 1998 focusing on the review of the research activities and future research plan. The succeeding 2nd workshop was held on March 1999 focusing on the topics of the plutonium utilization in water-cooled reactors. The 3rd workshop was held on March 3rd 2000, which was attended by 77 participants. The workshop began with a lecture titled 'Recent Situation Related to Reduced-Moderation Water Reactor (RMWR)', followed by 'Program on MOX Fuel Utilization in Light Water Reactors' which is the mainstream scenario of plutonium utilization by utilities, and 'Feasibility Studies on Commercialized Fast Breeder Reactor Cycle System' mainly conducted by Japan Nuclear Cycle Development Institute (JNC). Also, following lectures were given as the recent research activities in JAERI: 'Progress in Design Study on Reduced-Moderation Water Reactors', 'Long-Term Scenarios of Power Reactors and Fuel Cycle Development and the Role of Reduced Moderation Water Reactors', 'Experimental and Analytical Study on Thermal Hydraulics' and Reactor Physics Experiment Plan using TCA'. At the end of the workshop, a general discussion was performed about the research and development of the RMWR. This report includes the original papers presented at the workshop and summaries of the questions and answers for each lecture and general discussion, as well as presentation viewgraphs, program and participant list as appendixes. The 7 of the presented papers are indexed individually. (J.P.N.)

  9. Summary of the 3rd workshop on the reduced-moderation water reactor

    Energy Technology Data Exchange (ETDEWEB)

    Ishikawa, Nobuyuki; Nakatsuka, Tohru; Iwamura, Takamichi [eds.

    2000-06-01

    The research activities of a Reduced-Moderation Water Reactor (RMWR) are being performed for a development of the next generation water-cooled reactor. A workshop on the RMWR was held on March 3rd 2000 aiming to exchange information between JAERI and other organizations such as universities, laboratories, utilities and vendors. This report summarizes the contents of lectures and discussions on the workshop. The 1st workshop was held on March 1998 focusing on the review of the research activities and future research plan. The succeeding 2nd workshop was held on March 1999 focusing on the topics of the plutonium utilization in water-cooled reactors. The 3rd workshop was held on March 3rd 2000, which was attended by 77 participants. The workshop began with a lecture titled 'Recent Situation Related to Reduced-Moderation Water Reactor (RMWR)', followed by 'Program on MOX Fuel Utilization in Light Water Reactors' which is the mainstream scenario of plutonium utilization by utilities, and 'Feasibility Studies on Commercialized Fast Breeder Reactor Cycle System' mainly conducted by Japan Nuclear Cycle Development Institute (JNC). Also, following lectures were given as the recent research activities in JAERI: 'Progress in Design Study on Reduced-Moderation Water Reactors', 'Long-Term Scenarios of Power Reactors and Fuel Cycle Development and the Role of Reduced Moderation Water Reactors', 'Experimental and Analytical Study on Thermal Hydraulics' and Reactor Physics Experiment Plan using TCA'. At the end of the workshop, a general discussion was performed about the research and development of the RMWR. This report includes the original papers presented at the workshop and summaries of the questions and answers for each lecture and general discussion, as well as presentation viewgraphs, program and participant list as appendixes. The 7 of the presented papers are indexed individually. (J.P.N.)

  10. The role of hemorrhoidopexy in the management of 3rd degree hemorrhoids.

    Science.gov (United States)

    Pramateftakis, M G

    2010-11-01

    Hemorrhoidopathy is a very common benign surgical pathology. Hemorrhoids are divided into 4 stages, depending on symptoms and degree of prolapse. Hemorrhoidopexy is a technique developed for the treatment of 3rd degree hemorrhoids, but its application has been extended to the treatment of 4th degree hemorrhoids as well. Nevertheless, recent studies identify weaknesses of the PPH in the treatment of 4th degree hemorrhoids. One hundred and twenty-six consecutive patients with 3rd degree hemorrhoids underwent stapled hemorrhoidopexy. All procedures were performed under general anesthesia with the patient in lithotomy position. A phosphate enema was given to the patient 2 h before the procedure, and cephalosporine and metronidazole were administered at anesthesia induction. Most patients were discharged the day after the operation. All patients were reassessed at 1, 6 weeks, 6 and 12 months after the procedure. The mean operating time was 16.3 min. Of all patients, 5.8% complained of mild rectal pain for a post-operative period of 5-12 days, 5.8% developed post-operative urinary retention, managed with catheterization, 13.3% experienced fecal urgency while 5.8% experienced gas incontinence, which subsided 2-8 weeks from surgery. The mean hospital stay was 1.2 days. Most patients returned to daily activities within 2-5 days. Ninety-five percent of patients returned for their follow-up visits. Recurrence of the disease occurred in 8 patients (6.6%). It was managed conservatively in 2 patients, 3 underwent redo hemorrhoidopexy and 3 underwent classic hemorrhoidectomy. According to our results, stapled hemorrhoidopexy seems to be a safe, pain-free and, in the long-term, effective technique for the treatment of 3rd degree hemorrhoids.

  11. 3rd International Conference on Modelling, Computation and Optimization in Information Systems and Management Sciences

    CERN Document Server

    Dinh, Tao; Nguyen, Ngoc

    2015-01-01

    This proceedings set contains 85 selected full papers presented at the 3rd International Conference on Modelling, Computation and Optimization in Information Systems and Management Sciences - MCO 2015, held on May 11–13, 2015 at Lorraine University, France. The present part I of the 2 volume set includes articles devoted to Combinatorial optimization and applications, DC programming and DCA: thirty years of Developments, Dynamic Optimization, Modelling and Optimization in financial engineering, Multiobjective programming, Numerical Optimization, Spline Approximation and Optimization, as well as Variational Principles and Applications

  12. 3rd IFToMM Symposium on Mechanism Design for Robotics

    CERN Document Server

    Ceccarelli, Marco

    2015-01-01

    This volume contains the Proceedings of the 3rd IFToMM Symposium on Mechanism Design for Robotics, held in Aalborg, Denmark, 2-4 June, 2015. The book contains papers on recent advances in the design of mechanisms and their robotic applications. It treats the following topics: mechanism design, mechanics of robots, parallel manipulators, actuators and their control, linkage and industrial manipulators, innovative mechanisms/robots and their applications, among others. The book can be used by researchers and engineers in the relevant areas of mechanisms, machines and robotics.

  13. Announced document collection of the 3rd information exchange meeting on radioactive waste disposal research network

    International Nuclear Information System (INIS)

    2008-03-01

    The 3rd meeting on 'Radioactive Waste Disposal Research Network' was held at the Ricotti techno community square of JAEA on September 3 and 4, 2007. The 'Radioactive Waste Disposal Research Network' was established in Interorganization Atomic Energy Research Program under academic collaborative agreement between Japan Atomic Energy Agency and the University of Tokyo. The objective is to bring both research infrastructures and human expertise in Japan to an adequate performance level, thereby contributing to the development of the fundamental research area in the field of radioactive waste disposal. This lecture material is a collection of presentations and discussions during the information exchange meeting. (author)

  14. 3rd International Conference on Computer Science, Applied Mathematics and Applications

    CERN Document Server

    Nguyen, Ngoc; Do, Tien

    2015-01-01

    This volume contains the extended versions of papers presented at the 3rd International Conference on Computer Science, Applied Mathematics and Applications (ICCSAMA 2015) held on 11-13 May, 2015 in Metz, France. The book contains 5 parts: 1. Mathematical programming and optimization: theory, methods and software, Operational research and decision making, Machine learning, data security, and bioinformatics, Knowledge information system, Software engineering. All chapters in the book discuss theoretical and algorithmic as well as practical issues connected with computation methods & optimization methods for knowledge engineering and machine learning techniques.  

  15. The 3rd Asia–Pacific Transport Working Group (APTWG) Meeting

    International Nuclear Information System (INIS)

    Jhang, Hogun; Diamond, P.H.; Leconte, M.; Kwon, J.M.; Ida, K.; Tamura, N.; Kosuga, Y.

    2014-01-01

    This conference report summarizes the contributions to and discussions at the 3rd Asia–Pacific Transport Working Group (APTWG) meeting held in Jeju-island, Korea, on 21–24 May 2013. The main objective of the meeting is to develop a predictive understanding of transport mechanisms in magnetically confined fusion plasmas. In an effort to accomplish this objective, four technical working groups were organized under the headings: (1) transport barrier formation and confinement enhancement, (2) 3D effects and Magnetohydrodynamic–turbulence interaction, (3) momentum transport and non-locality and (4) particle/impurity transport and energetic particles. (conference report)

  16. Proceedings of the 3rd NINS symposium on engineering and technology

    International Nuclear Information System (INIS)

    2008-10-01

    The 3rd NINS Symposium on Engineering and Technology was held on 24-25, July 2008 at National Institute for Fusion Science (NIFS), organized by Department of Engineering and Technical Services, NIFS. This Symposium is continuation of an annual series. The 1st one was held on 25-26 July, 2006 organized by National Astronomical Observatory of Japan. The 2nd one was held on 25-26 June, 2007 organized by Institute for Molecular Science. This proceedings is a compilation of papers presented at the symposium. 49 participants from 5 institutes of NINS attended this symposium and 23 papers were presented. (author)

  17. 3rd International Symposium on Big Data and Cloud Computing Challenges

    CERN Document Server

    Neelanarayanan, V

    2016-01-01

    This proceedings volume contains selected papers that were presented in the 3rd International Symposium on Big data and Cloud Computing Challenges, 2016 held at VIT University, India on March 10 and 11. New research issues, challenges and opportunities shaping the future agenda in the field of Big Data and Cloud Computing are identified and presented throughout the book, which is intended for researchers, scholars, students, software developers and practitioners working at the forefront in their field. This book acts as a platform for exchanging ideas, setting questions for discussion, and sharing the experience in Big Data and Cloud Computing domain.

  18. Formal faculty observation and assessment of bedside skills for 3rd-year neurology clerks.

    Science.gov (United States)

    Thompson Stone, Robert; Mooney, Christopher; Wexler, Erika; Mink, Jonathan; Post, Jennifer; Jozefowicz, Ralph F

    2016-11-22

    To evaluate the feasibility and utility of instituting a formalized bedside skills evaluation (BSE) for 3rd-year medical students on the neurology clerkship. A neurologic BSE was developed for 3rd - year neurology clerks at the University of Rochester for the 2012-2014 academic years. Faculty directly observed 189 students completing a full history and neurologic examination on real inpatients. Mock grades were calculated utilizing the BSE in the final grade, and number of students with a grade difference was determined when compared to true grade. Correlation was explored between the BSE and clinical scores, National Board of Medical Examiners (NBME) scores, case complexity, and true final grades. A survey was administered to students to assess their clinical skills exposure and the usefulness of the BSE. Faculty completed and submitted a BSE form for 88.3% of students. There was a mock final grade change for 13.2% of students. Correlation coefficients between BSE score and clinical score/NBME score were 0.36 and 0.35, respectively. A statistically significant effect of BSE was found on final clerkship grade (F 2,186 = 31.9, p neurology clerkship was feasible. Low correlation between BSE score and other evaluations indicated a unique measurement to contribute to student grade. Using real patients with differing case complexity did not alter the grade. © 2016 American Academy of Neurology.

  19. Teaching Newton's 3rd law of motion using learning by design approach

    Science.gov (United States)

    Aquino, Jiezel G.; Caliguid, Mariel P.; Buan, Amelia T.; Magsayod, Joy R.; Lahoylahoy, Myrna E.

    2018-01-01

    This paper presents the process and implementation of Learning by Design Approach in teaching Newton's 3rd Law of Motion. A lesson activity from integrative STEM education was adapted, modified and enhanced through pilot testing. After revisions, the implementation was done to one class. The respondent's prior knowledge was first assessed by a pretest. PPIT (present the scenario, plan, implement and test) was the framework followed in the implementation of Learning by Design. Worksheets were then utilized to measure their conceptual understanding and perception. A score guide was also used to evaluate the student's output. Paired t-test analysis showed that there is a significant difference in the pretest and posttest achievement scores. This implies that the performance of the students have improved during the implementation of the Learning by Design. The Analysis of variance also depicts that the low, average and high benefited in the Learning by Design approach. The results of this study suggests that Learning by Design is an effective approach in teaching Newton's 3rd Law of Motion and thus be used in a Science classroom.

  20. Editorial: 3rd Special Issue on behavior change, health, and health disparities.

    Science.gov (United States)

    Higgins, Stephen T

    2016-11-01

    This Special Issue of Preventive Medicine (PM) is the 3rd that we have organized on behavior change, health, and health disparities. This is a topic of critical importance to improving U.S. population health. There is broad scientific consensus that personal behaviors such as cigarette smoking, other substance abuse, and physical inactivity/obesity are among the most important modifiable causes of chronic disease and its adverse impacts on population health. Hence, effectively promoting health-related behavior change needs to be a key component of health care research and policy. There is also broad recognition that while these problems extend throughout the population, they disproportionately impact economically disadvantaged populations and other vulnerable populations and represent a major contributor to health disparities. Thus, behavior change represents an essential step in curtailing health disparities, which receives special attention in this 3rd Special Issue. We also devote considerable space to the longstanding challenges of reducing cigarette smoking and use of other tobacco and nicotine delivery products in vulnerable populations, obesity, and for the first time food insecurity. Across each of these topics we include contributions from highly accomplished policymakers and scientists to acquaint readers with recent accomplishments as well as remaining knowledge gaps and challenges. Copyright © 2016 Elsevier Inc. All rights reserved.

  1. The Third International Genomic Medicine Conference (3rd IGMC, 2015: overall activities and outcome highlights

    Directory of Open Access Journals (Sweden)

    Muhammad Abu-Elmagd

    2016-10-01

    Full Text Available Abstract The Third International Genomic Medicine Conference (3rd IGMC was organised by the Centre of Excellence in Genomic Medicine Research (CEGMR at the King Abdulaziz University, Jeddah, Kingdom of Saudi Arabia (KSA. This conference is a continuation of a series of meetings, which began with the first International Genomic Medicine Conference (1st IGMC, 2011 followed by the second International Genomic Medicine Conference (2nd IGMC, 2013. The 3rd IGMC meeting presented as a timely opportunity to bring scientists from across the world to gather, discuss, and exchange recent advances in the field of genomics and genetics in general as well as practical information on using these new technologies in different basic and clinical applications. The meeting undoubtedly inspired young male and female Saudi researchers, who attended the conference in large numbers, as evidenced by the oversubscribed oral and poster presentations. The conference also witnessed the launch of the first content for npj Genomic Medicine, a high quality new journal was established in partnership by CEGMR with Springer Nature and published as part of the Nature Partner Journal series. Here, we present a brief summary report of the 2-day meeting including highlights from the oral presentations, poster presentations, workshops, poster prize-winners and comments from the distinguished scientists.

  2. Extreme and Local 3rd Harmonic Response of Niobium (Nb) Superconductor

    Science.gov (United States)

    Oripov, Bakhrom; Tai, Tamin; Anlage, Steven

    Superconducting Radio Frequency (SRF) cavities are being widely used in new generation particle accelerators. These SRF cavities are based on bulk Nb. Based on the needs of the SRF community to identify defects on Nb surfaces, a novel near-field magnetic microwave microscope was successfully built using a magnetic writer from a conventional magnetic recording hard-disk drive1. This magnetic writer can create an RF magnetic field, localized and strong enough to drive Nb into the vortex state. This probe enables us to locate defects through scanning and mapping of the local electrodynamic response in the multi-GHz frequency range. Recent measurements have shown that 3rd harmonic nonlinear response is far more sensitive to variations in input power and temperature then linear response, thus we mainly study the 3rd harmonic response. Moreover, the superconductor is usually the only source for nonlinear response in our setup, thus there is less chance of having noise or background signal. Understanding the mechanism responsible for this non-linear response is important for improving the performance of SRF cavities. Besides Nb we also study various other superconductors such as MgB2 and the cuprate Bi-Sr-Ca-Cu-O (BSCCO) for potential applications in SRF cavities. This work is funded by US Department of Energy through Grant # DE-SC0012036T and CNAM.

  3. 3rd Circuit hints it may reconsider McNemar reasoning.

    Science.gov (United States)

    1997-10-17

    The [name removed] v. The Disney Store ruling is under criticism and the 3rd U.S. Circuit Court of Appeals may reconsider its 1996 decision to not allow employees who receive disability benefits to sue under the Americans with Disabilities Act (ADA). A panel of 3rd Circuit judges, working on [name removed] v. American Sterilizer Co., asserts that the [name removed] decision should not be used to assume that an individual's ADA claims are barred because of prior representations of disability. [Name removed] is suing American Sterilizer under the retaliation provisions of the ADA. Other courts are criticizing the [name removed] decision, including the District of Columbia Court in [name removed] v. Washington Metropolitan Area Transit Authority. The [name removed] court assets that a statement made in the context of a disability application does not preclude an ADA claim brought by a worker for illegal discrimination because the ADA and the Social Security Act differ in their statutory intent. AIDS advocates state that the [name removed] decision places a plaintiff in the position of having to choose between asserting a legal right or maintaining an income. Alan Epstein, who represented [name removed], is pleased by the criticism but explains that [name removed], who died this summer, will not be vindicated.

  4. Influence of radiofrequency-electromagnetic waves from 3rd-generation cellular phones on fertilization and embryo development in mice.

    Science.gov (United States)

    Suzuki, Satoshi; Okutsu, Miho; Suganuma, Ryota; Komiya, Hiromi; Nakatani-Enomoto, Setsu; Kobayashi, Shunsuke; Ugawa, Yoshikazu; Tateno, Hiroyuki; Fujimori, Keiya

    2017-09-01

    The purpose of this study was to evaluate the effects of 3rd-generation (3G) cellular phone radiofrequency-electromagnetic wave (RF-EMW) exposure on fertilization and embryogenesis in mice. Oocytes and spermatozoa were exposed to 3G cellular phone RF-EMWs, 1.95 GHz wideband code division multiple access, at a specific absorption rate of 2 mW/g for 60 min, or to sham exposure. After RF-EMW exposure, in vitro fertilization and intracytoplasmic sperm injection were performed. Rates of fertilization, embryogenesis (8-cell embryo, blastocyst), and chromosome aberration were compared between the combined spermatozoa and oocyte groups: both exposed, both non-exposed, one exposed, and the other non-exposed. Rates of fertilization, embryogenesis, and blastocyst formation did not change significantly across the four groups. Considering that the degree of exposure in the present study was ≥100 times greater than daily exposure of human spermatozoa and even greater than daily exposure of oocytes, the present results indicate safety of RF-EMW exposure in humans. Bioelectromagnetics. 38:466-473, 2017. © 2017 Wiley Periodicals, Inc. © 2017 Wiley Periodicals, Inc.

  5. PREFACE: 3rd International Symposium on Functional Materials 2009 (ISFM 2009) 3rd International Symposium on Functional Materials 2009 (ISFM 2009)

    Science.gov (United States)

    Kiwon, Kim; Li, Lu; Taehyun, Nam; Jouhyeon, Ahn

    2010-05-01

    The 3rd International Symposium on Functional Materials 2009 (ISFM 2009) and its preconference, Advances in Functional Materials 2009 (AFM 2009), were successfully held in the Republic of Korea from 15-18 June 2009 and in the People's Republic of China from 8-12 June 2009, respectively. The two conferences attracted over 300 oral and poster presentations from over 12 countries including Australia, Canada, China, Germany, Japan, India, Israel, Korea, The Netherlands, Thailand, the UK and the USA. In the two conferences, eight keynote lectures were delivered by S Miyazaki, S A Akbar, D J Singh, C Suryanarayana, M~Greenblatt, H Zhang, T Sato and J Ding. This topical issue of Physica Scripta contains papers presented at the ISFM 2009 and AFM 2009. Keyan Li from Dalian University, People's Republic of China, presents some empirical formulae to estimate the elastic moduli of rocksalt-, zincblende- and chalcopyrite-structured crystals, on the basis of electronegativities of bonded atoms in the crystallographic frame. Min-Jung Kim from Hanyang University, Korea, reports on the preparation and characterization of carboxyl functionalization of magnetite nanoparticles for oligonucleotide immobilization. F Yan from the National University of Singapore studies the fabrication of Bi(Fe0.5Sc0.5)O3-PbTiO3 (BSF-PT) thin films by pulsed laser deposition, and the enhanced magnetic moment with respect to BiFeO3-PbTiO3. Dong-Gil Lee from Pusan National University, Korea, reports on the sterilization of enteropathogenic Escherichia coli using nanofiber TiO2 films prepared by the electrostatic spray method. Sang-Eun Park from the Korea Institute of Science and Technology reports on the study of encapsulated Fe3O4 nanoparticles with a silica thin layer with a reversible capacity of about 363 mAhg-1. Other researchers report on many other exiting achievements in the fields of ferromagnetic materials, magneto-optical materials, thermoelectric materials, shape memory materials, fuel-cell and

  6. Brownfields Samoa Peninsula, CA: Sustainable Solutions for Historic Houses in Northern California, A Voluntary Green Code & Green Rehabilitation Manual

    Science.gov (United States)

    This manual was created to help homeowners choose sustainable strategies for restoring and rehabilitating many of the smaller, Victorian-style, wood-framed houses built in Northern California during the late 1800s and early 1900s.

  7. PREFACE: 3rd International Conference of Mechanical Engineering Research (ICMER 2015)

    Science.gov (United States)

    Mamat, Riazalman; Rahman, Mustafizur; Mohd. Zuki Nik Mohamed, Nik; Che Ghani, Saiful Anwar; Harun, Wan Sharuzi Wan

    2015-12-01

    The 3rd ICMER2015 is the continuity of the NCMER2010. The year 2010 represents a significant milestone in the history for Faculty of Mechanical Engineering, Universiti Malaysia Pahang (UMP) Malaysia with the organization of the first and second national level conferences (1st and 2nd NCMER) at UMP on May 26-27 and Dec 3-4 2010. The Faculty then changed the name from National Conference on Mechanical Engineering Research (NCMER) to International Conference on Mechanical Engineering Research (ICMER) in 2011 and this year, 2015 is our 3rd ICMER. These proceedings contain the selected scientific manuscripts submitted to the conference. It is with great pleasure to welcome you to the "International Conference on Mechanical Engineering Research (ICMER2015)" that is held at Zenith Hotel, Kuantan, Malaysia. The call for papers attracted submissions of over two hundred abstracts from twelve different countries including Japan, Iran, China, Kuwait, Indonesia, Norway, Philippines, Morocco, Germany, UAE and more. The scientific papers published in these proceedings have been revised and approved by the technical committee of the 3rd ICMER2015. All of the papers exhibit clear, concise, and precise expositions that appeal to a broad international readership interested in mechanical engineering, combustion, metallurgy, materials science as well as in manufacturing and biomechanics. The reports present original ideas or results of general significance supported by clear reasoning and compelling evidence, and employ methods, theories and practices relevant to the research. The authors clearly state the questions and the significance of their research to theory and practice, describe how the research contributes to new knowledge, and provide tables and figures that meaningfully add to the narrative. In this edition of ICMER representatives attending are from academia, industry, governmental and private sectors. The plenary and invited speakers will present, discuss, promote and

  8. Aerosol sampling and Transport Efficiency Calculation (ASTEC) and application to surtsey/DCH aerosol sampling system: Code version 1.0: Code description and user's manual

    International Nuclear Information System (INIS)

    Yamano, N.; Brockmann, J.E.

    1989-05-01

    This report describes the features and use of the Aerosol Sampling and Transport Efficiency Calculation (ASTEC) Code. The ASTEC code has been developed to assess aerosol transport efficiency source term experiments at Sandia National Laboratories. This code also has broad application for aerosol sampling and transport efficiency calculations in general as well as for aerosol transport considerations in nuclear reactor safety issues. 32 refs., 31 figs., 7 tabs

  9. CESARR V.2 manual: Computer code for the evaluation of surface storage of low and medium level radioactive waste

    International Nuclear Information System (INIS)

    Moya Rivera, J.A.; Bolado Lavin, R.

    1997-01-01

    CESARR (Code for the safety evaluation of low and medium level radioactive waste storage). This code was developed for the safety probabilistic evaluations in the facilities of low-and medium level radioactive waste storage

  10. Proceedings of the 3rd Workshop of R and D and technologies on Radioactive Waste management. Vol. 1,2

    International Nuclear Information System (INIS)

    1998-01-01

    The sessions present at the 3rd workshops on radioactive waste management are: 1. Bases for the radioactive waste management 2. Capsule fuel barrier 3. Barriers for engineering 4. Geologic barriers 5. The biosphere as barrier

  11. Book review: Social Research: Issues, Methods and Process, 3rd edition, by Tim May, Open University Press, 2001, ISBN 0335206123

    OpenAIRE

    Jones, Keith

    2004-01-01

    The great strength of this book by Tim May ("Social Research: Issues, Methods and Process", 3rd edition ) is its successful negotiation (perhaps navigation) of the relationships between theory and method in (social) research.

  12. 3rd Sino-German Conference “Underground Storage of CO2 and Energy”

    CERN Document Server

    Xie, Heping; Were, Patrick

    2013-01-01

    Anthropogenic greenhouse gas emissions, energy security and sustainability are three of the greatest contemporary global challenges today. This year the Sino-German Cooperation Group “Underground Storage of CO2 and Energy”, is meeting on the 21-23 May 2013 for the second time in Goslar, Germany, to convene its 3rd Sino-German conference on the theme “Clean Energy Systems in the Subsurface: Production, Storage and Conversion”.   This volume is a collection of diverse quality scientific works from different perspectives elucidating on the current developments in CO2 geologic sequestration research to reduce greenhouse emissions including measures to monitor surface leakage, groundwater quality and the integrity of caprock, while ensuring a sufficient supply of clean energy. The contributions herein have been structured into 6 major thematic research themes: Integrated Energy and Environmental Utilization of Geo-reservoirs: Law, Risk Management & Monitoring CO2 for Enhanced Gas and Oil Recovery, Coa...

  13. Report of the 3rd European fusion physics workshop, Segovia 13-15 December 1995

    International Nuclear Information System (INIS)

    Todd, T.N.; Jones, T.T.C.; Moreau, D.; Zohm, H.

    1997-01-01

    The 3rd EFPW was convened in December 1995 at Segovia, with the support of Eurotom and CIEMAT. The established pattern for these meetings was followed, beginning with a range of topical themes of interest to the magnetic confinement fusion research community. Subsequent presentations moved on to summarize progress in experiments on JET and the design activity for ITER. The topical theme this year comprised tokamak operational limits, disruption phenomena and transport issues (including the role of plasma edge effects, dimensionless scaling analysers and 'non-local' dependences). Also discussed were tokamak concept improvements, with additional contributions emphasizing the synergistic role of stellarators. JET highlights reported were the achievements of the experiments with the Mk1 divertor, high fusion performance plasmas, and exploratory work on discharge optimization techniques (such as reversed magnetic shear). This article summarizes the proceedings of the workshop on the topical themes and the JET results, including a number of points raised in the associated discussion sessions. (author)

  14. Nonlinear Dynamics of Memristor Based 2nd and 3rd Order Oscillators

    KAUST Repository

    Talukdar, Abdul Hafiz

    2011-05-01

    Exceptional behaviours of Memristor are illustrated in Memristor based second order (Wien oscillator) and third order (phase shift oscillator) oscillator systems in this Thesis. Conventional concepts about sustained oscillation have been argued by demonstrating the possibility of sustained oscillation with oscillating resistance and dynamic poles. Mathematical models are also proposed for analysis and simulations have been presented to support the surprising characteristics of the Memristor based oscillator systems. This thesis also describes a comparative study among the Wien family oscillators with one Memristor. In case of phase shift oscillator, one Memristor and three Memristors systems are illustrated and compared to generalize the nonlinear dynamics observed for both 2nd order and 3rd order system. Detail explanations are provided with analytical models to simplify the unconventional properties of Memristor based oscillatory systems.

  15. Idaho National Laboratory Quarterly Occurrence Analysis - 3rd Quarter FY-2016

    Energy Technology Data Exchange (ETDEWEB)

    Mitchell, Lisbeth Ann [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2016-09-01

    This report is published quarterly by the Idaho National Laboratory (INL) Quality and Performance Management Organization. The Department of Energy (DOE) Occurrence Reporting and Processing System (ORPS), as prescribed in DOE Order 232.2, “Occurrence Reporting and Processing of Operations Information,” requires a quarterly analysis of events, both reportable and not reportable, for the previous 12 months. This report is the analysis of 73 reportable events (23 from the 3rd Qtr FY-16 and 50 from the prior three reporting quarters), as well as 45 other issue reports (including events found to be not reportable and Significant Category A and B conditions) identified at INL during the past 12 months (16 from this quarter and 29 from the prior three quarters).

  16. Quantification of bone mineral density at 3rd lumbar vertebra by dual photon absorptiometry

    International Nuclear Information System (INIS)

    Fukunaga, Masao; Otsuka, Nobuaki; Ono, Shimato; Nagai, Kiyohisa; Muranaka, Akira; Furukawa, Takako; Yanagimoto, Shinichi; Tomomitsu, Tatsushi; Morita, Rikushi

    1987-01-01

    To know bone mineral content of both cortical and spongy bones with aging and pathologic changes, bone mineral density (BMD) in the 3rd lumbar vertebra (L3) and distal radius (DR) was measured using dual photon absorptiometry and single photon absorptiometry, respectively, in 151 normal subjects (N) and four patients with primary hyperparathyroidism (PHP). In the N group, BMD in both L3 and DR decreased with aging. This was more noted, and occurred earlier in L3, irrespective of sex, than DR. In three PHP patients manifested as bone type, BMD was high in L3, and low in DR. Such a tendency was not seen in the remaining one patient with stone type PHP. The findings suggest the need to measure BMD in both cortical (L3) and spongy (DR) bones for elucidating bone pathophysiology in metabolic bone disease. (Namekawa, K.)

  17. The Perception of Entrepreneurial and 3rd Generation University in Turkey

    Directory of Open Access Journals (Sweden)

    Deniz Zungun

    2016-07-01

    Full Text Available Increased competition caused by globalization has led to philosophical changes in private and public businesses. This situation has affected educational institutions and they have needed dynamic, innovator and transformational tools in order to survive in competitive environment. The universities defined as �3rd Generation Universities� need commercialization, network among universities, close co-operation among institutions and entrepreneurship as well as intellectual and innovative changes. In this regard, the aim of the research is formed by the analysis of �Entrepreneur University� concept from the perspective of the academicians that served at managerial positions at the universities in Turkey. The research is limited to the opinions of the academicians that served at top, middle and lower management at randomly chosen 20 universities.

  18. 3rd International Doctoral Symposium on Applied Computation and Security Systems

    CERN Document Server

    Saeed, Khalid; Cortesi, Agostino; Chaki, Nabendu

    2017-01-01

    This book presents extended versions of papers originally presented and discussed at the 3rd International Doctoral Symposium on Applied Computation and Security Systems (ACSS 2016) held from August 12 to 14, 2016 in Kolkata, India. The symposium was jointly organized by the AGH University of Science & Technology, Cracow, Poland; Ca’ Foscari University, Venice, Italy; and the University of Calcutta, India. The book is divided into two volumes, Volumes 3 and 4, and presents dissertation works in the areas of Image Processing, Biometrics-based Authentication, Soft Computing, Data Mining, Next-Generation Networking and Network Security, Remote Healthcare, Communications, Embedded Systems, Software Engineering and Service Engineering. The first two volumes of the book published the works presented at the ACSS 2015, which was held from May 23 to 25, 2015 in Kolkata, India.

  19. Interviews with Michael Baxandall, February 3rd and 4th, 1994, Berkeley, CA

    Directory of Open Access Journals (Sweden)

    Allan Langdale

    2009-12-01

    Full Text Available The following interviews with Michael Baxandall were conducted in Berkeley on February 3rd and 4th of 1994. The content of these interviews include general responses about developments in art history in the years between 1960 and 1985, a period of dramatic modifications in the discipline. Among the issues are the rise of the social history of art and the sources from anthropology that informed Baxandall’s concept of the ‘Period Eye’. Baxandall talks about his own work, his personal intellectual history, and the scholars of past and current generations who influenced him. Other topics include Baxandall’s professional trajectory, the Warburg Library, and aspects of cultural history having to do with Renaissance Humanism. These interviews first appeared as an appendix to the PhD dissertation by Allan Langdale, Art History and Intellectual History: Michael Baxandall’s Work between 1963 and 1985, U. C. Santa Barbara, 1995.

  20. Summary of the 3rd workshop on human resources development (HRD) in FNCA. FY2001

    International Nuclear Information System (INIS)

    2002-07-01

    The Human Resources Development (HRD) Project was added in 1999 to the Cooperation Activities of 'the Forum for Nuclear Cooperation in Asia (FNCA)' which is organized by AEC of Japan. The HRD Project supports to solidify the foundation of nuclear development utilization in Asia by promoting human resources development in Asian countries. The principal activity of the HRD Project is to hold the Workshop on Human Resources Development in the Nuclear Field in Asia once a year. The objective of the Workshop is to clarify problems and needs of the human resources development of each country and to support mutually by exchanging information etc. The report consists of the summary of the 3rd Workshop on Human Resources Development in the Nuclear Field in Asia held on October 29 - November 1, 2001 at the Nuclear Training Center of the Korea Atomic Energy Research Institute in Daejeon, Korea. (author)

  1. Dental health in antique population of Vinkovci - Cibalae in Croatia (3rd-5th century).

    Science.gov (United States)

    Peko, Dunja; Vodanović, Marin

    2016-08-01

    Roman city Cibalae (Vinkovci) - the birthplace of Roman emperors Valentinian I and Valens was a very well developed urban ares in the late antique what was evidenced by numerous archaeological findings. The aim of this paper is to get insight in dental health of antique population of Cibalae. One hundred individuals with 2041 teeth dated to 3rd - 5th century AD have been analyzed for caries, antemortem tooth loss, periapical diseases and tooth wear. Prevalence of antemortem tooth loss was 4.3% in males, 5.2% in females. Prevalence of caries per tooth was 8.4% in males, 7.0% in females. Compared to other Croatian antique sites, ancient inhabitants of Roman Cibalae had rather good dental health with low caries prevalence and no gender differences. Statistically significant difference was found between males in females in the prevalence of periapical lesions and degree of tooth wear. Periapical lesions were found only in males.

  2. 3rd International Asia Conference on Informatics in Control, Automation and Robotics

    CERN Document Server

    Informatics in Control, Automation and Robotics

    2012-01-01

    Session 2 includes 110 papers selected from 2011 3rd International Asia Conference on Informatics in Control, Automation and Robotics (CAR 2011), held on December 24-25, 2011, Shenzhen, China.   As we all know, the ever growing technology in robotics and automation will help build a better human society. This session will provide a unique opportunity for the academic and industrial communities to address new challenges, share solutions, and discuss research directions for the future. Robotics research emphasizes intelligence and adaptability to cope with unstructured environments. Automation research emphasizes efficiency, productivity, quality, and reliability, focusing on systems that operate autonomously. The main focus of this session is on the autonomous acquisition of semantic information in intelligent robots and systems, as well as the use of semantic knowledge to guide further acquisition of information.

  3. 3rd International Summer School Nanotechnology : From Fundamental Research to Innovations

    CERN Document Server

    Yatsenko, Leonid

    2015-01-01

    This book highlights the most recent advances in nanoscience from leading researchers in Ukraine, Europe, and beyond.  It features contributions from participants of the 3rd International Summer School “Nanotechnology: From Fundamental Research to Innovations,” held in Yaremche, Ukraine on August 23-26, 2014 and of the 2nd International NANO-2014 Conference, held in Lviv, Ukraine on August 27-30, 2014.  These events took place within the framework of the European Commission FP7 project Nanotwinning, and were organized jointly by the Institute of Physics of the National Academy of Sciences of Ukraine, University of Tartu (Estonia), University of Turin (Italy), and Pierre and Marie Curie University (France).  Internationally recognized experts from a wide range of universities and research institutions share their knowledge and key results in the areas of nanocomposites and nanomaterials, nanostructured surfaces, microscopy of nano-objects, nano-optics and nanophotonics, nanoplasmonics, nanochemistry, na...

  4. 3rd International Conference on Simulation and Modeling Methodologies, Technologies and Applications

    CERN Document Server

    Koziel, Slawomir; Kacprzyk, Janusz; Leifsson, Leifur; Ören, Tuncer

    2015-01-01

    This book includes extended and revised versions of a set of selected papers from the 3rd International Conference on Simulation and Modeling Methodologies, Technologies and Applications (SIMULTECH 2013) which was co-organized by the Reykjavik University (RU) and sponsored by the Institute for Systems and Technologies of Information, Control and Communication (INSTICC). SIMULTECH 2013 was held in cooperation with the ACM SIGSIM - Special Interest Group (SIG) on SImulation and Modeling (SIM), Movimento Italiano Modellazione e Simulazione (MIMOS) and AIS Special Interest Group on Modeling and Simulation (AIS SIGMAS) and technically co-sponsored by the Society for Modeling & Simulation International (SCS), Liophant Simulation, Simulation Team and International Federation for Information Processing (IFIP). This proceedings brings together researchers, engineers, applied mathematicians and practitioners working in the advances and applications in the field of system simulation.

  5. Analysis of coherence properties of 3-rd generation synchrotron sources and free-electron lasers

    International Nuclear Information System (INIS)

    Vartanyants, I.A.; Singer, A.

    2009-07-01

    A general theoretical approach based on the results of statistical optics is used for the analysis of the transverse coherence properties of 3-rd generation synchrotron sources and X-ray free-electron lasers (XFEL). Correlation properties of the wave elds are calculated at different distances from an equivalent Gaussian Schell-model source. This model is used to describe coherence properties of the five meter undulator source at the synchrotron storage ring PETRA III. In the case of XFEL sources the decomposition of the statistical fields into a sum of independently propagating transverse modes is used for the analysis of the coherence properties of these new sources. A detailed calculation is performed for the parameters of the SASE1 undulator at the European XFEL. It is demonstrated that only a few modes contribute significantly to the total radiation field of that source. (orig.)

  6. 3rd International Conference on Modelling and Management of Engineering Processes

    CERN Document Server

    Gericke, Kilian; Szélig, Nikoletta; Vajna, Sándor

    2015-01-01

    Innovative processes for the development of products and services are more and more considered as an organisational capability, which is recognised to be increasingly important for business success in today’s competitive environment. However, management and academia need a more profound understanding of these processes in order to develop improved management approaches to exploit business potentials. This book contains the proceedings of the 3rd International Conference on Modelling and Management of Engineering Processes (MMEP2013) held in Magdeburg, Germany, in November 2013. It includes contributions from international leading researchers in the fields of process modelling and process management. The conference topics were recent trends in modelling and management of engineering processes, potential synergies between different modelling approaches, future challenges for the management of engineering processes as well as future research in these areas.

  7. Analysis of coherence properties of 3-rd generation synchrotron sources and free-electron lasers

    Energy Technology Data Exchange (ETDEWEB)

    Vartanyants, I.A.; Singer, A. [HASYLAB at Deutsches Elektronen-Synchrotron DESY, Hamburg (Germany)

    2009-07-15

    A general theoretical approach based on the results of statistical optics is used for the analysis of the transverse coherence properties of 3-rd generation synchrotron sources and X-ray free-electron lasers (XFEL). Correlation properties of the wave elds are calculated at different distances from an equivalent Gaussian Schell-model source. This model is used to describe coherence properties of the five meter undulator source at the synchrotron storage ring PETRA III. In the case of XFEL sources the decomposition of the statistical fields into a sum of independently propagating transverse modes is used for the analysis of the coherence properties of these new sources. A detailed calculation is performed for the parameters of the SASE1 undulator at the European XFEL. It is demonstrated that only a few modes contribute significantly to the total radiation field of that source. (orig.)

  8. 3rd international KES conference on Smart Education and Smart e-Learning

    CERN Document Server

    Howlett, Robert; Jain, Lakhmi

    2016-01-01

    This book contains the contributions presented at the 3rd international KES conference on Smart Education and Smart e-Learning, which took place in Puerto de la Cruz, Tenerife, Spain, June 15-17, 2016. It contains a total of 56 peer-reviewed book chapters that are grouped into several parts: Part 1 - Smart University: Conceptual Modeling, Part 2 – Smart Education: Research and Case Studies, Part 3 – Smart e-Learning, Part 4 – Smart Education: Software and Hardware Systems, and Part 5 – Smart Technology as a Resource to Improve Education and Professional Training. We believe that the book will serve as a useful source of research data and valuable information for faculty, scholars, Ph.D. students, administrators, and practitioners - those who are interested in innovative areas of smart education and smart e-learning. .

  9. [3rd and 4th generation estroprogestatives French controversy: What effect on women's behavior?].

    Science.gov (United States)

    Torres, Luis; Frapard, Christian; Daumas, Aurélie; Guibert, Nicolas; Lagouanelle-Simeoni, Marie-Claude; Rakoto, Jean-Claude; Villani, Patrick; Sambuc, Roland

    2016-04-01

    The primary objective of this study was to determine the reasons given by women who have changed or suspended their contraceptive method in 2013. What influence had the 3rd and 4th generation estroprogestatives (EP) French controversy and advices from doctors? Did they notice any consequences of the controversy on their lifestyle? Did they feel an impact on their behavior to health professionals? A study was conducted on women of childbearing age. Data collection took place between November 4 and December 16, 2013. The included subjects were between 18 and 55 years old females. Subjects were surveyed through an anonymous self-administered questionnaire distributed through pharmacies. The protocol called for the construction of clusters of subjects by having heard about, or not, of the controversy. Patients reporting having heard about the controversy have formed the "exposed" group while the others have formed the "unexposed" group. We compared two parameters between these two groups: the rate of subjects who reported having modified or suspended their contraceptive method in 2013 on one hand, and the rate of subjects who reported having made a change in their contraceptive method without or against advices from a doctor on the other hand. The sample included 988 subjects. The average age was 34 years. The level of exposure to media debates was 86.5%. Of the respondents, 19.8% were under 3rd or 4th generation EP in 2012, thus directly involved in the discussions and affected by health recommendations. Of the patients, 38.5% reported having changed their contraception in 2013. In these women, when they confirmed having heard about the controversy, 40.1% of them claimed to have conducted this process without or against advices from a doctor. This number dropped to 18.2% for those who had not heard of it. Media coverage of the 3rd and 4th generation EP vascular risk was not mentioned more by patients who suspended all medical contraceptive method than it was by

  10. Proceedings of the 3rd international symposium on material chemistry in nuclear environment (MATERIAL CHEMISTRY '02)

    International Nuclear Information System (INIS)

    2003-03-01

    The volume contains all presented papers during the 3rd International Symposium on Material Chemistry in Nuclear Environment: MATERIAL CHEMISTRY 02 (MC'02), held March 13-15, 2002. The purpose of this symposium is to provide an international forum for the discussion of recent progress in the field of materials chemistry in nuclear environments. This symposium intends to build on the success of the previous symposiums held in Tsukuba in 1992 and 1996. The topics discussed in the symposium MC'02 are Chemical Reaction and Thermodynamics, Degradation Phenomena, New Characterization Technology, Fabrication and New Materials, Composite Materials, Surface Modification, and Computational Science. The 61 of the presented papers are indexed individually. (J.P.N.)

  11. Proceedings of the 3rd seminar of R and D on advanced ORIENT (International)

    International Nuclear Information System (INIS)

    Sasaki, Yuji; Ozawa, Masaki

    2010-03-01

    The 3rd Seminar of R and D on advanced ORIENT (International) was held at Tohoku University, on October 30th, 2009 organized by Japan Atomic Energy Agency. The first meeting of this seminar was held at Oarai, Ibaraki on May, 2007, and the second seminar was held at Tokai, Ibaraki on November, 2008. This seminar has the world-wide concept and includes the main topics from foreign researchers. Spent nuclear fuel should be recognized not only mass of radioactive elements but also potentially useful materials including platinum metals and rare earth elements. Taking the cooperation with universities related companies and research institutes, into consideration, we aimed at expanding and progressing the basic researches. This report records abstracts and figures submitted from the oral speakers in this seminar. (author)

  12. 3rd International Arab Forensic Sciences & Forensic Medicine Conference, ASFSFM 2017: Conference Report

    Directory of Open Access Journals (Sweden)

    Abdulsallam A. Bakdash

    2017-12-01

    Full Text Available The Arab Society for Forensic Sciences and Forensic Medicine (ASFSFM at Naif Arab University for Security Sciences seeks to present the latest developments in all fields of forensic sciences through holding specialized scientific events and academic activities. This is also achieved through its periodic scientific peer-reviewed journal, the Arab Journal of Forensic Sciences and Forensic Medicine. It also seeks to promote scientific research in all fields of forensic science and forensic medicine, and seeks actively to contribute in holding scientific meetings in accordance with advanced scientific standards, including the 3rd International Arab Forensic Sciences & Forensic Medicine Conference. This important event was attended by scientists and experts from various fields of criminal and forensic sciences from both Arab and non-Arab countries. This conference was a significant scientific accomplishment that contributed to the advancement of forensic sciences and forensic medicine in the Arab world. The conference aimed, in accordance with the vision of Naif Arab University for Security Sciences, to enhance peace, security and justice in Arab societies.  Naif Arab University for Security Sciences, represented by the Arab Society for Forensic Sciences and Forensic Medicine, held the 3rd International Arab Forensic Sciences & Forensic Medicine Conference on the University's campus during the period from 21st to 23rd November 2017. The event included the participation of more than 720 experts in forensic sciences and forensic medicine from 33 countries all over the world. Experts discussed and presented the latest developments in their fields. The conference provided a creative environment for students from both local and international universities to benefit from experts and specialists, and to access the most recent research.  On behalf of His Excellency the president of Naif Arab University for Security Sciences, and the Arab Society for

  13. User's manual for the BNW-II optimization code for dry/wet-cooled power plants

    Energy Technology Data Exchange (ETDEWEB)

    Braun, D.J.; Bamberger, J.A.; Braun, D.J.; Faletti, D.W.; Wiles, L.E.

    1978-05-01

    This volume provides a listing of the BNW-II dry/wet ammonia heat rejection optimization code and is an appendix to Volume I which gives a narrative description of the code's algorithms as well as logic, input and output information.

  14. COBRA-SFS [Spent Fuel Storage]: A thermal-hydraulic analysis computer code: Volume 2, User's manual

    International Nuclear Information System (INIS)

    Rector, D.R.; Cuta, J.M.; Lombardo, N.J.; Michener, T.E.; Wheeler, C.L.

    1986-11-01

    COBRA-SFS (Spent Fuel Storage) is a general thermal-hydraulic analysis computer code used to predict temperatures and velocities in a wide variety of systems. The code was refined and specialized for spent fuel storage system analyses for the US Department of Energy's Commercial Spent Fuel Management Program. The finite-volume equations governing mass, momentum, and energy conservation are written for an incompressible, single-phase fluid. The flow equations model a wide range of conditions including natural circulation. The energy equations include the effects of solid and fluid conduction, natural convection, and thermal radiation. The COBRA-SFS code is structured to perform both steady-state and transient calculations; however, the transient capability has not yet been validated. This volume contains the input instructions for COBRA-SFS and an auxiliary radiation exchange factor code, RADX-1. It is intended to aid the user in becoming familiar with the capabilities and modeling conventions of the code

  15. Recent developments at 3rd generation storage ring light sources (2/4)

    CERN Multimedia

    CERN. Geneva

    2009-01-01

    Over the last decade, many 3rd generation storage ring light sources have been built and put into operation. Progressively, significant improvements have been brought to the machine performances and experiences developed at the first facilities have benefited to the most recently built ones. Most of the recent facilities are now featuring small emittances, high current together with high position stability. The small sizes of the electron beam at the source points impose achieving position stabilities in the sub micron range. The technology to build the insertion devices that produce the photon beams has reached a very mature state and enables 3 GeV medium energy /medium size machines to produce high brilliance beams up to the hard X-Ray range (10 - 30 keV). The designing of the optical set-up of a beamline includes now the choice of the best suited undulator. All these facilities are operated as “photon factories” and deliver their beams to many beamlines over several thousands hours per year. Some re...

  16. Recent developments at 3rd generation storage ring light sources (4/4)

    CERN Multimedia

    CERN. Geneva

    2009-01-01

    Over the last decade, many 3rd generation storage ring light sources have been built and put into operation. Progressively, significant improvements have been brought to the machine performances and experiences developed at the first facilities have benefited to the most recently built ones. Most of the recent facilities are now featuring small emittances, high current together with high position stability. The small sizes of the electron beam at the source points impose achieving position stabilities in the sub micron range. The technology to build the insertion devices that produce the photon beams has reached a very mature state and enables 3 GeV medium energy /medium size machines to produce high brilliance beams up to the hard X-Ray range (10 - 30 keV). The designing of the optical set-up of a beamline includes now the choice of the best suited undulator. All these facilities are operated as “photon factories” and deliver their beams to many beamlines over several thousands hours per year. Some re...

  17. Recent developments at 3rd generation storage ring light sources (3/4)

    CERN Multimedia

    CERN. Geneva

    2009-01-01

    Over the last decade, many 3rd generation storage ring light sources have been built and put into operation. Progressively, significant improvements have been brought to the machine performances and experiences developed at the first facilities have benefited to the most recently built ones. Most of the recent facilities are now featuring small emittances, high current together with high position stability. The small sizes of the electron beam at the source points impose achieving position stabilities in the sub micron range. The technology to build the insertion devices that produce the photon beams has reached a very mature state and enables 3 GeV medium energy /medium size machines to produce high brilliance beams up to the hard X-Ray range (10 - 30 keV). The designing of the optical set-up of a beamline includes now the choice of the best suited undulator. All these facilities are operated as “photon factories” and deliver their beams to many beamlines over several thousands hours per year. Some re...

  18. Recent developments at 3rd generation storage ring light sources (1/4)

    CERN Multimedia

    CERN. Geneva

    2009-01-01

    Over the last decade, many 3rd generation storage ring light sources have been built and put into operation. Progressively, significant improvements have been brought to the machine performances and experiences developed at the first facilities have benefited to the most recently built ones. Most of the recent facilities are now featuring small emittances, high current together with high position stability. The small sizes of the electron beam at the source points impose achieving position stabilities in the sub micron range. The technology to build the insertion devices that produce the photon beams has reached a very mature state and enables 3 GeV medium energy /medium size machines to produce high brilliance beams up to the hard X-Ray range (10 - 30 keV). The designing of the optical set-up of a beamline includes now the choice of the best suited undulator. All these facilities are operated as “photon factories” and deliver their beams to many beamlines over several thousands hours per year. Some re...

  19. Proceedings of the 3rd topical meeting on FEL and high power radiation

    International Nuclear Information System (INIS)

    Hiramatsu, Shigenori

    1994-01-01

    The meeting was held on June 10 and 11, 1993, at the National Laboratory for High Energy Physics. This is the joint study meeting with 31st large power microwave-milliwave study meeting. At the meeting, lectures were given on the report of 1st Asia FEL study meeting, infrared free electron laser (FEL) project in JAERI, present state of Free Electron Laser Research Institute Inc., infrared FEL experiment in the Institute of Scientific and Industrial Research, Osaka University, FEL experiment in UVSOR storage ring, NIJI-4 SRFEL, simulation of FEL oscillation in photo-klystron, vacuum UVFEL in PF, beam characteristics of small photon storage ring, micro-cherenkov FEL using field emission array, coherent spontaneous emission and radiation build-up in FEL oscillator, stability of soft X-ray multilayers under exposure to multipole Wigger radiation, long life Zn 2 excimer excited with relativistic electron beam, development of large power klystron in KEK, design of 1 THz gyrotron and first experiment, experiment of relativistic peniotron, experiments of 3rd and 10th cyclotron harmonic peniotron oscillators and others. (K.I.)

  20. The 3rd international intercomparison on EPR tooth dosimetry: Part 1, general analysis

    International Nuclear Information System (INIS)

    Wieser, A.; Debuyst, R.; Fattibene, P.

    2005-01-01

    The objective of the 3rd International Intercomparison on Electron Paramagnetic Resonance (EPR) Tooth Dosimetry was the evaluation of laboratories performing tooth enamel dosimetry below 300 mGy. Participants had to reconstruct the absorbed dose in tooth enamel from 11 molars, which were cut into two halves. One half of each tooth was irradiated in a 60 Co beam to doses in the ranges of 30-100 mGy (5 samples), 100-300 mGy (5 samples), and 300-900 mGy (1 sample). Fourteen international laboratories participated in this intercomparison programme. A first analysis of the results and an overview of the essential features of methods applied in different laboratories are presented. The relative standard deviation of results of all methods was better than 27% for applied doses in the range of 79-704 mGy. In the analysis of the unirradiated tooth halves 8% of the samples were identified as outliers with additional absorbed dose above background dose

  1. Effects of notetaking instruction on 3rd grade student's science learning and notetaking behavior

    Science.gov (United States)

    Lee, Pai-Lin

    The research examined effects of notetaking instruction on elementary-aged students' ability to recall science information and notetaking behavior. Classes of 3rd grade students were randomly assigned to three treatment conditions, strategic notetaking, partial strategic notetaking, and control, for 4 training sessions. The effects of the notetaking instruction were measured by their performances on a test on science information taught during the training, a long-term free recall of the information, and number of information units recalled with or without cues. Students' prior science achievement was used to group students into two levels (high vs. low) and functioned as another independent variable in analysis. Results indicated significant treatment effect on cued and non-cued recall of the information units in favor of the strategy instruction groups. Students with higher prior achievement in science performed better on cued recall and long-term free recall of information. The results suggest that students as young as at the third grade can be instructed to develop the ability of notetaking that promotes their learning.

  2. A critical experimental test of synchrotron radiation theory with 3rd generation light source

    Energy Technology Data Exchange (ETDEWEB)

    Geloni, Gianluca [European XFEL GmbH, Hamburg (Germany); Kocharyan, Vitali; Saldin, Evgeni [Deutsches Elektronen-Synchrotron (DESY), Hamburg (Germany)

    2016-05-15

    A recent ''beam splitting'' experiment at LCLS apparently demonstrated that after a microbunched electron beam is kicked on a large angle compared to the divergence of the FEL radiation, the microbunching wave front is readjusted along the new direction of motion of the kicked beam. Therefore, coherent radiation from an undulator placed after the kicker is emitted along the kicked direction without suppression. This strong emission of coherent undulator radiation in the kicked direction cannot be explained in the framework of conventional synchrotron radiation theory. In a previous paper we explained this puzzle. We demonstrated that, in accelerator physics, the coupling of fields and particles is based, on the one hand, on the use of results from particle dynamics treated according to the absolute time convention and, on the other hand, on the use of Maxwell equations treated according to the standard (Einstein) synchronization convention. Here lies the misconception which led to the strong qualitative disagreement between theory and experiment. After the ''beam splitting'' experiment at LCLS, it became clear that the conventional theory of synchrotron radiation cannot ensure the correct description of coherent and spontaneous emission from a kicked electron beam, nor the emission from a beam with finite angular divergence, in an undulator or a bending magnet. However, this result requires further experimental confirmation. In this publication we propose an uncomplicated and inexpensive experiment to test synchrotron radiation theory at 3rd generation light sources.

  3. A critical experimental test of synchrotron radiation theory with 3rd generation light source

    International Nuclear Information System (INIS)

    Geloni, Gianluca; Kocharyan, Vitali; Saldin, Evgeni

    2016-05-01

    A recent ''beam splitting'' experiment at LCLS apparently demonstrated that after a microbunched electron beam is kicked on a large angle compared to the divergence of the FEL radiation, the microbunching wave front is readjusted along the new direction of motion of the kicked beam. Therefore, coherent radiation from an undulator placed after the kicker is emitted along the kicked direction without suppression. This strong emission of coherent undulator radiation in the kicked direction cannot be explained in the framework of conventional synchrotron radiation theory. In a previous paper we explained this puzzle. We demonstrated that, in accelerator physics, the coupling of fields and particles is based, on the one hand, on the use of results from particle dynamics treated according to the absolute time convention and, on the other hand, on the use of Maxwell equations treated according to the standard (Einstein) synchronization convention. Here lies the misconception which led to the strong qualitative disagreement between theory and experiment. After the ''beam splitting'' experiment at LCLS, it became clear that the conventional theory of synchrotron radiation cannot ensure the correct description of coherent and spontaneous emission from a kicked electron beam, nor the emission from a beam with finite angular divergence, in an undulator or a bending magnet. However, this result requires further experimental confirmation. In this publication we propose an uncomplicated and inexpensive experiment to test synchrotron radiation theory at 3rd generation light sources.

  4. Hypertrophic osteoarthropathy in a young adult male from Berber, Sudan (2nd-3rd century CE).

    Science.gov (United States)

    Binder, M; Saad, M

    2017-09-01

    Hypertrophic osteoarthropathy (HOA) is a pathological condition characterised by extensive periosteal new bone formation (NBF) on the diaphyses of the long bones, metacarpal and metatarsal bones. In modern clinical contexts, the secondary form of the disease is common and most often occurs secondary to intra-thoracic cancer and other forms of chronic pulmonary disease. Paleopathological evidence for HOA on the other hand has only occasionally been reported. Here we report a young adult male from the Meriotic cemetery at Berber in Sudan (2nd-3rd century CE) displaying widespread NBF on the diaphyses of the upper and lower limb bones, metacarpal and metatarsal bones, as well as the pelvis and scapulae. While several pathological conditions have to be considered as differential diagnostic options for NBF in the post-cranial skeleton, HOA is the most likely diagnosis, based on the distribution of the changes observed in this individual, as well as their macroscopic and radiographic characteristics. A chronic pulmonary condition as indicated by NBF on the visceral side of the ribs may represent the underlying cause for the HOA. This individual represents the first paleopathological case of HOA reported from an archaeological site in Africa. Copyright © 2017 Elsevier Inc. All rights reserved.

  5. Visual, Critical, and Scientific Thinking Dispositions in a 3rd Grade Science Classroom

    Science.gov (United States)

    Foss, Stacy

    Many American students leave school without the required 21st century critical thinking skills. This qualitative case study, based on the theoretical concepts of Facione, Arheim, and Vygotsky, explored the development of thinking dispositions through the arts in science on the development of scientific thinking skills when used as a conceptual thinking routine in a rural 3rd grade classroom. Research questions examined the disposition to think critically through the arts in science and focused on the perceptions and experiences of 25 students with the Visual Thinking Strategy (VTS) process. Data were collected from classroom observations (n = 10), student interviews (n = 25), teacher interviews ( n = 1), a focus group discussion (n = 3), and artifacts of student work (n = 25); these data included perceptions of VTS, school culture, and classroom characteristics. An inductive analysis of qualitative data resulted in several emergent themes regarding disposition development and students generating questions while increasing affective motivation. The most prevalent dispositions were open-mindedness, the truth-seeking disposition, the analytical disposition, and the systematicity disposition. The findings about the teachers indicated that VTS questions in science supported "gradual release of responsibility", the internalization of process skills and vocabulary, and argumentation. This case study offers descriptive research that links visual arts inquiry and the development of critical thinking dispositions in science at the elementary level. A science curriculum could be developed, that emphasizes the development of thinking dispositions through the arts in science, which in turn, could impact the professional development of teachers and learning outcomes for students.

  6. Regional apparent diffusion coefficient values in 3rd trimester fetal brain

    International Nuclear Information System (INIS)

    Hoffmann, Chen; Weisz, Boaz; Lipitz, Shlomo; Katorza, Eldad; Yaniv, Gal; Bergman, Dafi; Biegon, Anat

    2014-01-01

    Apparent diffusion coefficient (ADC) values in the developing fetus can be used in the diagnosis and prognosis of prenatal brain pathologies. To this end, we measured regional ADC in a relatively large cohort of normal fetal brains in utero. Diffusion-weighted imaging (DWI) was performed in 48 non-sedated 3rd trimester fetuses with normal structural MR imaging results. ADC was measured in white matter (frontal, parietal, temporal, and occipital lobes), basal ganglia, thalamus, pons, and cerebellum. Regional ADC values were compared by one-way ANOVA with gestational age as covariate. Regression analysis was used to examine gestational age-related changes in regional ADC. Four other cases of CMV infection were also examined. Median gestational age was 32 weeks (range, 26-33 weeks). There was a highly significant effect of region on ADC, whereby ADC values were highest in white matter, with significantly lower values in basal ganglia and cerebellum and the lowest values in thalamus and pons. ADC did not significantly change with gestational age in any of the regions tested. In the four cases with fetal CMV infection, ADC value was associated with a global decrease. ADC values in normal fetal brain are relatively stable during the third trimester, show consistent regional variation, and can make an important contribution to the early diagnosis and possibly prognosis of fetal brain pathologies. (orig.)

  7. Regional apparent diffusion coefficient values in 3rd trimester fetal brain

    Energy Technology Data Exchange (ETDEWEB)

    Hoffmann, Chen [Tel Aviv University, Department of Radiology, Sheba Medical Center, Tel Hashomer (affiliated to the Sackler School of Medicine), Tel Aviv (Israel); Sheba Medical Center, Diagnostic Imaging, 52621, Tel Hashomer (Israel); Weisz, Boaz; Lipitz, Shlomo; Katorza, Eldad [Tel Aviv University, Department of Obstetrics and Gynecology, Sheba Medical Center, Tel Hashomer (affiliated to the Sackler School of Medicine), Tel Aviv (Israel); Yaniv, Gal; Bergman, Dafi [Tel Aviv University, Department of Radiology, Sheba Medical Center, Tel Hashomer (affiliated to the Sackler School of Medicine), Tel Aviv (Israel); Biegon, Anat [Stony Brook University School of Medicine, Department of Neurology, Stony Brook, NY (United States)

    2014-07-15

    Apparent diffusion coefficient (ADC) values in the developing fetus can be used in the diagnosis and prognosis of prenatal brain pathologies. To this end, we measured regional ADC in a relatively large cohort of normal fetal brains in utero. Diffusion-weighted imaging (DWI) was performed in 48 non-sedated 3rd trimester fetuses with normal structural MR imaging results. ADC was measured in white matter (frontal, parietal, temporal, and occipital lobes), basal ganglia, thalamus, pons, and cerebellum. Regional ADC values were compared by one-way ANOVA with gestational age as covariate. Regression analysis was used to examine gestational age-related changes in regional ADC. Four other cases of CMV infection were also examined. Median gestational age was 32 weeks (range, 26-33 weeks). There was a highly significant effect of region on ADC, whereby ADC values were highest in white matter, with significantly lower values in basal ganglia and cerebellum and the lowest values in thalamus and pons. ADC did not significantly change with gestational age in any of the regions tested. In the four cases with fetal CMV infection, ADC value was associated with a global decrease. ADC values in normal fetal brain are relatively stable during the third trimester, show consistent regional variation, and can make an important contribution to the early diagnosis and possibly prognosis of fetal brain pathologies. (orig.)

  8. 3rd symposium on tires and chassis; 3. Symposium Reifen und Fahrwerk

    Energy Technology Data Exchange (ETDEWEB)

    Geringer, B.; Stumpf, H. (comps.)

    2005-07-01

    The present volume contains the talks, which were held at the 3rd symposium on ''Tires and chassis'' at the Institute for combustion machines at the Technical University Vienna on 26th September 2005 in cooperation with UAMTTC and Semperit Reifen Ges.m.H. Apart from technical improvements on chassis, tires and carriageway the overall perspective will get more important in the future, which also includes the driver, the neighbour, the environment and the traffic policy. Due to an increasing number of international participants, discussions can be expected, which will take into consideration extraordinary and manifold perspectives. The third symposium on ''Tires and chassis'' discusses the following developments, of which some are evolutionary. (a) Tire engineering; environmental aspects of tires, roll resistance of tires, driving comfort of tires, winter tires for passenger vehicles and trucks. (b) vehicle engineering, engineering of a race car chassis by means of telemetric measuring data acquisition; simulation of steering wheel vibrations on a complete vehicle test stand. (c) Vehicle steering; chassis of tracklaying vehicles; automatic air pressure control. (orig.)

  9. Book Review: Guide to computer forensics and investigations (3rd ed.

    Directory of Open Access Journals (Sweden)

    Keyu Jiang

    2008-09-01

    Full Text Available Nelson, B., Phillips, A., Enfinger, F., & Steuart, C. (2008. Guide to computer forensics and investigations (3rd ed.. New Jersey: Pearson Education, Inc. 693 pages, ISBN: 1-4180-6733-4 (paper.Reviewed by Keyu Jiang (kjiang@fhsu.edu and Ruifeng Xuan (r_xuan@scatcat.fhsu.edu, Department of Information Networking and Telecommunications, Fort Hays State University, Hays, KS 67601Nelson, Phillips, Enfinger, and Steuart’s book is about the science of computer forensics and its implications in crime investigations. This book is not intended to provide comprehensive training in computer forensics, but introduce the science the science of computer forensics and its implications in crime investigations.  It focused on establishing a solid foundation for those who are new to this field.  Nelson, Philips, Enfiger, and Steuart are experienced experts in different areas of computer forensics.  Different expertise makes this book could benefit many groups of people at different educational level and industrial background.(see PDF for full review

  10. The 2001 activities and the 3rd workshop of the human resources development project in FNCA

    International Nuclear Information System (INIS)

    2002-07-01

    In 1999, the Project for Human Resources Development (HRD) was initiated as defined in the framework of the Forum for Nuclear Cooperation in Asia (FNCA), organized by the Atomic Energy Commission of Japan. The objective of the HRD Project is to solidify the foundation of technologies for nuclear development and utilization in Asia by promoting human resources development in Asian countries. In the Project are two kinds of activity; In-workshop activity and Outside-of-workshop activity. The 3rd Workshop on Human Resources Development in the Nuclear Field was held on October 29 to November 1, at the Nuclear Training Center of KAERI. Participating countries were China, Indonesia, Republic of Korea, Japan, Malaysia, the Philippines, Thailand, and Vietnam. The secretariat for the Human Resources Development Project is provided by the Nuclear Training Center of the Korea Atomic Energy Research Institute and the Nuclear Technology and Education Center of the Japan Atomic Energy Research Institute. This report consists of presentation papers and materials at the Workshop as In-Workshop Activity, a document of project review on Human Resources Development for the fourth Coordinators Meeting of FNCA at Tokyo on March, 2002, a letter of proposal from the Project Leader of Japan to the project leaders of the participating countries, and training materials of participating countries as Outside-Workshop Activity. (author)

  11. 3rd International Conference on Energy Equipment Science and Engineering (ICEESE 2017)

    Science.gov (United States)

    2018-03-01

    PREFACE On behalf of the organizing committee of the 2017 3rd International Conference on Energy Equipment Science and Engineering (ICEESE 2017), I would like to express a warm “Thank You” to all the participants, for their important contribution they brought to the Conference! I strongly appreciate the contribution of the authors, who submitted valuable papers and agreed to do successive revisions of their papers, following the recommendations received from the reviewers. ICEESE 2017 was held in Beijing, China during December28-31, 2017, which was organized by Wuhan University and Guizhou Minzu University. The conference provides a useful and wide platform both for display the latest research and for exchange of research results and thoughts in Energy Equipment Science and Engineering. The participants of the conference were from almost every part of the world, with background of either academia or industry, even well-known enterprise. The success and prosperity of the conference is reflected high level of the papers received. List of Committees available in this pdf.

  12. 3rd International Conference on Opto-Electronics and Applied Optics

    CERN Document Server

    Chakrabarti, Satyajit; Reehal, Haricharan; Lakshminarayanan, Vasudevan

    2017-01-01

    The Proceedings of 3rd International Conference on Opto-Electronics and Applied Optics, OPTRONIX 2016 is an effort to promote and present the research works by scientists and researchers including students in India and abroad in the area of Green Photonics and other related areas as well as to raise awareness about the recent trends of research and development in the area of the related fields. The book has been organized in such a way that it will be easier for the readers to go through and find out the topic of their interests. The first part includes the Keynote addresses by Rajesh Gupta, Department of Energy Science and Engineering, Indian Institute of Technology, Bombay; P.T. Ajith Kumar, President and Leading Scientist Light Logics Holography and Optics, Crescent Hill, Trivandrum, Kerala; and K.K. Ghosh, Institute of Engineering & Management, Kolkata, India.  The second part focuses on the Plenary and Invited Talks given by eminent scientists namely, Vasudevan Lakshminarayanan, University of Wate...

  13. The 3^rd International Conference on Women in Physics: Global Perspectives, Common Concerns, Worldwide Views

    Science.gov (United States)

    Zastavker, Yevgeniya V.

    2009-03-01

    The 3^rd International Conference on Women in Physics (ICWIP), held in Seoul, Korea, in October 2008, brought together 300 participants from 57 countries, including a diverse 22-member U.S. Delegation, for a 3-day summit of stimulating discussions, thought-provoking presentations, inspirational posters, and networking. Held under the auspices of the Working Group on Women in Physics of the International Union of Pure and Applied Physics (IUPAP), this meeting built on the successes of the 1^st (Paris, 2002) and 2^nd (Rio de Janeiro, 2005) Conferences and further clarified the importance of diversifying the field of physics worldwide. Although considerable progress has been made since 2002, it was clear that the global scientific workforce is still under-utilizing a large percentage of the available female talent pool. If human society is to benefit to its fullest from various contributions that the field of physics can offer in addressing global issues of economic crisis, energy, environment, water, health, poverty, and hunger, women of all races and nationalities need to become fully included and engaged in the national and international physical community. To address these and many other issues, the ICWIP unanimously approved a five-part resolution to IUPAP recommending actions to promote the recruitment, retention, and advancement of women in physics and related fields.

  14. [Methodology for an appreciative, dynamic and collaborative process: 3rd Canary Islands (Spain) Health Plan].

    Science.gov (United States)

    O'Shanahan Juan, José Joaquín; Hernández Rodríguez, Miguel Ángel; Del Otero Sanz, Laura; Henríquez Suárez, José Andrés; Mahtani Chugani, Vinita

    The need for new approaches to strategic planning by incorporating the perspectives of professionals and inhabitants has led to a new model for the 3rd Canary Islands (Spain) Health Plan (IIIPSC). A dual-phase participatory process using qualitative techniques is proposed: 1) local phase: a quantitative and qualitative study based on training and a research-action-participation initiative; and 2) insular phase: health conferences with face-to-face discussion of results in each health area (island) and proposals for action. The process prioritises problems and establishes a specific action plan for each island through initiatives that are considered to be viable, grouped by themes and weighted according to the potential impact on priority problems. This process of interaction may help to guide planning model changes and health policy decision-making, and was included in the IIIPSC Project for its parliamentary procedure. Copyright © 2016 SESPAS. Publicado por Elsevier España, S.L.U. All rights reserved.

  15. GRACE manual

    International Nuclear Information System (INIS)

    Ishikawa, T.; Kawabata, S.; Shimizu, Y.; Kaneko, T.; Kato, K.; Tanaka, H.

    1993-02-01

    This manual is composed of three kinds of objects, theoretical background for calculating the cross section of elementary process, usage and technical details of the GRACE system. Throughout this manual we take the tree level process e + e - → W + W - γ as an example, including the e ± -scalar boson interactions. The real FORTRAN source code for this process is attached in the relevant sections as well as the results of calculation, which might be a great help for understanding the practical use of the system. (J.P.N.)

  16. User's manual for EXALPHA (a code for calculating electronic properties of molecules). [Muscatel code, multiply scattered electron approximation

    Energy Technology Data Exchange (ETDEWEB)

    Jones, H.D.

    1976-06-01

    The EXALPHA procedures provide a simplified method for running the MUSCATEL computer code, which in turn is used for calculating electronic properties of simple molecules and atomic clusters, based on the multiply scattered electron approximation for the wave equations. The use of the EXALPHA procedures to set up a run of MUSCATEL is described.

  17. User's manual of MANYCASK code for calculation of spatial distributions of radiation dose rates in a system composed of many spent-fuel-shipping casks

    International Nuclear Information System (INIS)

    Yamakoshi, Hisao

    1986-01-01

    A calculation code MANYCASK is designed for evaluation of spatial distributions of radiation dose rates in ships loaded with a lot of spent fuel shipping casks. Principle of the calculation method adopted in this code is different from that of ordinary codes, and is advantageous for calculating highly reliable dose rate distributions with a very short calculation time. Basic concept of the principle has been described in other reports in detail. A brief description of the principle will be included in the present report along with a technique named Shadow Technique in this report, in addition to format descriptions of output data as well as input data. Results of sample calculations are compared with measured results in figures so as to show how the calculation method adopted is valid. For the purpose of making this code popular among many people, the author writes the user's manual in the present report in Japanese for domestic users, and in English in another report for people in abroad. (author)

  18. Development of WWER-440 fuel. Use of fuel assemblies of 2-nd and 3-rd generations with increased enrichment

    International Nuclear Information System (INIS)

    Vasilchenko, I.; Lushin, V.; Ananev, U.; Baranov, A.; Kukushkin, U.

    2009-01-01

    The problem of increasing the power of units at NPPs with WWER-440 is of current importance. There are all the necessary prerequisites for the above-stated problem as a result of updating the design of fuel assemblies and codes. The decrease of power peaking factor in the core is achieved by using profiled fuel assemblies, fuel-integrated burning absorber, FAs with modernized docking unit, modern codes, which allows decreasing conservatism of RP safety substantiation. A wide range of experimental studies of fuel behaviour has been performed which has reached burn-up of (50-60) MW·day/kgU in transition and emergency conditions, post-reactor studies of fuel assemblies, fuel rods and fuel pellets with a 5-year operating period have been performed, which prove high reliability of fuel, presence of a large margin in the fuel pillar, which helps reactor operation at increased power. The results of the work performed on introduction of 5-6 fuel cycles show that the ultimate fuel state on operability in WWER-440 reactors is far from being achieved. Neutron-physical and thermal-hydraulic characteristics of the cores of working power units with RP V-213 are such that actual (design and measured) power peaking factors on fuel assemblies and fuel rods, as a rule, are smaller than the maximum design values. This factor is a real reserve for power forcing. There is experience of operating Units 1, 2, 4 of the Kola NPP and Unit 2 of the Rovno NPP at increased power. Units of the Loviisa NPP are operated at 109 % power. During transfer to work at increased power it is reasonable to use fuel assemblies with increased height of the fuel pillar, which allows decreasing medium linear power distribution. Further development of the 2-nd generation fuel assembly design and consequent transition to working fuel assemblies of the 3-rd generation provides significant improvement of fuel consumption under the conditions of WWER-440 reactors operation with more continuous fuel cycles and

  19. Fission product data for thermal reactors. Final report. Part 2. Users manual for EPRI-CINDER code and data

    International Nuclear Information System (INIS)

    England, T.R.; Wilson, W.B.; Stamatelatos, M.G.

    1976-12-01

    A four-group fission-product absorption chain library using ENDF/B-IV decay data and cross sections processed with a typical light water reactor spectrum for a modified version of the original CINDER code has been developed as described in Part 1. CINDER is a general point-depletion and fission product code based on an analytical solution of the equations describing nuclides coupled in any linear sequence of radioactive decays and neutron absorptions. The basic code has been in wide use for a number of years. Previously, the user was required to specify all physical data. This report describes the chain library in detail and a modified version of the basic CINDER code (EPRI-CINDER) that is still compatible with existing libraries

  20. PREFACE: 3rd International Youth Conference "Interdisciplinary Problems of Nanotechnology, Biomedicine and Nanotoxicology" (Nanobiotech 2015)

    Science.gov (United States)

    Refsnes, Magne, Prof; Gusev, Alexander, Dr; Godymchuk, Anna, Dr; Bogdan, Anna

    2015-11-01

    The 3rd International Youth Conference "Interdisciplinary Problems of Nanotechnology, Biomedicine and Nanotoxicology" (Nanobiotech2015) was held on 21-22 May 2015 in Tambov, Russia, and was jointly organized by Tambov Derzhavin State University (Russia), the Norwegian Institute of Public Health (Norway), the National University of Science and Technology MISiS (Russia), Tomsk Polytechnic University (Russia) and Tomsk State University. The conference gathered experienced and young researchers, post-docs and students, working in the fieldof nanotechnologies, nanomedicine, nano(eco)toxicology and risk assessment of nanomaterials, in order to facilitate the aggregation and sharing of interests and results for better collaboration and visibility of activity. The goal of Nanobiotech2015 was to bring researchers and practitioners together to share the latest knowledge on nanotechnology-specific risks to occupational and environmental health and assessing how to reduce these potential risks. The main objective of the conference is to identify, systematize and solve current scientific problems inthe sphere of nanobiotechnologies, nanomedicine and nanotoxicology, in order to join forces todetermine prospective areas and compose working groups of interested co-workers for carrying out interdisciplinary research projects. The topics of Nanobiotech2015 were: (1) Nanotechnologies in pharmaceutics and medicine; (2) Sources and mechanisms of nanoparticle release into the environment; (3) Ecological and biological effects of nanoparticles; (4) (Eco)toxicology of nanomaterials; (5) Methods for detection of nanoparticles in the environment and in biological objects; and (6) Physico-chemical properties of nanoparticles in the environment. We want to thank the Organizing Committee, the universities and sponsors supporting the conference,and everyone who contributed to the organization of this meeting, for their contribution towards the conference and for their contributions to these

  1. The 3rd questionnaire report of safety control on instrument in nuclear medicine laboratory

    International Nuclear Information System (INIS)

    1994-01-01

    The present 3rd survey was aimed at grasping safety control in nuclear medicine examination and the trend for SPECT usage. Questionnaires were sent to 1238 facilities dealing with nuclear medicine; and 1127 facilities (91.0%) responded. The survey period was three years from April 1, 1989 through March 31, 1992. The following 7 items were surveyed: (1) nuclear medicine personnel, (2) nuclear medicine equipments, (3) accidents occurring in nuclear medicine laboratories, (4) risk factors leading to accidents, (5) countermeasures for improving safety control, (6) major breakdown of the machinery and equipment, and (7) demands for makers. Majority of nuclear medicine personnel were male and were less than 50 years old. The number of SPECT equipments increased from 714 in the previous survey to 968. Accidents (personal injuries) and narrow escape from an accident were seen in 45 and 154 cases. Personal injuries such as falling occurred in 37 patients and 8 nuclear medicine personnel. According to nuclear medicine examinations, SPECT was the most common examination associated with accident and narrow escape cases (86/199). Such cases at the beginning of examination were remarkably decreased, as compared with those in the previous two surveys. Accidents were primarily attributable to careless management by personnel. Breakdown of the machinery and equipment was reported in 207 cases. In Item 5, the following contents were presented: heads for examination, personnel's behavior, education, examination equipments, collimators and others. Finally, contents in Item 7 included: equipment design, heads for examination, maintenance or management, data processing, collimators, examination equipments and others. (N.K.)

  2. Overview of the 3rd phase crossover research on migration of radionuclides in biosphere

    International Nuclear Information System (INIS)

    Uchida, Shigeo; Amano, Hikaru; Chiba, Masaru; Hisamatsu, Shun'ichi; Enomoto, Shuichi; Matsumoto, Shiro

    2003-01-01

    In 1991, we started a series of projects in Nuclear Energy Generic Crossover Research, which is known as ''Crossover Research (CR)''. This 1st phase was successfully finished with the active cooperation of five organizations: Japan Atomic Energy Research Institute (JAERI), Meteorological Research Institute (MRI), National Institute of Radiological Sciences (NIRS), the Institute of Physical and Chemical Research (RIKEN) and Power Reactor and Nuclear Fuel Development Corporation (PNC). Subsequently we carried out the 2nd phase of CR (1996-1998). A new member, Institute for Environmental Sciences (IES) participated from this phase. In the 3rd phase CR, a project on ''Development of a dynamic transfer model of radionuclides in the soil ecosphere'', is currently being promoted (1999-2003). The following five researches are carried out in this project. (1) Research into the forms of existence of nuclide and their change in the soil (NIRS and JAERI), (2) Research into the transition behavior of radionuclides in plants (IES, RIKEN and NIRS), (3) Research into the relation to the microorganism and on environmental remediation (RIKEN, JAERI and NIRS), (4) Research on the migration of radionuclides from atmosphere to soil and plant (MRI and JAERI), and (5) Database construction on transfer parameters (JAERI, NIRS and MRI). Then, JAERI, MRI and NIRS are working on the development of a dynamic transfer model for radionuclides on the basis of a gained knowledge about the environmental behavior with the cooperation of universities, etc. The dynamic transfer model developed in this project is effective not only for Japan, but also for the Southeast Asian countries. Besides, this model is capable of predicting the behavior of materials that are harmful to the environment, i.e. hazardous heavy metals discharged in the soil ecosphere. (author)

  3. Proceedings of the 3rd workshop on ion-beam-applied biology

    International Nuclear Information System (INIS)

    Matsuhashi, Shinpei; Suzui, Nobuo; Ishioka, Noriko S.

    2005-09-01

    In order to encourage research on biological application using ion beam at TIARA, we have had the workshop on ion beam applied biology at JAERI Takasaki every year since 2002. The 3rd workshop titled 'Future development of plant research using the positron imaging method - Understanding the plant functions through visualization images-' is held this year. The main topics of this workshop are introduction of the latest studies on the assimilation and transportation of nutrients by plant using positron imaging method. Further, related technologies of the positron imaging and prospect of positron imaging for is discussed. We hope this workshop popularizes positron imaging technology for plants, accelerates cooperation between industries, universities and governmental institutes and contributes future projects of understanding of the physiological functions of plants using the positron imaging method. This workshop was held on September 29th 2004, hosted by JAERI Takasaki and cooperated by The Japan Radioisotope Association, Japanese Society of Soil Science and Plant Nutrition. The Japanese Society of Plant Physiologists, Atomic Energy Society of Japan, The Japanese Society of Nuclear and Radiochemical Science and The Ion Beam Breeding Society. There were 85 participants from not only universities and laboratories but also private company developing the environment conservation technology, so on. Highly qualified presentations were given on biological studies with ion beam, on analysis of plant functions using the positron imaging method and on supporting technology for the positron imaging monitoring. Progress in the elucidation of plant functions is expected to develop the technologies for production of safe provisions and conservation of environment with plant. The 14 of the presented papers are indexed individually. (J.P.N.)

  4. User`s manual for the FEHM application -- A finite-element heat- and mass-transfer code

    Energy Technology Data Exchange (ETDEWEB)

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

    1997-07-01

    The use of this code is applicable to natural-state studies of geothermal systems and groundwater flow. A primary use of the FEHM application will be to assist in the understanding of flow fields and mass transport in the saturated and unsaturated zones below the proposed Yucca Mountain nuclear waste repository in Nevada. The equations of heat and mass transfer for multiphase flow in porous and permeable media are solved in the FEHM application by using the finite-element method. The permeability and porosity of the medium are allowed to depend on pressure and temperature. The code also has provisions for movable air and water phases and noncoupled tracers; that is, tracer solutions that do not affect the heat- and mass-transfer solutions. The tracers can be passive or reactive. The code can simulate two-dimensional, two-dimensional radial, or three-dimensional geometries. In fact, FEHM is capable of describing flow that is dominated in many areas by fracture and fault flow, including the inherently three-dimensional flow that results from permeation to and from faults and fractures. The code can handle coupled heat and mass-transfer effects, such as boiling, dryout, and condensation that can occur in the near-field region surrounding the potential repository and the natural convection that occurs through Yucca Mountain due to seasonal temperature changes. This report outlines the uses and capabilities of the FEHM application, initialization of code variables, restart procedures, and error processing. The report describes all the data files, the input data, including individual input records or parameters, and the various output files. The system interface is described, including the software environment and installation instructions.

  5. Visual Arts Teaching in Kindergarten through 3rd-Grade Classrooms in the UAE: Teacher Profiles, Perceptions, and Practices

    Science.gov (United States)

    Buldu, Mehmet; Shaban, Mohamed S.

    2010-01-01

    This study portrayed a picture of kindergarten through 3rd-grade teachers who teach visual arts, their perceptions of the value of visual arts, their visual arts teaching practices, visual arts experiences provided to young learners in school, and major factors and/or influences that affect their teaching of visual arts. The sample for this study…

  6. Constancy and Variability: Dialogic Literacy Events as Sites for Improvisation in Two 3rd-Grade Classrooms

    Science.gov (United States)

    Jordan, Michelle E.; Santori, Diane

    2015-01-01

    This multisite study investigates dialogic literacy events that revolved around narrative and informational texts in two 3rd-grade classrooms. The authors offer a metaphor of musical improvisation to contemplate dialogic literacy events as part of the repertoire of teaching and learning experiences. In literacy learning, where there is much…

  7. Influence of the 1st, 2nd and 3rd harmonic magnetic field in mini-cyclotron

    International Nuclear Information System (INIS)

    Lu xiangshun; Chen Maobai; Li Deming; Xu Senlin

    1996-01-01

    The influence of the 1st, 2nd and 3rd harmonic magnetic field on particle's movement in the mini-cyclotron has been studied. The permitted upper limits for each harmonic part are calculated. These data provide a theoretical reference for magnetic trimming

  8. Analyzing Entrepreneurship Skill Levels of the 3rd Grade Primary School Students in Life Sciences Course Based on Different Variables

    Science.gov (United States)

    Polat, Hüseyin

    2018-01-01

    The purpose of this study is to investigate Life Sciences course entrepreneurship skills of the 3rd grade primary school students as evaluated by their parents. The study was conducted with the screening model. The participants of the study were the parents (47 mothers and 23 fathers) of the students (32 girls, 38 boys) who study in the center of…

  9. Business process management : 3rd international conference, BPM 2005, Nancy, France, September 5-8, 2005 : proceedings

    NARCIS (Netherlands)

    Aalst, van der W.M.P.; Benatallah, B.; Casati, F.; Curbera, F.

    2005-01-01

    This volume contains the proceedings of the 3rd International Conference on Business Process Management (BPM 2005), organized by LORIA in Nancy, France, September 5–8, 2005. This year, BPM included several innovations with respect to previous editions, most notably the addition of an industrial

  10. Conference proceedings of the 2nd and 3rd Regional Innovation & Entrepreneurship Conference : at Saxion University of applied sciences

    NARCIS (Netherlands)

    Bazen, J.J. (Jacques); Hammer, M.H.M. (Matthijs)

    2016-01-01

    DOI:https://doi.org/10.14261/postit/F20ECDBA-3106-4133-9EE0714DBAA65B51 In 2015 and 2016, Saxion University of Applied Sciences organized the 2nd and 3rd edition of the Regional Innovation and Entrepreneurship Conference (RIEC). The book that is in front of you now is the result of these two

  11. SESAME — A 3rd Generation Synchrotron Light Source for the Middle East

    Science.gov (United States)

    Å°lkü, Dinçer; Rahighi, Javad; Winick, Herman

    2007-01-01

    SESAME (Synchrotron-light for Experimental Science and Applications in the Middle East) will be the Middle East's first international research center. It is a cooperative venture by the scientists and governments of the region with founding members Bahrain, Egypt, Israel, Jordan, Pakistan, Palestine Authority, and Turkey. Iran is in the process of finalizing its formal membership. Other countries (Cyprus, Morocco, and the United Arab Emirates) are also expected to join. The permanent Council of member states has full responsibility for the project. Members provide the annual operating budget. Observer countries are Germany, Greece, Italy, Kuwait, Portugal, Russian Federation, Sweden, the UK, and the US. SESAME is being developed under the umbrella of UNESCO. Jordan was selected as the building site. SESAME will offer excellent opportunities for training of Middle East scientists and attract those working abroad to consider returning. SESAME will be a 2.5GeV 3rd Generation light source (emittance 26nm-rad, circumference ˜133m), providing excellent performance for structural molecular biology, molecular environmental science, surface and interface science, microelectromechanical devices, x-ray imaging, archaeological microanalysis, and materials characterization. It will cover a broad spectral range from the infrared to hard x-rays and will have 12 straight sections for insertion devices (average length 2.75m). The injector will be the BESSY I 0.8 GeV booster synchrotron which has been given as a gift from Germany. Four committees advise the Council and assist in developing the technical design, beam lines, user community, and scientific Program. The SESAME building, now in construction with funds and a site provided by Jordan, is scheduled for completion in late 2006 after which the BESSY I injector will be installed. First stored beam in the new 2.5 GeV ring is planned for 2009 with six initial beamlines planned. Some beamlines will be built by member countries

  12. SESAME - A 3rd Generation Synchrotron Light Source for the Middle East

    Science.gov (United States)

    U˝Lkü, Dinçer; Rahighi, Javad; Winick, Herman

    2007-01-01

    SESAME (Synchrotron-light for Experimental Science and Applications in the Middle East) will be the Middle East's first international research center. It is a cooperative venture by the scientists and governments of the region with founding members Bahrain, Egypt, Israel, Jordan, Pakistan, Palestine Authority, and Turkey. Iran is in the process of finalizing its formal membership. Other countries (Cyprus, Morocco, and the United Arab Emirates) are also expected to join. The permanent Council of member states has full responsibility for the project. Members provide the annual operating budget. Observer countries are Germany, Greece, Italy, Kuwait, Portugal, Russian Federation, Sweden, the UK, and the US. SESAME is being developed under the umbrella of UNESCO. Jordan was selected as the building site. SESAME will offer excellent opportunities for training of Middle East scientists and attract those working abroad to consider returning. SESAME will be a 2.5GeV 3rd Generation light source (emittance 26nm-rad, circumference ~133m), providing excellent performance for structural molecular biology, molecular environmental science, surface and interface science, microelectromechanical devices, x-ray imaging, archaeological microanalysis, and materials characterization. It will cover a broad spectral range from the infrared to hard x-rays and will have 12 straight sections for insertion devices (average length 2.75m). The injector will be the BESSY I 0.8 GeV booster synchrotron which has been given as a gift from Germany. Four committees advise the Council and assist in developing the technical design, beam lines, user community, and scientific Program. The SESAME building, now in construction with funds and a site provided by Jordan, is scheduled for completion in late 2006 after which the BESSY I injector will be installed. First stored beam in the new 2.5 GeV ring is planned for 2009 with six initial beamlines planned. Some beamlines will be built by member countries

  13. The 3rd International Conference on Mathematics, Science and Education 2016

    International Nuclear Information System (INIS)

    2017-01-01

    The 3 rd International Conference of Mathematics, Science, and Education (ICMSE) 2016 on Semarang, 3-4 September 2016 organized by Faculty of Mathematics and Natural Science, Semarang State University. ICMSE2016 provides a platform to the researchers, experts and practitioners from academia, governments, NGOs, research institutes, and industries to meet and share cutting-edge progress in the fields of mathematics and natural science. It is reflected in this year theme “Contribution of Mathematics and Science Research for Sustainable Life in Facing Global Challenge”. The scope of this conference are Mathematics, Biology, Chemistry, and Physics,We thank to the keynote speakers and all authors of the contributed papers, for the cooperation rendered to us in the publication of the conference proceedings. In particular, we would like to place on record our thanks to the expert reviewers who have spared their time reviewing the papers. We also highly appreciate the assistance offered by many volunteers in the preparation of the conference proceedings, and of course to the sponsors assisting in funding this conference, especially Research, Technology and Higher Education Ministry of Indonesia for supporting this conference.The committee selected 71 papers from 129 papers presented in this forum to be published in Journal of Physics: Conference Series (Institute of Physics Publisher) indexed by Scopus. We hope that this program will further stimulate research in Mathematics, Science, and Education; share research interest and information; and create a forum of collaboration and build trust relationship. We feel honored and privileged to serve the best recent developments in the field of Mathematics and Science Education to you through this exciting program.Chairperson,Dr. Margareta RahayuningsihCOMMITTEEInternational Scientific Advisory BoardEdy Cahyono ( Chemistry Department, State University of Semarang )Rahim Sahar ( Department of Physics, Universiti Teknologi

  14. SESAME - A 3rd Generation Synchrotron Light Source for the Middle East

    International Nuclear Information System (INIS)

    Ulkue, Dincer; Rahighi, Javad; Winick, Herman

    2007-01-01

    SESAME (Synchrotron-light for Experimental Science and Applications in the Middle East) will be the Middle East's first international research center. It is a cooperative venture by the scientists and governments of the region with founding members Bahrain, Egypt, Israel, Jordan, Pakistan, Palestine Authority, and Turkey. Iran is in the process of finalizing its formal membership. Other countries (Cyprus, Morocco, and the United Arab Emirates) are also expected to join. The permanent Council of member states has full responsibility for the project. Members provide the annual operating budget. Observer countries are Germany, Greece, Italy, Kuwait, Portugal, Russian Federation, Sweden, the UK, and the US. SESAME is being developed under the umbrella of UNESCO. Jordan was selected as the building site. SESAME will offer excellent opportunities for training of Middle East scientists and attract those working abroad to consider returning. SESAME will be a 2.5GeV 3rd Generation light source (emittance 26nm-rad, circumference ∼133m), providing excellent performance for structural molecular biology, molecular environmental science, surface and interface science, microelectromechanical devices, x-ray imaging, archaeological microanalysis, and materials characterization. It will cover a broad spectral range from the infrared to hard x-rays and will have 12 straight sections for insertion devices (average length 2.75m). The injector will be the BESSY I 0.8 GeV booster synchrotron which has been given as a gift from Germany. Four committees advise the Council and assist in developing the technical design, beam lines, user community, and scientific Program. The SESAME building, now in construction with funds and a site provided by Jordan, is scheduled for completion in late 2006 after which the BESSY I injector will be installed. First stored beam in the new 2.5 GeV ring is planned for 2009 with six initial beamlines planned. Some beamlines will be built by member countries

  15. ic-cmtp3: 3rd International Conference on Competitive Materials and Technology Processes

    Science.gov (United States)

    2016-04-01

    Competitiveness is one of the most important factors in our lives and it plays a key role in the efficiency both of organizations and societies. The more scientifically advanced and prepared organizations develop more competitive materials with better physical, chemical, and biological properties, and the leading companies apply more competitive equipment and technological processes. The aims of the 3rd International Conference on Competitive Materials and Technology Processes (ic-cmtp3), and the 1st International Symposium on Innovative Carbons and Carbon Based Materials (is-icbm1) and the 1st International Symposium on Innovative Construction Materials (is-icm1) organized alongside are the following: —Promote new methods and results of scientific research in the fields of material, biological, environmental and technological sciences; —Exchange information between the theoretical and applied sciences as well as technical and technological implementations; —Promote communication and collaboration between the scientists, researchers and engineers of different nations, countries and continents. Among the major fields of interest are advanced and innovative materials with competitive characteristics, including mechanical, physical, chemical, biological, medical and thermal, properties and extreme dynamic strength. Their crystalline, nano - and micro-structures, phase transformations as well as details of their technological processes, tests and measurements are also in the focus of the ic-cmtp3 conference and the is-scbm1 and is-icm1 symposia. Multidisciplinary applications of material science and the technological problems encountered in sectors like ceramics, glasses, thin films, aerospace, automotive and marine industries, electronics, energy, construction materials, medicine, biosciences and environmental sciences are of particular interest. In accordance with the program of the ic-cmtp3 conference and is-icbm1 and is-icm1 symposia we have received more

  16. PREFACE: 3rd International Workshop on Statistical Physics and Mathematics for Complex Systems (SPMCS 2012)

    Science.gov (United States)

    Tayurskii, Dmitrii; Abe, Sumiyoshi; Alexandre Wang, Q.

    2012-11-01

    The 3rd International Workshop on Statistical Physics and Mathematics for Complex Systems (SPMCS2012) was held between 25-30 August at Kazan (Volga Region) Federal University, Kazan, Russian Federation. This workshop was jointly organized by Kazan Federal University and Institut Supérieur des Matériaux et Mécaniques Avancées (ISMANS), France. The series of SPMCS workshops was created in 2008 with the aim to be an interdisciplinary incubator for the worldwide exchange of innovative ideas and information about the latest results. The first workshop was held at ISMANS, Le Mans (France) in 2008, and the third at Huazhong Normal University, Wuhan (China) in 2010. At SPMCS2012, we wished to bring together a broad community of researchers from the different branches of the rapidly developing complexity science to discuss the fundamental theoretical challenges (geometry/topology, number theory, statistical physics, dynamical systems, etc) as well as experimental and applied aspects of many practical problems (condensed matter, disordered systems, financial markets, chemistry, biology, geoscience, etc). The program of SPMCS2012 was prepared based on three categories: (i) physical and mathematical studies (quantum mechanics, generalized nonequilibrium thermodynamics, nonlinear dynamics, condensed matter physics, nanoscience); (ii) natural complex systems (physical, geophysical, chemical and biological); (iii) social, economical, political agent systems and man-made complex systems. The conference attracted 64 participants from 10 countries. There were 10 invited lectures, 12 invited talks and 28 regular oral talks in the morning and afternoon sessions. The book of Abstracts is available from the conference website (http://www.ksu.ru/conf/spmcs2012/?id=3). A round table was also held, the topic of which was 'Recent and Anticipated Future Progress in Science of Complexity', discussing a variety of questions and opinions important for the understanding of the concept of

  17. Building monument materials during the 3rd-4rd millennium (Portugal)

    Science.gov (United States)

    Moita, Patricia; Pedro, Jorge; Boaventura, Rui; Mataloto, Rui; Maximo, Jaime; Almeida, Luís; Nogueira, Pedro

    2014-05-01

    Dolmens are the most conspicuous remains of the populations of the 4th and first half of 3rd millennia BCE. These tombs are impressive not only for their monumentality, but also because of the socioeconomic investment they represent for those Neolithic communities, namely from the Central-South of Portugal, who built them. Although dolmens have been studied for their funerary content and typologies, an interdisciplinary approach toward the geological characterization and sourcing of stones used in these constructions has not received enough attention from researchers. With MEGAGEO project a multidisciplinary group of geologist and archaeologists intends to assess the relationship between the distribution of dolmens in Central-South Portugal, their source materials, and the geological landscape. GIS will map the information gathered and will be used to analyse these relationships. The selection of the areas, with distinctive geologies (limestone vs granite), will allow to verify if human patterns of behaviour regarding the selection of megaliths are similar or different regionally. Geologically the first target area (Freixo, Alentejo) is dominated by a small intrusion of gabbro mingled/mixed within a granodioritic intrusion both related with variscan orogeny. Granodiorite exhibit several enclaves of igneous and metamorphic nature attesting the interaction between both igneous rocks as well with enclosing gneisses. Despite Alentejo region have a reduced number of outcrops the granodiorite provides rounded to tabular metric blocks. The gabbro is very coarse grained, sometimes with a cumulate texture, and their fracturing and weathering provide very fresh tabular blocks. The five studied dolmens (Quinta do Freixo #1 to #5) are implanted in a large granodioritic intrusion, around the gabbroic rocks, within an area of approximately 9km2. The medium grained granodiorite is ubiquity in all the dolmens slabs and occasionally it can be observed features of mixing and

  18. User's manual for DYNA2D: an explicit two-dimensional hydrodynamic finite-element code with interactive rezoning

    Energy Technology Data Exchange (ETDEWEB)

    Hallquist, J.O.

    1982-02-01

    This revised report provides an updated user's manual for DYNA2D, an explicit two-dimensional axisymmetric and plane strain finite element code for analyzing the large deformation dynamic and hydrodynamic response of inelastic solids. A contact-impact algorithm permits gaps and sliding along material interfaces. By a specialization of this algorithm, such interfaces can be rigidly tied to admit variable zoning without the need of transition regions. Spatial discretization is achieved by the use of 4-node solid elements, and the equations-of motion are integrated by the central difference method. An interactive rezoner eliminates the need to terminate the calculation when the mesh becomes too distorted. Rather, the mesh can be rezoned and the calculation continued. The command structure for the rezoner is described and illustrated by an example.

  19. 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

  20. A probabilistic assessment code system for derivation of clearance levels of radioactive materials. PASCLR user's manual

    Energy Technology Data Exchange (ETDEWEB)

    Takahashi, Tomoyuki [Kyoto Univ., Kumatori, Osaka (Japan). Research Reactor Inst; Takeda, Seiji; Kimura, Hideo [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2001-01-01

    It is indicated that some types of radioactive material generating from the development and utilization of nuclear energy do not need to be subject regulatory control because they can only give rise to trivial radiation hazards. The process to remove such materials from regulatory control is called as 'clearance'. The corresponding levels of the concentration of radionuclides are called as 'clearance levels'. In the Nuclear Safety Commission's discussion, the deterministic approach was applied to derive the clearance levels, which are the concentrations of radionuclides in a cleared material equivalent to an individual dose criterion. Basically, realistic parameter values were selected for it. If the realistic values could not be defined, reasonably conservative values were selected. Additionally, the stochastic approaches were performed to validate the results which were obtained by the deterministic calculations. We have developed a computer code system PASCLR (Probabilistic Assessment code System for derivation of Clearance Levels of Radioactive materials) by using the Monte Carlo technique for carrying out the stochastic calculations. This report describes the structure and user information for execution of PASCLR code. (author)

  1. CELEBRATION OF DECEMBER 3RD, INTERNATIONAL DAY OF PERSONS WITH DISABILITIES

    Directory of Open Access Journals (Sweden)

    Maja FILIPOVSKA

    2017-03-01

    Full Text Available On December 2nd 2016 in the main amphitheater at the Faculty of Philosophy in Skopje, was held the celebration of December 3rd, the International Day of Persons with Disabilities, in organization of the Institute of Special Education and Rehabilitation. The official part of the program was started with a speech by Goran Ajdinski, PhD, the Dean of the Faculty of Philosophy in Skopje. The guests at the celebration were also greeted by the Rector of the University “Ss. Cyril and Methodius” – Skopje, Nikola Jankulovski, PhD and the Minister of Labor and Social Policy of Republic of Macedonia, Frosina Tashevska-Remenski, PhD. After the speeches, which highlighted the current efforts and future commitment to inclusion and accessibility of persons with disabilities, two awards were presented by the Humanitarian foundation “Prof. d-r Ljupco Ajdinski”. The first award was given to Simona Kostadinova as the student with achieved highest grade point average of 9.65 in the generation 2011/12 during the studies of Special education and rehabilitation. The second award was intended for the highest ranked student at the university admission in 2016/2017. This award belonged to Nadica Gjerasimova who had 97.70 points on the official rank list. Beside the awards, two acknowledgements for humanity were also given by the Foundation “Prof. d-r Ljupco Ajdinski”. For the longstanding human activity in preparation of special education and rehabilitation staff and education and rehabilitation of persons with disabilities, the first acknowledgement was given to the Institute of Special education and rehabilitation. The second acknowledgement was meant for Kiril Temkov, PhD, about his numerous initiated and organized human activities, especially for the published paper on the ethical dimensions of special education and rehabilitation and introduction of Ethics in the education system in Republic of Macedonia. The last part of the program was intended for

  2. PREFACE: 3rd International Workshop on Materials Analysis and Processing in Magnetic Fields (MAP3)

    Science.gov (United States)

    Sakka, Yoshio; Hirota, Noriyuki; Horii, Shigeru; Ando, Tsutomu

    2009-07-01

    The 3rd International Workshop on Materials Analysis and Processing in Materials Fields (MAP3) was held on 14-16 May 2008 at the University of Tokyo, Japan. The first was held in March 2004 at the National High Magnetic Field Laboratory in Tallahassee, USA. Two years later the second took place in Grenoble, France. MAP3 was held at The University of Tokyo International Symposium, and jointly with MANA Workshop on Materials Processing by External Stimulation, and JSPS CORE Program of Construction of the World Center on Electromagnetic Processing of Materials. At the end of MAP3 it was decided that the next MAP4 will be held in Atlanta, USA in 2010. Processing in magnetic fields is a rapidly expanding research area with a wide range of promising applications in materials science. MAP3 focused on the magnetic field interactions involved in the study and processing of materials in all disciplines ranging from physics to chemistry and biology: Magnetic field effects on chemical, physical, and biological phenomena Magnetic field effects on electrochemical phenomena Magnetic field effects on thermodynamic phenomena Magnetic field effects on hydrodynamic phenomena Magnetic field effects on crystal growth Magnetic processing of materials Diamagnetic levitation Magneto-Archimedes effect Spin chemistry Application of magnetic fields to analytical chemistry Magnetic orientation Control of structure by magnetic fields Magnetic separation and purification Magnetic field-induced phase transitions Materials properties in high magnetic fields Development of NMR and MRI Medical application of magnetic fields Novel magnetic phenomena Physical property measurement by Magnetic fields High magnetic field generation> MAP3 consisted of 84 presentations including 16 invited talks. This volume of Journal of Physics: Conference Series contains the proceeding of MAP3 with 34 papers that provide a scientific record of the topics covered by the conference with the special topics (13 papers) in

  3. PREFACE: 3rd Workshop on Theory, Modelling and Computational Methods for Semiconductors (TMCSIII)

    Science.gov (United States)

    Califano, Marco; Migliorato, Max; Probert, Matt

    2012-05-01

    These conference proceedings contain the written papers of the contributions presented at the 3rd International Conference on Theory, Modelling and Computational Methods for Semiconductor materials and nanostructures. The conference was held at the School of Electronic and Electrical Engineering, University of Leeds, Leeds, UK on 18-20 January 2012. The previous conferences in this series took place in 2010 at St William's College, York and in 2008 at the University of Manchester, UK. The development of high-speed computer architectures is finally allowing the routine use of accurate methods for calculating the structural, thermodynamic, vibrational, optical and electronic properties of semiconductors and their hetero- and nano-structures. The scope of this conference embraces modelling, theory and the use of sophisticated computational tools in semiconductor science and technology, where there is substantial potential for time-saving in R&D. Theoretical approaches represented in this meeting included: Density Functional Theory, Tight Binding, Semiempirical Pseudopotential Methods, Effective Mass Models, Empirical Potential Methods and Multiscale Approaches. Topics included, but were not limited to: Optical and Transport Properties of Quantum Nanostructures including Colloids and Nanotubes, Plasmonics, Magnetic Semiconductors, Graphene, Lasers, Photonic Structures, Photovoltaic and Electronic Devices. This workshop ran for three days, with the objective of bringing together UK and international leading experts in the theoretical modelling of Group IV, III-V and II-VI semiconductors, as well as students, postdocs and early-career researchers. The first day focused on providing an introduction and overview of this vast field, aimed particularly at students, with several lectures given by recognised experts in various theoretical approaches. The following two days showcased some of the best theoretical research carried out in the UK in this field, with several

  4. RELAP-7 Theory Manual

    Energy Technology Data Exchange (ETDEWEB)

    Berry, Ray Alden [Idaho National Lab. (INL), Idaho Falls, ID (United States); Zou, Ling [Idaho National Lab. (INL), Idaho Falls, ID (United States); Zhao, Haihua [Idaho National Lab. (INL), Idaho Falls, ID (United States); Zhang, Hongbin [Idaho National Lab. (INL), Idaho Falls, ID (United States); Peterson, John William [Idaho National Lab. (INL), Idaho Falls, ID (United States); Martineau, Richard Charles [Idaho National Lab. (INL), Idaho Falls, ID (United States); Kadioglu, Samet Yucel [Idaho National Lab. (INL), Idaho Falls, ID (United States); Andrs, David [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2016-03-01

    This document summarizes the physical models and mathematical formulations used in the RELAP-7 code. In summary, the MOOSE based RELAP-7 code development is an ongoing effort. The MOOSE framework enables rapid development of the RELAP-7 code. The developmental efforts and results demonstrate that the RELAP-7 project is on a path to success. This theory manual documents the main features implemented into the RELAP-7 code. Because the code is an ongoing development effort, this RELAP-7 Theory Manual will evolve with periodic updates to keep it current with the state of the development, implementation, and model additions/revisions.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2001-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2001-07-01

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

  7. Coronal MR imaging of the normal 3rd, 4th, and 5th lumbar and 1st sacral nerve roots

    International Nuclear Information System (INIS)

    Hald, J.K.; Nakstad, P.H.; Hauglum, B.E.

    1991-01-01

    Seven healthy volunteers underwent coronal MR imaging at 1.5 tesla of the normal 3rd, 4th, and 5th lumbar, and 1st sacral nerve roots. Coronal slices, 3-mm-thick with a 0.3-mm gap between the slices were obtained (TR/TE 600/22) through the lumbar spinal canal. All the nerve roots were visible on at least one image. One can routinely expect to demonstrate the 3rd, 4th, and 5th lumbar, and 1st sacral nerve roots on T1-weighted, 3-mm-thick coronal MR scans. We found no correlation between the degree of lumbar lordosis and the lengths of the visible nerve roots. Five patients with one of the following spinal problems: anomaly, tumor, disk herniation, and failed back surgery syndrome were examined according to our protocol. In all these cases coronal MR imaging gave the correct diagnosis. (orig.)

  8. Coronal MR imaging of the normal 3rd, 4th, and 5th lumbar and 1st sacral nerve roots

    Energy Technology Data Exchange (ETDEWEB)

    Hald, J K; Nakstad, P H; Hauglum, B E [National Hospital, Oslo (Norway). Dept. of Radiology

    1991-05-01

    Seven healthy volunteers underwent coronal MR imaging at 1.5 tesla of the normal 3rd, 4th, and 5th lumbar, and 1st sacral nerve roots. Coronal slices, 3-mm-thick with a 0.3-mm gap between the slices were obtained (TR/TE 600/22) through the lumbar spinal canal. All the nerve roots were visible on at least one image. One can routinely expect to demonstrate the 3rd, 4th, and 5th lumbar, and 1st sacral nerve roots on T1-weighted, 3-mm-thick coronal MR scans. We found no correlation between the degree of lumbar lordosis and the lengths of the visible nerve roots. Five patients with one of the following spinal problems: anomaly, tumor, disk herniation, and failed back surgery syndrome were examined according to our protocol. In all these cases coronal MR imaging gave the correct diagnosis. (orig.).

  9. Mechanical design and engineering of the 3.9 GHZ, 3rd harmonic SRF system at Fermilab

    International Nuclear Information System (INIS)

    Don Mitchell

    2004-01-01

    The mechanical development of the 3.9 GHz, 3rd Harmonic SRF System is summarized to include: the development of a full scale copper prototype cavity structure; the design of the niobium 3 cell and niobium 9 cell structures; the design of the helium vessel and cryostat; the HOM coupler design; and a preliminary look at the main coupler design. The manufacturing processes for forming, rolling, and e-beam welding the HOM coupler, cavity cells, and end tubes are also described. Due to the exotic materials and manufacturing processes used in this type of device, a cost estimate for the material and fabrication is provided. The 3rd harmonic design is organized via a web-based data management approach

  10. Mechanical design and engineering of the 3.9 GHZ, 3rd harmonic SRF system at Fermilab

    Energy Technology Data Exchange (ETDEWEB)

    Don Mitchell et al.

    2004-08-05

    The mechanical development of the 3.9 GHz, 3rd Harmonic SRF System is summarized to include: the development of a full scale copper prototype cavity structure; the design of the niobium 3 cell and niobium 9 cell structures; the design of the helium vessel and cryostat; the HOM coupler design; and a preliminary look at the main coupler design. The manufacturing processes for forming, rolling, and e-beam welding the HOM coupler, cavity cells, and end tubes are also described. Due to the exotic materials and manufacturing processes used in this type of device, a cost estimate for the material and fabrication is provided. The 3rd harmonic design is organized via a web-based data management approach.

  11. FOREWORD: 3rd International Workshop on New Computational Methods for Inverse Problems (NCMIP 2013)

    Science.gov (United States)

    Blanc-Féraud, Laure; Joubert, Pierre-Yves

    2013-10-01

    Conference logo This volume of Journal of Physics: Conference Series is dedicated to the scientific contributions presented during the 3rd International Workshop on New Computational Methods for Inverse Problems, NCMIP 2013 (http://www.farman.ens-cachan.fr/NCMIP_2013.html). This workshop took place at Ecole Normale Supérieure de Cachan, in Cachan, France, on 22 May 2013, at the initiative of Institut Farman. The prior editions of NCMIP also took place in Cachan, France, firstly within the scope of the ValueTools Conference, in May 2011 (http://www.ncmip.org/2011/), and secondly at the initiative of Institut Farman, in May 2012 (http://www.farman.ens-cachan.fr/NCMIP_2012.html). The NCMIP Workshop focused on recent advances in the resolution of inverse problems. Indeed inverse problems appear in numerous scientific areas such as geophysics, biological and medical imaging, material and structure characterization, electrical, mechanical and civil engineering, and finances. The resolution of inverse problems consists of estimating the parameters of the observed system or structure from data collected by an instrumental sensing or imaging device. Its success firstly requires the collection of relevant observation data. It also requires accurate models describing the physical interactions between the instrumental device and the observed system, as well as the intrinsic properties of the solution itself. Finally, it requires the design of robust, accurate and efficient inversion algorithms. Advanced sensor arrays and imaging devices provide high rate and high volume data; in this context, the efficient resolution of the inverse problem requires the joint development of new models and inversion methods, taking computational and implementation aspects into account. During this one-day workshop, researchers had the opportunity to bring to light and share new techniques and results in the field of inverse problems. The topics of the workshop were: algorithms and computational

  12. Turkey's Struggle with Internet in its 3rd year: Don Quixote, Ostrich, Harakiri

    Directory of Open Access Journals (Sweden)

    Mustafa Akgül

    2010-06-01

    Full Text Available The Code 5651 which sets Internet censhorship in Turkey has been active for 3 years. With this lawr, our country twanted to be a leader among democratic countries, , and challenged giant companies like Youtube and Google and fined them with tax penalty. Our country t is trying to set International Law on Internet via code 5651 and decisions of its courts. But it doesn't do this by defending or negotiating the issue on international forums or United Nations. It considers Internet as media and it punishes and bans similar to printing press.. A serious number of people, including the Prime Minister, break the ban. The President of the Republic, State Minister for EU, Minister of Transportation and chairman of Information and Communication Technologies Authority give statements against these bans. In the meantime, rule of law, separation of powers, fair trial, and basic human rights such as freedom of expression are ignored. In other words, a Legal Tradegy occurs in front of lawyers and intellectuals. And our country commits hara-kiri by not understanding Internet, just like the situation in printing machine. In this article, various dimensions of the 3-year struggle of Turkey with Internet are discussed.

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

    Energy Technology Data Exchange (ETDEWEB)

    Serov, I V; Hoogenboom, J E

    1993-07-01

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

  14. EVLncRNAs: a manually curated database for long non-coding RNAs validated by low-throughput experiments

    Science.gov (United States)

    Zhao, Huiying; Yu, Jiafeng; Guo, Chengang; Dou, Xianghua; Song, Feng; Hu, Guodong; Cao, Zanxia; Qu, Yuanxu

    2018-01-01

    Abstract Long non-coding RNAs (lncRNAs) play important functional roles in various biological processes. Early databases were utilized to deposit all lncRNA candidates produced by high-throughput experimental and/or computational techniques to facilitate classification, assessment and validation. As more lncRNAs are validated by low-throughput experiments, several databases were established for experimentally validated lncRNAs. However, these databases are small in scale (with a few hundreds of lncRNAs only) and specific in their focuses (plants, diseases or interactions). Thus, it is highly desirable to have a comprehensive dataset for experimentally validated lncRNAs as a central repository for all of their structures, functions and phenotypes. Here, we established EVLncRNAs by curating lncRNAs validated by low-throughput experiments (up to 1 May 2016) and integrating specific databases (lncRNAdb, LncRANDisease, Lnc2Cancer and PLNIncRBase) with additional functional and disease-specific information not covered previously. The current version of EVLncRNAs contains 1543 lncRNAs from 77 species that is 2.9 times larger than the current largest database for experimentally validated lncRNAs. Seventy-four percent lncRNA entries are partially or completely new, comparing to all existing experimentally validated databases. The established database allows users to browse, search and download as well as to submit experimentally validated lncRNAs. The database is available at http://biophy.dzu.edu.cn/EVLncRNAs. PMID:28985416

  15. The relationship between component skills, reading experience, and reading comprehension in Danish 3rd graders

    DEFF Research Database (Denmark)

    Rønberg, Louise Flensted-Jensen; Petersen, Dorthe Klint

    data sets were obtained from 179 Danish Grade 3 pupils. Participants were given a standard reading comprehension test requiring multiple-choice answers to six different texts of various length and type. Orthographic and phonological coding, as well as non-verbal problem solving were assessed by means......Purpose The main aim of this study was to investigate the contribution of aspects of vocabulary, word reading abilities, and reading experience to reading comprehension, and to analyse sub-samples of students with comprehension difficulties. Method The study employed a cross-sectional design. Full......: path, street, road, river). Results Data analyses showed that in the entire sample, skills of semantic lexical structuring and reading experience made strong contributions to reading comprehension. Analyses of the pupils below the 25%-percentile in reading comprehension revealed that for the vast...

  16. Fundamentals of convolutional coding

    CERN Document Server

    Johannesson, Rolf

    2015-01-01

    Fundamentals of Convolutional Coding, Second Edition, regarded as a bible of convolutional coding brings you a clear and comprehensive discussion of the basic principles of this field * Two new chapters on low-density parity-check (LDPC) convolutional codes and iterative coding * Viterbi, BCJR, BEAST, list, and sequential decoding of convolutional codes * Distance properties of convolutional codes * Includes a downloadable solutions manual

  17. User's manual for ASTERIX-2: a two-dimensional modular-code system for the steady-state and xenon-transient analysis of a pebble-bed high-temperature reactor

    International Nuclear Information System (INIS)

    Lauer, A.; Schwiegk, H.J.; Wu, T.; Cowan, C.L.

    1982-03-01

    The ASTERIX modular code package was developed at KFA Laboratory-Juelich for the steady state and xenon transient analysis of a pebble bed high temperature reactor. The code package was implemented on the Stanford Linear Accelerator Center Computer in August, 1980, and a user's manual for the current version of the code, identified as ASTERIX-2, was prepared as a cooperative effort by KFA Laboratory and GE-ARSD. The material in the manual includes the requirements for accessing the program, a description of the major subroutines, a listing of the input options, and a listing of the input data for a sample problem. The material is provided in sufficient detail for the user to carry out a wide range of analyses from steady state operations to the xenon induced power transients in which the local xenon, temperature, buckling and control feedback effects have been incorporated in the problem solution

  18. Do 2nd and 3rd Grade Teachers' Linguistic Knowledge and Instructional Practices Predict Spelling Gains in Weaker Spellers?

    Science.gov (United States)

    Puliatte, Alison; Ehri, Linnea C.

    2018-01-01

    The relationship between 2nd and 3rd grade teachers' linguistic knowledge and spelling instructional practices and their students' spelling gains from fall to spring was examined. Second grade (N = 16) and 3rd grade (N = 16) teachers were administered an instructional practices survey and a linguistic knowledge test. Total scores on the two…

  19. Lnc2Meth: a manually curated database of regulatory relationships between long non-coding RNAs and DNA methylation associated with human disease.

    Science.gov (United States)

    Zhi, Hui; Li, Xin; Wang, Peng; Gao, Yue; Gao, Baoqing; Zhou, Dianshuang; Zhang, Yan; Guo, Maoni; Yue, Ming; Shen, Weitao; Ning, Shangwei; Jin, Lianhong; Li, Xia

    2018-01-04

    Lnc2Meth (http://www.bio-bigdata.com/Lnc2Meth/), an interactive resource to identify regulatory relationships between human long non-coding RNAs (lncRNAs) and DNA methylation, is not only a manually curated collection and annotation of experimentally supported lncRNAs-DNA methylation associations but also a platform that effectively integrates tools for calculating and identifying the differentially methylated lncRNAs and protein-coding genes (PCGs) in diverse human diseases. The resource provides: (i) advanced search possibilities, e.g. retrieval of the database by searching the lncRNA symbol of interest, DNA methylation patterns, regulatory mechanisms and disease types; (ii) abundant computationally calculated DNA methylation array profiles for the lncRNAs and PCGs; (iii) the prognostic values for each hit transcript calculated from the patients clinical data; (iv) a genome browser to display the DNA methylation landscape of the lncRNA transcripts for a specific type of disease; (v) tools to re-annotate probes to lncRNA loci and identify the differential methylation patterns for lncRNAs and PCGs with user-supplied external datasets; (vi) an R package (LncDM) to complete the differentially methylated lncRNAs identification and visualization with local computers. Lnc2Meth provides a timely and valuable resource that can be applied to significantly expand our understanding of the regulatory relationships between lncRNAs and DNA methylation in various human diseases. © The Author(s) 2017. Published by Oxford University Press on behalf of Nucleic Acids Research.

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

    International Nuclear Information System (INIS)

    2001-01-01

    generated by each plant and the user specified characteristics of fuels used. Expanded dimensions for handling up to 90 types of plants and a larger number of configurations (up to 500 per year and 5000 for the study period). The present manual allows us to support the use of the WASP-IV version and to illustrate the capabilities of the model. This manual contains 13 chapters. Chapter 1 gives a summary description of WASP-IV Computer Code and its Modules and file system. Chapter 2 explains the hardware requirement and the installation of the package. The sequence of the execution of WASP-IV is also briefly introduced in this chapter. Chapters 3 to 9 explains, in detail, how to execute each of the module of WASP-IV package, the organisation of input files and output from the run of the model. Special attention was paid to the description of the linkage of modules. Chapter 10 specially guides the users on how to effectively search for an optimal solution. Chapter 11 describes the execution of sensitivity analyses that can be (recommend to be) performed with WASP-IV. To ease the debugging during the running of the software, Chapter 12 provides technical details of the new features incorporated in this version. Chapter 13 provides a list of error and warning messages produced for each module of WASP. The reader of this manual is assumed to have experience in the field of power generation expansion planning and to be familiar with all concepts related to such type of analysis, therefore these aspects are not treated in this manual. Additional information on power generation expansion planning can be found in the IAEA publication 'Expansion Planning for Electrical Generating Systems, A Guidebook', Technical Reports Series No. 241 (1984) or User's Manual of WASP-IV Plus, Computer Manual Series No. 8, (1995)

  1. “Patenting Bioprinting Technologies in the US and Europe– The 5th element in the 3rd dimension"

    DEFF Research Database (Denmark)

    Minssen, Timo; Mimler, Marc

    2017-01-01

    of bioprinting- inventions are being patented or would be- protectable under European and US patent laws. Rather than focusing on the highly relevant questions that 3D printing poses for patent infringement doctrines and research exemptions , this paper concentrates on the question of patentable subject matter......, “Patenting Bioprinting Technologies in the US and Europe– The 5th element in the 3rd dimension", Working Paper, forthcoming in: RM Ballardini, M Norrgård & J Partanen (red), 3D printing, Intellectual Property and Innovation – Insights from Law and Technology. Wolters Klu. Available at https...

  2. Comparison of Assemblies of Four-Link Structural Groups of 3rd Class on the Transmission Angle

    Directory of Open Access Journals (Sweden)

    Matsyuk I.N.

    2016-05-01

    Full Text Available Comparison of various assemblies of four-link structural group of 3rd class with revolute joints on the transmission angle is performed. Equations of the trajectories of plug points of one of the groups of joint are obtained to determine transmission angles. Derived functions of these equations enable to determine the values of transmission angles for each assembly group. It is shown that only two assemblies of maximum possible assembling number of such group (six have practical value. The solution of this problem was performed with the help of Mathcad program.

  3. 3rd DAtF-seminar on the development of potential for young scientists and engineers in nuclear technology

    International Nuclear Information System (INIS)

    Gassner, H.

    2003-01-01

    The 3 rd seminar organized by the Deutsches Atomforum e.V. for young nuclear scientists and engineers seeking to realize their potential was about 'Communication - Key to Acceptance'. The topic was presented in contributions outlining the scientific viewpoint and in results of practical everyday experience. The young participants from all areas of the nuclear industry were sensitized to the problem areas under discussion, which were then debated in more detail. Reference was made to the importance of continuous communication with all participants. The seminar offered valuable suggestions for working with the media and the public, but also for handling information in one's daily work. (orig.)

  4. 3rd International Meeting for Researchers in Materials and Plasma Technology (IMRMPT) and 1st Symposium on Nanoscience and Nanotechnology

    International Nuclear Information System (INIS)

    2016-01-01

    These proceedings present the written contributions of the participants of the 3rd International Meeting for Researchers in Materials and Plasma Technology (3rd IMRMPT) and the 1st Symposium on Nanoscience and Nanotechnology which was held from 4 to May 9, 2015 at the Dann Carlton Hotel Bucaramanga, Colombia, organized by the faculty of science of the Universidad Industrial de Santander (UIS) and the basic science department of the Universidad Pontificia Bolivariana. This was the third version of biennial meetings that began in 2011. The five-day scientific program of the 3rd IMRMPT consisted of 24 Magisterial Conferences, 70 Oral Presentations, 185 Poster Presentations, 3 Courses and 1 Discussion Panel with the participation of undergraduate and graduate students, professors, researchers and entrepreneurs from Colombia, Russia, Germany, France, Spain, England, United States, Mexico, Argentina, Uruguay, Brazil, Venezuela, among others. Moreover, the objective of IMRMPT was to bring together national and international researchers in order to establish a network of scientific cooperation with a global impact in the area of the science and the technology of materials; to promote the exchange of creative ideas and the effective transfer of scientific knowledge, from fundamental research to innovation applied to industrial solutions and to advances in the development of new research allowing to increase the lifetime of the materials used in the industry by means of efficient transference of the knowledge between sectors academia and industry. The topics covered in the 3rd IMRMPT include New Materials, Surface Physics, Structural Integrity, Renewable Energy, Online Process Control, Non Destructive Evaluation, Characterization of Materials, Laser and Hybrid Processes, Thin Films and Nanomaterials, Surface Hardening Processes, Wear and Corrosion/Oxidation, Plasma Applications and Technologies, Modelling, Simulation and Diagnostics, Biomedical Coatings, Surface Treatments

  5. TUMULI, ROADS AND PLOTS. DECODING THE MONUMENTAL FUNERARY SPACE OF THE 4TH-3RD CENTURIES BC KALLATIS

    Directory of Open Access Journals (Sweden)

    Maria Magdalena Ștefan

    2017-03-01

    Full Text Available The study focusses on the monumental elements of the 4th-3rd centuries BC cemeteries of Kallatis: the use of large tumuli, the implementation of a systematized network of funerary plots, the extent of the burial grounds, the discovery of a series of built chamber tombs under tumuli with elements of decorated architecture, including mural paintings and exceptional presence of a statue topping a tumulus. The detection and morphological characterisation of archaeological features and the recovering of the funerary landscapes’ spatial layout were based on historiographic study, remote-sensing and geophysical investigations.

  6. Radiological Control Manual

    Energy Technology Data Exchange (ETDEWEB)

    1993-04-01

    This manual has been prepared by Lawrence Berkeley Laboratory to provide guidance for site-specific additions, supplements, and clarifications to the DOE Radiological Control Manual. The guidance provided in this manual is based on the requirements given in Title 10 Code of Federal Regulations Part 835, Radiation Protection for Occupational Workers, DOE Order 5480.11, Radiation Protection for Occupational Workers, and the DOE Radiological Control Manual. The topics covered are (1) excellence in radiological control, (2) radiological standards, (3) conduct of radiological work, (4) radioactive materials, (5) radiological health support operations, (6) training and qualification, and (7) radiological records.

  7. Radiological Control Manual

    International Nuclear Information System (INIS)

    1993-04-01

    This manual has been prepared by Lawrence Berkeley Laboratory to provide guidance for site-specific additions, supplements, and clarifications to the DOE Radiological Control Manual. The guidance provided in this manual is based on the requirements given in Title 10 Code of Federal Regulations Part 835, Radiation Protection for Occupational Workers, DOE Order 5480.11, Radiation Protection for Occupational Workers, and the DOE Radiological Control Manual. The topics covered are (1) excellence in radiological control, (2) radiological standards, (3) conduct of radiological work, (4) radioactive materials, (5) radiological health support operations, (6) training and qualification, and (7) radiological records

  8. A procedure for safety assessment of components with cracks - Handbook. 3rd revised edition

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, P.; Bergman, M.; Brickstad, B.; Dahlberg, L.; Nilsson, F.; Sattari-Far, I. [SAQ Kontroll AB, Stockholm (Sweden)

    1999-12-01

    given objectives, the handbook contains solutions for the stress intensity factor and the limit load for a number of crack geometries of importance for applications. It also contains rules for defect characterization, recommendations for estimation of residual stresses, material data for nuclear applications and a safety evaluation system. To ensure conservatism, the procedure with the given solutions of the stress intensity factor and the limit load has been validated. Predictions of the procedure were compared with the actual outcome of full scale experiments reported in the literature. The first edition of the handbook was released in 1990 and the second in 1991. This third edition has been extensively revised. A new safety evaluation system has been introduced. The conservatism in the method for assessment of secondary stresses has been reduced. The solutions for the stress intensity factor and the limit load, the recommendations for estimation of residual stresses and the given material data for nuclear applications have been updated. A modern Windows based PC-program SACC has been developed which can perform the assessments described in this handbook including calculation of crack growth due to stress corrosion and fatigue. The program also has an option which enables assessment of cracks according to the 1995 edition of the ASME Boiler and Pressure Vessel Code, Section XI. Appendices A, C and H for assessment of cracks in ferritic pressure vessels, austenitic piping and ferritic piping, respectively.

  9. A procedure for safety assessment of components with cracks - Handbook. 3rd revised edition

    International Nuclear Information System (INIS)

    Andersson, P.; Bergman, M.; Brickstad, B.; Dahlberg, L.; Nilsson, F.; Sattari-Far, I.

    1999-12-01

    , the handbook contains solutions for the stress intensity factor and the limit load for a number of crack geometries of importance for applications. It also contains rules for defect characterization, recommendations for estimation of residual stresses, material data for nuclear applications and a safety evaluation system. To ensure conservatism, the procedure with the given solutions of the stress intensity factor and the limit load has been validated. Predictions of the procedure were compared with the actual outcome of full scale experiments reported in the literature. The first edition of the handbook was released in 1990 and the second in 1991. This third edition has been extensively revised. A new safety evaluation system has been introduced. The conservatism in the method for assessment of secondary stresses has been reduced. The solutions for the stress intensity factor and the limit load, the recommendations for estimation of residual stresses and the given material data for nuclear applications have been updated. A modern Windows based PC-program SACC has been developed which can perform the assessments described in this handbook including calculation of crack growth due to stress corrosion and fatigue. The program also has an option which enables assessment of cracks according to the 1995 edition of the ASME Boiler and Pressure Vessel Code, Section XI. Appendices A, C and H for assessment of cracks in ferritic pressure vessels, austenitic piping and ferritic piping, respectively

  10. AN ANALYSIS OF STUDENTS’ SPEAKING ABILITY IN ENGLISH CONVERSATION CLUB (ECC PROGRAM AT THE 3rd SEMESTER

    Directory of Open Access Journals (Sweden)

    M. Fadhly Farhy Abbas

    2017-07-01

    Full Text Available This research is based on students’ speaking ability who had followed the EnglishConversation Club (ECC program especially for the third semester of English Department. Thepurpose of this study was to analyze the students’ speaking ability at the 3rd semester in the EnglishConversation Club FKIP UNILAK Pekanbaru. The type of the research was mixed method in typeof explanatory design. The number of participant was 53 students. The researcher used twoinstruments, those were test and interview. In analyzing the data, it used in descriptive statistics.The result of the analysis showed that the average score of 3rd semester students’ speaking abilitywas 45.42. It can be concluded that the students’ speaking ability was categorized into failed . Thescore of Standard Deviation was 7.02, Variance was 49.30, and Range was 36 points . It meansthat the students’ speaking ability was homogeneous. According to the Z-Score, it can be seen that49.06% students’ ability was higher than average and 50.94% students ability was below theaverage. In conclusion, the students’ ability in learning speaking English was failed, it had beenaffected by some factors, those were lack of vocabulary, grammar and motivation. It was supportedby the interview, eventhough the students’ perception to English Conversation Club (ECCprogram was positive, but in fact, the students’ frequency to speak English was seldom, they wereless practice speaking English everyday.Keywords : Speaking , English Conversation Club (ECC

  11. Differentiation of initial skills in 1st grade and the relative age effect in 3rd grade

    Directory of Open Access Journals (Sweden)

    KRZYSZTOF KONARZEWSKI

    2017-06-01

    Full Text Available The paper aims to verify two hypotheses. The first states that the differentiation of initial 1st grade pupil skills is negatively correlated with age at entry to school. This was tested according to findings from the ERI study Six and seven year olds at the start of school. The variation of reading and writing scores of 1164 pupils aged 5.9–7.9 years who were beginning 1st grade decreased in subsequent age quartiles. The second hypothesis – that classroom differentiation of pupils’ initial skills in 1st grade is positively correlated with the birthdate effect in 3rd grade – was tested on data of 4838 pupils from 254 classrooms drawn from the 2011 PIRLS and TIMSS studies in Poland. Skills were evaluated on the basis of parental reports. Hierarchical linear analysis (gender, SES and school location controlled showed that the greater the differentiation of language skills in 1st grade, the greater the birthdate effect in mathematics in 3rd grade. This result suggests that school entry age is of lesser importance than the methods used to reduce differences in children’s school readiness at the onset of education.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2003-07-01

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

  13. SHARP User Manual

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-03-31

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

  14. SHARP User Manual

    International Nuclear Information System (INIS)

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

    2016-01-01

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

  15. MINTEQ user's manual

    International Nuclear Information System (INIS)

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

    1987-02-01

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

  16. Linac-augmented light sources : an incremental concept for enhancing the capabilities of existing 3rd-generation storage rings

    International Nuclear Information System (INIS)

    Lewellen, J. W.

    2003-01-01

    Planned and proposed 4th-generation x-ray sources, such as energy-recovery linacs (ERLs) and single-pass x-ray free-electron lasers (X-FELs) offer a number of potential advantages, including small source size, higher peak brightness, ultrashort pulses, and potentially temporally and transversely coherent pulses. While offering unique capabilities, such facilities will also offer several important limitations, including limited numbers of user beamlines (for FELs) and a pulse-repetition rate that may be too high for many dynamics experiments (ERLs). In addition, there are many technical challenges associated with both types of facilities. A third type of facility, exemplified by the Short Pulse Photon Source (SPPS) at SLAC [1], would support neither a large number of users simultaneously nor generate coherent pulses, but would generate very intense, short x-ray pulses. Such a facility could serve as the starting point for either an ERL or an X-FEL, or a combined, hybrid machine. For the foreseeable future, however, existing 3rd-generation light source storage rings, such as the Advanced Photon Source, will continue to play important roles in supporting scientific research utilizing high-brightness x-rays. Existing facilities offer the powerful combination of a large number of user beamlines, efficient use of electron beam energy, and established user communities, and a program of incremental investment in, and improvements to, these facilities should continue to pay dividends into the future. This document discusses potential upgrade paths based on the Advanced Photon Source (APS) as a model 3rd-generation facility. If existing 3rd-generation facilities are to remain centers of excellence for light source-based research into the future, they must not only maintain and enhance their support of their existing user base, but also seek to expand their capabilities to support additional classes of users. There are several paths available toward this goal. The APS is

  17. Main results on pilot operation during 5 years of the 3rd generation fuel in VVER-440 reactors of Kola NPP

    International Nuclear Information System (INIS)

    Saprykin, V.; Sumarokov, M.; Gagarinskiy, A.; Sumarokova, A.; Adeev, V.

    2015-01-01

    In the report the results of comparison of main neutron-physical data of exploitation of nuclear fuel are presented for the average enrichment (on U - 235) of 4.87 for the 2nd and 3rd (12 piece) generations with the results of calculations by the complex of the programs KASKAD for 5 fuel loadings of Kola NPP Unit 4 with the reactor VVER- 440. The basic feature of fuel of the 3rd generation as compared with the 2nd is a presence of ribs of inflexibility at corners instead of cover of the fuel assembly and also the increased amount of uranium. The arrangement of fuel rods with different enrichment in fuel assemblies of the 2nd and 3rd generations is chosen identical for the convenient comparison of neutronic and thermohydraulic characteristics of the fuel of different generations. The fuel of 3rd generation was situated in the core symmetrically to the fuel of 2nd one

  18. Results of the independent verification of radiological remedial action at 280 South 3rd East Street, Monticello, Utah (MS00099)

    International Nuclear Information System (INIS)

    Crutcher, J.W.; Wilson, M.J.

    1990-02-01

    In 1980 the site of a vanadium and uranium mill at Monticello, Utah, was accepted into the US Department of Energy's (DOE's) Surplus Facilities Management Program, with the objectives of restoring the government-owned mill site to safe levels of radioactivity, disposing of or containing the tailings in an environmentally safe manner, and performing remedial actions on off-site (vicinity) properties that had been contaminated by radioactive material resulting from mill operations. During 1985 and 1986, UNC Geotech, the remedial action contractor designated by DOE, performed remedial action on the vicinity property at 280 South 3rd East Street, Monticello, Utah. The Pollutant Assessments Group (PAG) of Oak Ridge National Laboratory was assigned the responsibility of verifying the data supporting the adequacy of remedial action and confirming the site's compliance with DOE guidelines. The PAG found that the site successfully meets the DOE remedial action objectives. Procedures used by PAG are described. 3 refs., 2 tabs

  19. Results of the independent verification of radiological remedial action at 397 East 3rd South Street, Monticello, Utah (MS00168)

    International Nuclear Information System (INIS)

    Wilson, M.J.; Crutcher, J.W.

    1991-07-01

    In 1980 the site of a vanadium and uranium mill at Monticello, Utah, was accepted into the US Department of Energy's (DOE's) Surplus Facilities Management Program, with the objectives of restoring the government-owned mill site to safe levels of radioactivity, disposing of or containing the tailings in an environmentally safe manner, and performing remedial actions on off-site (vicinity) properties that had been contaminated by radioactive material resulting from mill operations. During 1987 and 1988, UNC Geotech, the remedial action contractor designated by DOE, performed remedial action on the vicinity property at 397 East 3rd South Street, Monticello, Utah. The Pollutant Assessments Group (PAG) of Oak Ridge National Laboratory was assigned the responsibility of verifying the data supporting the adequacy of remedial action and confirming the site's compliance with DOE guidelines. The PAG found that the site successfully meets the DOE remedial action objectives. Procedures used by PAG are described. 3 refs., 2 tabs

  20. THE 3rd SCHIZOPHRENIA INTERNATIONAL RESEARCH SOCIETY CONFERENCE, 14-18 APRIL 2012, FLORENCE, ITALY: SUMMARIES OF ORAL SESSIONS

    Science.gov (United States)

    Abbs, Brandon; Achalia, Rashmin M; Adelufosi, Adegoke O; Aktener, Ahmet Yiğit; Beveridge, Natalie J; Bhakta, Savita G; Blackman, Rachael K; Bora, Emre; Byun, MS; Cabanis, Maurice; Carrion, Ricardo; Castellani, Christina A; Chow, Tze Jen; Dmitrzak-Weglarz, M; Gayer-Anderson, Charlotte; Gomes, Felipe V; Haut, Kristen; Hori, Hiroaki; Kantrowitz, Joshua T; Kishimoto, Taishiro; Lee, Frankie HF; Lin, Ashleigh; Palaniyappan, Lena; Quan, Meina; Rubio, Maria D; Ruiz de Azúa, Sonia; Sahoo, Saddichha; Strauss, Gregory P; Szczepankiewicz, Aleksandra; Thompson, Andrew D; Trotta, Antonella; Tully, Laura M; Uchida, Hiroyuki; Velthorst, Eva; Young, Jared W; O’Shea, Anne; DeLisi, Lynn E.

    2013-01-01

    The 3rd Schizophrenia International Research Society Conference was held in Florence, Italy, April 14-18, 2012.and this year had as its emphasis, “The Globalization of Research”. Student travel awardees served as rapporteurs for each oral session and focused their summaries on the most significant findings that emerged and the discussions that followed. The following report is a composite of these summaries. We hope that it will provide an overview for those who were present, but could not participate in all sessions, and those who did not have the opportunity to attend, but who would be interested in an update on current investigations ongoing in the field of schizophrenia research. PMID:22910407

  1. Quantification of bone mineral density at 3rd lumbar vertebra by dual photon absorptiometry in healthy subjects

    International Nuclear Information System (INIS)

    Fukunaga, Masao; Otsuka, Nobuaki; Ono, Shimato

    1987-01-01

    Bone mineral density (BMD), by dual photon absorptiometry (DPA), at the 3rd lumbar vertebra (L 3 ) was measured in healthy subjects (37 males and 49 females). BMD values on 1 slice of vertebral body (L 3 ), employed as a routine, showed good correlation to the mean BMD values, calculated from multiple slices of whole L 3 . BMD values, by DPA, at L 3 were better correlation to concentrations of bone mineral equivalent material, by quantitative computed tomography, at the trabecular bone of L 3 than to BMD values, by single photon absorptiometry, at distal radius (predominantly cortical bone). Furthermore, by this DPA technique, bone diminution at L 3 with aging was shown in both sexes. These data suggest that measurements of BMD by DPA is greatly useful for evaluating the spinal bone mineral content. (author)

  2. 3rd Singularity Theory Meeting of Northeast region & the Brazil-Mexico 2nd Meeting on Singularities

    CERN Document Server

    Neto, Aurélio; Mond, David; Saia, Marcelo; Snoussi, Jawad; BMMS 2/NBMS 3; ENSINO; Singularities and foliations geometry, topology and applications

    2018-01-01

    This proceedings book brings selected works from two conferences, the 2nd Brazil-Mexico Meeting on Singularity and the 3rd Northeastern Brazilian Meeting on Singularities, that were hold in Salvador, in July 2015. All contributions were carefully peer-reviewed and revised, and cover topics like Equisingularity, Topology and Geometry of Singularities, Topological Classification of Singularities of Mappings, and more. They were written by mathematicians from several countries, including Brazil, Spain, Mexico, Japan and the USA, on relevant topics on Theory of Singularity, such as studies on deformations, Milnor fibration, foliations, Catastrophe theory, and myriad applications. Open problems are also introduced, making this volume a must-read both for graduate students and active researchers in this field.

  3. Results of the independent verification of radiological remedial action at 381 East 3rd South Street, Monticello, Utah (MS00140)

    International Nuclear Information System (INIS)

    Crutcher, J.W.; Smuin, M.W.

    1989-10-01

    In 1980 the site of a vanadium and uranium mill at Monticello, Utah, was accepted into the US Department of Energy (DOE's) Surplus Facilities Management Program, with the objectives of restoring the government-owned mill site to safe levels of radioactivity, disposing of or containing the tailings in an environmentally safe manner, and performing remedial actions on off-site (vicinity) properties that had been contaminated by radioactive material resulting from mill operations. During 1986, UNC Geotech, the remedial action contractor designated by DOE, performed remedial action on the vicinity at 381 East 3rd South Street, Monticello, Utah. The Pollutant Assessments group (PAG) of Oak Ridge National Laboratory was assigned the responsibility of verifying the data supporting the adequacy of remedial action and confirming the site's compliance with DOE guidelines. The PAG found that the site successfully meets the DOE remedial action objectives. Procedures used by PAG are described. 3 refs., 2 tabs

  4. Results of the independent verification of radiological remedial action at 281 East 3rd South Street, Monticello, Utah (MS00138)

    International Nuclear Information System (INIS)

    Crutcher, J.W.; Wilson, M.J.

    1990-02-01

    In 1980 the site of a vanadium and uranium mill at Monticello, Utah, was accepted into the US Department of Energy's (DOE's) Surplus Facilities Management Program, with the objectives of restoring the government-owned mill site to safe levels of radioactivity, disposing of or containing the tailings in an environmentally safe manner, and performing remedial actions on off-site (vicinity) properties that had been contaminated by radioactive material resulting from mill operations. During 1985, UNC Geotech, the remedial action contractor designated by DOE, performed remedial action on the vicinity property at 281 East 3rd South Street, Monticello, Utah. The Pollutant Assessments Group (PAG) of Oak Ridge National Laboratory was assigned the responsibility of verifying the data supporting the adequacy of remedial action and confirming the site's compliance with DOE guidelines. The PAG found that the site successfully meets the DOE remedial action objectives. Procedures used by PAG are described. 3 refs., 2 tabs

  5. Results of the independent verification of radiological remedial action at 196 East 3rd South Street, Monticello, Utah (MS00083)

    International Nuclear Information System (INIS)

    Crutcher, J.W.; Smuin, M.W.

    1989-10-01

    In 1980 the site of a vanadium and uranium mill at Monticello, Utah, was accepted into the US Department of Energy's (DOE) Surplus Facilities Management program with the objectives of restoring the government-owned mill site to safe levels of radioactivity, disposing of or containing the tailings in an environmentally safe manner, and performing remedial actions on off-site (vicinity) properties that had been contaminated by radioactive material resulting from mill operations. During 1984 and 1985, UNC Geotech, the remedial action contractor designated by DOE, performed remedial action on the vicinity property at 196 East 3rd South Street, Monticello, Utah. The Pollutant Assessments Group (PAG) of Oak Ridge National Laboratory was assigned the responsibility of verifying the data supporting the adequacy of remedial action and confirming the site's compliance with DOE guidelines. The PAG found that the site successfully meets the DOE remedial action objectives. Procedures used by PAG are described. 3 refs., 2 tabs

  6. 3rd SAGA Workshop

    CERN Document Server

    Conti, Giuseppe

    2014-01-01

    Mathematical algorithms are a fundamental component of Computer Aided Design and Manufacturing (CAD/CAM) systems. This book provides a bridge between algebraic geometry and geometric modelling algorithms, formulated within a computer science framework. Apart from the algebraic geometry topics covered, the entire book is based on the unifying concept of using algebraic techniques – properly specialized to solve geometric problems – to seriously improve accuracy, robustness and efficiency of CAD-systems. It provides new approaches as well as industrial applications to deform surfaces when animating virtual characters, to automatically compare images of handwritten signatures, and to improve control of NC machines. This book further introduces a noteworthy representation based on 2D contours, which is essential to model the metal sheet in industrial processes. It additionally reviews applications of numerical algebraic geometry to differential equations systems with multiple solutions and bifurcations. Futur...

  7. 3rd IDPASC School

    CERN Document Server

    Lectures on particle physics, astrophysics and cosmology

    2015-01-01

    This volume gathers the content of the courses held at the Third IDPASC School, which took place in San Martiño Pinario, Hospederia and Seminario Maior, in the city of Santiago de Compostela, Galiza, Spain, from January 21st to February 2nd, 2013. This school is the annual joint program of the International Doctorate Network in Particle Physics, Astrophysics, and Cosmology (IDPASC).   The purpose of the school series is to present doctoral students from different universities and laboratories in Europe and beyond with a broad range of the latest results and current state of the art in the fields of Particle Physics, Astrophysics, and Cosmology, and to further introduce them to both the questions now posed by the potentials of physics and to challenges connected with current and future experiments – in particular, with the newly available energy ranges.   Following these guidelines, the content of this third edition of the IDPASC School was jointly planned by the Academic Council and by the network’s In...

  8. 3rd Dynamics Days

    CERN Document Server

    Clerc, Marcel

    2016-01-01

    This book presents recent advances, new ideas and novel techniques related to the field of nonlinear dynamics, including localized pattern formation, self-organization and chaos. Various natural systems ranging from nonlinear optics to mechanics, fluids and magnetic are considered. The aim of this book is to gather specialists from these various fields of research to promote cross-fertilization and transfer of knowledge between these active research areas. In particular, nonlinear optics and laser physics constitute an important part in this issue due to the potential applications for all-optical control of light, optical storage, and information processing. Other possible applications include the generation of ultra-short pulses using all-fiber cavities.

  9. WAM-E user's manual

    International Nuclear Information System (INIS)

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

    1986-07-01

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

  10. Users Manual for the FEHMN application

    International Nuclear Information System (INIS)

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

    1996-01-01

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

  11. TRUBA User Manual

    Energy Technology Data Exchange (ETDEWEB)

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

    2008-04-25

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

  12. TRUBA User Manual

    International Nuclear Information System (INIS)

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

    2008-01-01

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

  13. FISPACT 97: user manual

    International Nuclear Information System (INIS)

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

    1997-05-01

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

  14. ECH power deposition at 3rd harmonic in high elongation TCV discharges sustained by 2nd harmonic current profile broadening

    International Nuclear Information System (INIS)

    Pochelon, A. . E-mail : Antoine.Pochelon@epfl.ch; Arnoux, G.; Camenen, Y.

    2003-01-01

    This paper summarises the present effort aimed at developing high elongation heated discharges and testing their confinement properties at normalised currents for which the highest ideal MHD β-limits are predicted. 2nd harmonic (X2) far off-axis ECH/CD is used to stabilise the plasma vertically at high elongation by broadening the current profile in stationary conditions (during the current flat top and over several current diffusion times). Current broadening is maximal for a power deposition in a narrow region (∼a/5), for a finite toroidal injection angle and for high plasma density using upper lateral launchers to minimise refraction. In these discharges which are twice X2 overdense in the centre, 3rd harmonic (X3) is injected from a top launcher to deposit power in the centre and increase the central pressure, simultaneously with far off-axis X2. Using modulated X3, full absorption is measured by the diamagnetic probe. Absorption higher than calculated by thermal ray tracing is occasionally found, indicating absorption on the electron bulk as well as in the suprathermal electron population sometimes with a hollow deposition profile. The high sensitivity of the power coupling to the beam angle stresses the need for developing a mirror feedback scheme to increase the coupling efficiency in transient heating scenarios. (author)

  15. 3rd Quarter Transportation Report FY 2014: Radioactive Waste Shipments to and from the Nevada National Security Site (NNSS)

    International Nuclear Information System (INIS)

    Gregory, Louis

    2014-01-01

    This report satisfies the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO) commitment to prepare a quarterly summary report of radioactive waste shipments to the Nevada National Security Site (NNSS) Radioactive Waste Management Complex (RWMC) at Area 5. There were no shipments sent for offsite treatment and returned to the NNSS this quarter. This report summarizes the 3rd quarter of Fiscal Year (FY) 2014 low-level radioactive waste (LLW) and mixed low-level radioactive waste (MLLW) shipments. This report also includes annual summaries for FY 2014 in Tables 4 and 5. Tabular summaries are provided which include the following: Sources of and carriers for LLW and MLLW shipments to and from the NNSS; Number and external volume of LLW and MLLW shipments; Highway routes used by carriers; and Incident/accident data applicable to LLW and MLLW shipments. In this report shipments are accounted for upon arrival at the NNSS, while disposal volumes are accounted for upon waste burial. The disposal volumes presented in this report do not include minor volumes of non-radioactive materials that were approved for disposal. Volume reports showing cubic feet generated using the Low-Level Waste Information System may vary slightly due to differing rounding conventions.

  16. Psychometric properties and validation of Portuguese version of Ages & Stages Questionnaires (3rd edition): 9, 18 and 30 Questionnaires.

    Science.gov (United States)

    Lopes, Sónia; Graça, Patrícia; Teixeira, Salete; Serrano, Ana Maria; Squires, Jane

    2015-09-01

    The essential underlying foundations of Early Intervention (EI), in which parents/family play a critical role in their child's development, leads us to conclude that their contribution assessing early detection of problems is fundamental. The Ages & Stages Questionnaires (ASQ) is a standardized screening instrument that has been successfully studied in different countries and cultures. Translate and study the psychometrics proprieties of the Portuguese version of the 9, 18 and 30month questionnaires of the Ages and Stages Questionnaires, 3rd edition (ASQ-3). Cross-sectional study. Validity and reliability were studied in a sample of 234 parents of children within 9, 18 and 30months. The results indicated that the questionnaires had good internal consistency, strong agreement between observers and between observations with two weeks interval, and strong Pearson product-moment correlation coefficients between the overall and the total for each domain. The cutoff points (i.e. 2 standard deviations below the mean domain score), that identifies children who should receive further referral for more comprehensive assessment, were close to those determined in the original ASQ-3 psychometric studies. Cronbach's alpha ranging from .42 to .70 and Pearson's r values varies from .22 to .60. Although some weaknesses were noted in psychometric qualities analysis, it can be concluded that the ASQ-PT of 9, 18 and 30months of age fulfills the requirements of a screening tool validated for the Portuguese population. To allow the early identification of children with developmental problems. Copyright © 2015 Elsevier Ireland Ltd. All rights reserved.

  17. Ultrastructure of the ovary of Dermatobia hominis (Diptera: cuterebridae. I. Development during the 3rd larval instar

    Directory of Open Access Journals (Sweden)

    E. A. Gregorio

    1990-09-01

    Full Text Available The ultrastructure and distribution of gonial and somatic cells in the ovary of Dermatobia hominis was studied during the 3rd larval instar. In larvae weighing between 400 and 500 mg, the ovary is partially divided into basal and apical regions by oblong somatic cells that penetrate from the periphery; these cells show ovoid nucleus and cytoplasm full of microtubules. In both regions, gonial cells with regular outlines, large nucleus and low electron-density cytoplasm are scattered among the interstitial somatic cells. These later cells have small nucleus and electrodense cytoplasm. Clear somatic cells with small nucleus and cytoplasm of very low electron-density are restrict to the apical region of the gonad. Degenerating interstitial somatic cells are seen in the basal portion close to the ovary peduncle. During all this larval period the morphological features of the ovary remain almost the same. At the end of the period there is a gradual deposition of glycogen in the cytoplasm of the somatic cells, increase in the number and density of their mitochondria plus nuclear modification as membrane wrinkling and chromatin condensation in masses.

  18. Palaeopathology of human remains of the 1st century BC–3rd century AD from Armenia (Beniamin, Shirakavan I

    Directory of Open Access Journals (Sweden)

    Khudaverdyan Anahit Yu.

    2015-06-01

    Full Text Available The aim of this article was to document the pathology of the individuals from the archeological sites of Beniamin and Shirakavan I, Armenia, dated on the 1st century BC - 3rd century AD. The findings revealed that two groups differed in mean age at death of adults. At Beniamin it was 24 years, 40.8 years for males and 30.9 years for females, whereas at Shirakavanit it was 29.3 years, 29.6 years for males and 35.8 years for females. The greatest mortality appeared to have occurred when the children reached the age of one year (Beniamin. The population had high number of young-adult females with a cause of death associated with child-bearing. Very few females survived to old age. Traumatic conditions (63.64% and enamel hypoplasias (57.2% have a high frequency in the skeletal material from Shirakavan. The volume of selection of Shirakavan does not allow itself to so big discussion as it was possible with the Beniamin site. Fewer hypoplasias in Beniamin group indicate that food resources were more abundant and more easily exploited. The small frequency of a periodontal disorder indicates that dental hygiene was good during the Antiquity period. We here report a case of possible pituitary dwarfism and a case of decapitation.

  19. From Bottom to Top: Identification to Precision Measurement of 3rd-Generation Quarks with the ATLAS Detector

    CERN Document Server

    AUTHOR|(INSPIRE)INSPIRE-00335926

    The 3rd-generation quarks, bottom ($b$) and top ($t$), are recent additions to the Standard Model of particle physics, and precise characterization of their properties have important implications to searching for new physics phenomena. This thesis presents two analyses which use 4.6 fb$^{-1}$ of $pp$ collision data at $\\sqrt{s} = 7$ TeV collected by the ATLAS detector at the Large Hadron Collider (LHC) to measure their properties. The first is an analysis which measures our ability to identify jets originating from $b$ quarks with machine-learning algorithms applied to simulated and real data, so the result in simulation can be corrected to match that in data. This measurement has implications for our ability to identify processes with b quarks in their final state; $t$ quarks decay to a $b$ quark and a weak vector boson $W$ more than 99% of the time. The second analysis presented measures properties of the $t \\rightarrow Wb$ decay channel associated with phenomena not predicted by the Standard Model, through...

  20. The 3rd Canadian Symposium on Hepatitis C Virus: Expanding Care in the Interferon-Free Era

    Directory of Open Access Journals (Sweden)

    Sonya A MacParland

    2014-01-01

    Full Text Available Hepatitis C virus (HCV currently infects approximately 250,000 individuals in Canada and causes more years of life lost than any other infectious disease in the country. In August 2011, new therapies were approved by Health Canada that have achieved higher response rates among those treated, but are poorly tolerated. By 2014/2015, short-course, well-tolerated treatments with cure rates >95% will be available. However, treatment uptake is poor due to structural, financial, geographical, cultural and social barriers. As such, ‘Barriers to access to HCV care in Canada’ is a crucial topic that must be addressed to decrease HCV disease burden and potentially eliminate HCV in Canada. Understanding how to better care for HCV-infected individuals requires integration across multiple disciplines including researchers, clinical services and policy makers to address the major populations affected by HCV including people who inject drugs, baby boomers, immigrants and Aboriginal and/or First Nations people. In 2012, the National CIHR Research Training Program in Hepatitis C organized the 1st Canadian Symposium on Hepatitis C Virus (CSHCV in Montreal, Quebec. The 2nd CSHCV was held in 2013 in Victoria, British Columbia. Both symposia were highly successful, attracting leading international faculty with excellent attendance leading to dialogue and knowledge translation among attendees of diverse backgrounds. The current article summarizes the 3rd CSHCV, held February 2014, in Toronto, Ontario.

  1. PREFACE: Special section featuring selected papers from the 3rd International Workshop on Numerical Modelling of High Temperature Superconductors Special section featuring selected papers from the 3rd International Workshop on Numerical Modelling of High Temperature Superconductors

    Science.gov (United States)

    Granados, Xavier; Sánchez, Àlvar; López-López, Josep

    2012-10-01

    The development of superconducting applications and superconducting engineering requires the support of consistent tools which can provide models for obtaining a good understanding of the behaviour of the systems and predict novel features. These models aim to compute the behaviour of the superconducting systems, design superconducting devices and systems, and understand and test the behavior of the superconducting parts. 50 years ago, in 1962, Charles Bean provided the superconducting community with a model efficient enough to allow the computation of the response of a superconductor to external magnetic fields and currents flowing through in an understandable way: the so called critical-state model. Since then, in addition to the pioneering critical-state approach, other tools have been devised for designing operative superconducting systems, allowing integration of the superconducting design in nearly standard electromagnetic computer-aided design systems by modelling the superconducting parts with consideration of time-dependent processes. In April 2012, Barcelona hosted the 3rd International Workshop on Numerical Modelling of High Temperature Superconductors (HTS), the third in a series of workshops started in Lausanne in 2010 and followed by Cambridge in 2011. The workshop reflected the state-of-the-art and the new initiatives of HTS modelling, considering mathematical, physical and technological aspects within a wide and interdisciplinary scope. Superconductor Science and Technology is now publishing a selection of papers from the workshop which have been selected for their high quality. The selection comprises seven papers covering mathematical, physical and technological topics which contribute to an improvement in the development of procedures, understanding of phenomena and development of applications. We hope that they provide a perspective on the relevance and growth that the modelling of HTS superconductors has achieved in the past 25 years.

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

    (FIXSYS plants); user control of the distribution of capital cost expenditures during the construction period (if required to be different from the general 'S' curve distribution used as default). The present document has been produced to support use of the WASP-Ill Plus computer code and to illustrate the capabilities of the program. This Manual is organized in two separate volumes. This first one includes 11 main chapters describing how to use the WASP-Ill Plus computer program. Chapter 1 gives a summary description and some background information about the program. Chapter 2 introduces some concepts, mainly related to the computer requirements imposed by the program, that are used throughout the Manual. Chapters 3 to 9 describe how to execute each of the various programs (or modules) of the WASP-Ill Plus package. (abstract truncated)

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

    International Nuclear Information System (INIS)

    1995-01-01

    (FIXSYS plants); user control of the distribution of capital cost expenditures during the construction period (if required to be different from the general 'S' curve distribution used as default). The present document has been produced to support use of the WASP-Ill Plus computer code and to illustrate the capabilities of the program. This Manual is organized in two separate volumes. This first one includes 11 main chapters describing how to use the WASP-Ill Plus computer program. Chapter 1 gives a summary description and some background information about the program. Chapter 2 introduces some concepts, mainly related to the computer requirements imposed by the program, that are used throughout the Manual. Chapters 3 to 9 describe how to execute each of the various programs (or modules) of the WASP-Ill Plus package. The description for each module shows the user how to prepare the Job Control statements and input data needed to execute the module and how to interpret the printed output produced. The iterative process that should be followed in order to obtain the 'optimal solution' for a WASP case study is covered in Chapters 6 to 8. Chapter 10 explains the use of an auxiliary program of the WASP package which is mainly intended for saving computer time. Lastly, Chapter 11 recapitulates the use of WASP-Ill Plus for executing a generation expansion planning study; describes the several phases normally involved in this type of study; and provides the user with practical hints about the most important aspects that need to be verified at each phase while executing the various WASP modules

  4. Code of Medical Ethics

    Directory of Open Access Journals (Sweden)

    . SZD-SZZ

    2017-03-01

    Full Text Available Te Code was approved on December 12, 1992, at the 3rd regular meeting of the General Assembly of the Medical Chamber of Slovenia and revised on April 24, 1997, at the 27th regular meeting of the General Assembly of the Medical Chamber of Slovenia. The Code was updated and harmonized with the Medical Association of Slovenia and approved on October 6, 2016, at the regular meeting of the General Assembly of the Medical Chamber of Slovenia.

  5. “New” Scythian Complex of the 3rd Century BC on the Right Bank of the Lower Dniester Region

    Directory of Open Access Journals (Sweden)

    Sergey N. Razumov

    2017-09-01

    Full Text Available The article deals with the new attribution of the materials from barrow 20, excavated in 1975 near Semenovka village on the right bank of the Dniester liman, Belgorod-Dnesterovsky district, Odessa region, Ukraine. The only burial of this barrow was still considered as the monument of Babino culture (aka Multi-Cordoned Ware culture of the first quarter of the 2nd millennium BC. The ceramic and metal artifacts found under the barrow were considered during the study of the material culture of the Scythians of the last third of the 1st millennium BC. The thorough analysis of the stratigraphy, planigraphy, funeral rite and artifacts showed that barrow 20 near Semenovka village was built instantaneously, and in fact it is Scythian. A cenotaph was the main complex of the barrow. It came with not only the armament items (iron-socketed arrowheads, spearheads and sockets of spears, horse harness (bronze frontlet with axe-shaped blade and a hook, bronze ringed beads, iron bits and iron snaffle ring, iron round pendants, glass cup, remains of the funeral feast as a ceramic breakage (Rhodes, Sinop, Cos, Cnidus amphorae, two pottery jars and molded vessel, but also with the burial of a dependent person lying crouched on his left side, his head in the eastern sector, in the catacomb. Depth of the fixing of these findings corresponded to the level of the ancient horizon on which the two-sided mainland ejected from the burial construction. Based on the Rhodes amphora marked with the eponym Άγήσιππος of - manufacturer - Έπίγονος 1, the barrow dates back to the last third or last quarter of the 3rd century BC.

  6. NDS EXFOR Manual

    International Nuclear Information System (INIS)

    Lemmel, H.D.

    1979-06-01

    This manual contains the coding rules and formats and NDS internal compilation rules for the exchange format (EXFOR) for the transmission of nuclear reaction data between national and international nuclear data centres, and for the data storage and retrieval system of the IAEA Nuclear Data Section

  7. CANAL user's manual

    International Nuclear Information System (INIS)

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

    1979-11-01

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

  8. Study on applicability of evaluation model of manpower needs for dismantling of equipments in FUGEN-2. Preparation and clean-up process in 3rd/4th feedwater heater room

    International Nuclear Information System (INIS)

    Shibahara, Yuji; Izumi, Masanori; Nanko, Takashi; Tachibana, Mitsuo

    2011-06-01

    Manpower needs for the preparation and clean-up process on the dismantling of equipments in FUGEN 3rd/4th feedwater heater room conducted in 2008 were calculated with the management data evaluation system: PRODIA Code, and it was inspected whether a conventional evaluation model had applicability for large nuclear facilities such as FUGEN or not. It was confirmed that the conventional evaluation model had no applicability for FUGEN causing by the difference in the plant scale between JPDR and FUGEN bringing expansion of working area. The difference between the actual data and the calculated value was improved by reviewing of the evaluation model, and this reviewing process also brought a new evaluation model. (author)

  9. Comprehensive risk reduction in patients with atrial fibrillation : Emerging diagnostic and therapeutic options Executive summary* of the report from the 3rd AFNET/EHRA consensus conference

    NARCIS (Netherlands)

    Kirchhof, Paulus; Lip, Gregory Y. H.; Van Gelder, Isabelle C.; Bax, Jeroen; Hylek, Elaine; Kaeaeb, Stefan; Schotten, Ulrich; Wegscheider, Karl; Boriani, Giuseppe; Ezekowitz, Michael; Diener, Hans; Heidbuchel, Hein; Lane, Deirdre; Mont, Luis; Willems, Stephan; Dorian, Paul; Vardas, Panos; Breithardt, Guenter; Camm, A. John

    2011-01-01

    There are exciting new developments in several areas of atrial fibrillation (AF) management that carry the hope of improving outcomes in AF patients. This paper is an executive summary that summarises the proceedings from the 3rd AFNET/EHRA consensus conference on atrial fibrillation, held in Sophia

  10. Approaches to ultra-low radiation dose coronary artery calcium scoring based on 3rd generation dual-source CT : A phantom study

    NARCIS (Netherlands)

    McQuiston, Andrew D.; Muscogiuri, Giuseppe; Schoepf, U. Joseph; Meinel, Felix G.; Canstein, Christian; Varga-Szemes, Akos; Cannao, Paola M.; Wichmann, Julian L.; Allmendinger, Thomas; Vliegenthart, Rozemarijn; De Cecco, Carlo N.

    Objectives: To investigate to what extent 3rd generation dual-source computed tomography (DSCT) can reduce radiation dose in coronary artery calcium scoring. Methods: Image acquisition was performed using a stationary calcification phantom. Prospectively electrocardiogram (ECG)-triggered 120 kV

  11. Moving from information and collaboration to action: report from the 3rd International Dog Health Workshop, Paris in April 2017.

    Science.gov (United States)

    O'Neill, Dan G; Keijser, Sylvia F A; Hedhammar, Åke; Kisko, Caroline; Leroy, Gregoire; Llewellyn-Zaidi, Aimée; Malm, Sofia; Olson, Patricia N; Packer, Rowena M A; Rousselot, Jean Francois; Seath, Ian J; Stull, Jason W; Bonnett, Brenda N

    2017-01-01

    Breed-related health problems in dogs have received increased focus over the last decade. Responsibility for causing and/or solving these problems has been variously directed towards dog breeders and kennel clubs, the veterinary profession, welfare scientists, owners, regulators, insurance companies and the media. In reality, all these stakeholders are likely to share some responsibility and optimal progress on resolving these challenges requires all key stakeholders to work together. The International Partnership for Dogs (IPFD), together with an alternating host organization, holds biennial meetings called the International Dog Health Workshops (IDHW). The Société Centrale Canine (French Kennel Club) hosted the 3rd IDHW, in Paris, in April, 2017. These meetings bring together a wide range of stakeholders in dog health, science and welfare to improve international sharing of information and resources, to provide a forum for ongoing collaboration, and to identify specific needs and actions to improve health, well-being and welfare in dogs. The workshop included 140 participants from 23 countries and was structured around six important issues facing those who work to improve dog health. These included individualized breed-specific strategies for health and breeding, extreme conformations, education and communication in relation to antimicrobial resistance, behavior and welfare, genetic testing and population-based evidence. A number of exciting actions were agreed during the meeting. These included setting up working groups to create tools to help breed clubs accelerate the implementation of breed-health strategies, review aspects of extreme conformation and share useful information on behavior. The meeting also heralded the development of an online resource of relevant information describing quality measures for DNA testing. A demand for more and better data and evidence was a recurring message stressed across all themes. The meeting confirmed the benefits from

  12. 3rd International School and Conference “Saint Petersburg OPEN 2016” on Optoelectronics, Photonics, Engineering and Nanostructures

    International Nuclear Information System (INIS)

    2016-01-01

    Dear Colleagues, 3rd International School and Conference “Saint Petersburg OPEN 2016” on Optoelectronics, Photonics, Engineering and Nanostructures was held on March 28 - 30, 2016 at St. Petersburg Academic University of the Russian Academy of Sciences. The School and Conference included a series of invited talks given by leading professors with the aim of introducing young scientists to the actual problems and major advances in modern physics and technology. The keynote speakers were Mircea Guina (Tampere University of Technology, Finland) Evgeny I. Terukov (Ioffe Institute RAS, Russia) Victor M. Ustinov (Ioffe Institute RAS, Russia) Peter G. Kazansky (University of Southampton, UK) Alexander O. Golubok (ITMO University, Russia) Georgy E. Cirlin (St Petersburg Academic University RAS, Russia) Levon V. Asryan (Virginia Polytechnic Institute and State University, USA) Andrey A. Lipovskii (Peter the Great St.Petersburg Polytechnic University, Russia) During the poster session all undergraduate and graduate students attending the conference presented their works. A large number of participants with more than 280 student attendees from all over the world allowed the Conference to provide a fertile ground for the fruitful discussions between the young scientists as well as to become a perfect platform for the valuable discussions between student authors and highly experienced scientists. The best student papers, which were selected by the Program Committee and by the invited speakers based on the theses and their poster presentation, were awarded with diplomas of the conference - see the photos. This year “Saint Petersburg OPEN 2016” is organized by St. Petersburg Academic University in cooperation with Peter the Great St. Petersburg Polytechnic University. The School and Conference is supported by the Russian Foundation for Basic Research (Project N 16-32-10060) , Russian Science Foundation, SPIE (The International Society for Optics and Photonics) and OSA (The

  13. PREFACE: 3rd International Conference on Science & Engineering in Mathematics, Chemistry and Physics 2015 (ScieTech 2015)

    Science.gov (United States)

    Gaol, F. L.

    2015-06-01

    The 3rd International Conference on Science & Engineering in Mathematics, Chemistry and Physics 2015 (ScieTech 2015), was held at The Westin Resort Nusa Dua, Bali on 31 January - 1 February 2015. The ScieTech 2015 conference is aimed to bring together researchers, engineers and scientists from around the world. ScieTech 2015 is placed on promoting interaction between the theoretical, experimental, and applied communities, so that a high level exchange is achieved in new and emerging areas within mathematics, chemistry and physics. As we already know that science and technology have brought tremendous benefits for human civilization. People are becoming healthier, wealthier, better educated, more peaceful, increasingly connected, and living longer. Of course, science and technology provide many answers to global challenges, but we will face more complex problems in the next decade due to increasing world population, limitation of energy, and climate change. Therefore, researchers should be more active in conducting research that enables collaboration between one and the others. Interdisciplinary cooperation is absolutely necessary in order to create a smart system for solving the global problems. We need a global and general long-term view of the future with long-range goals for solving complex problems in next decade. Therefore the conference was held to be a forum for researchers from different disciplines to start collaborating and conducting research that provides a solution to the global issues. The theme of ScieTech 2015 was ''The interdisciplinary Application between Mathematics, Chemistry and Physics to enhance the Quality of Life''. We would like to express our sincere gratitude to all in the Technical Program Committee who have reviewed the papers and developed a very interesting conference program as well as the invited and plenary speakers. This year, we received 197 papers and after rigorous review, 59 papers were accepted. The participants came from 19

  14. GASFLOW-MPI. A scalable computational fluid dynamics code for gases, aerosols and combustion. Vol. 2. Users' manual (Revision 1.0)

    Energy Technology Data Exchange (ETDEWEB)

    Xiao, Jianjun; Travis, Jack; Royl, Peter; Necker, Gottfried; Svishchev, Anatoly; Jordan, Thomas

    2016-07-01

    Karlsruhe Institute of Technology (KIT) is developing the parallel computational fluid dynamics code GASFLOW-MPI as a best-estimate tool for predicting transport, mixing, and combustion of hydrogen and other gases in nuclear reactor containments and other facility buildings. GASFLOW-MPI is a finite-volume code based on proven computational fluid dynamics methodology that solves the compressible Navier-Stokes equations for three-dimensional volumes in Cartesian or cylindrical coordinates.

  15. RADTRAN 4: Volume 4, Programmer's manual

    International Nuclear Information System (INIS)

    Kanipe, F.L.; Neuhauser, K.S.

    1992-07-01

    The RADTRAN 4 computer code is designed to analyze radiological consequences and accident risks of transporting radioactive material. This manual provides information useful for interpreting, troubleshooting, or debugging components of the code during development or revision of the program

  16. CTF Theory Manual

    Energy Technology Data Exchange (ETDEWEB)

    Avramova, Maria N. [Pennsylvania State Univ., University Park, PA (United States); Salko, Robert K. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2016-05-25

    Coolant-Boiling in Rod Arrays|Two Fluids (COBRA-TF) is a thermal/ hydraulic (T/H) simulation code designed for light water reactor (LWR) vessel analysis. It uses a two-fluid, three-field (i.e. fluid film, fluid drops, and vapor) modeling approach. Both sub-channel and 3D Cartesian forms of 9 conservation equations are available for LWR modeling. The code was originally developed by Pacific Northwest Laboratory in 1980 and had been used and modified by several institutions over the last few decades. COBRA-TF also found use at the Pennsylvania State University (PSU) by the Reactor Dynamics and Fuel Management Group (RDFMG) and has been improved, updated, and subsequently re-branded as CTF. As part of the improvement process, it was necessary to generate sufficient documentation for the open-source code which had lacked such material upon being adopted by RDFMG. This document serves mainly as a theory manual for CTF, detailing the many two-phase heat transfer, drag, and important accident scenario models contained in the code as well as the numerical solution process utilized. Coding of the models is also discussed, all with consideration for updates that have been made when transitioning from COBRA-TF to CTF. Further documentation outside of this manual is also available at RDFMG which focus on code input deck generation and source code global variable and module listings.

  17. STAT, GAPS, STRAIN, DRWDIM: a system of computer codes for analyzing HTGR fuel test element metrology data. User's manual

    Energy Technology Data Exchange (ETDEWEB)

    Saurwein, J.J.

    1977-08-01

    A system of computer codes has been developed to statistically reduce Peach Bottom fuel test element metrology data and to compare the material strains and fuel rod-fuel hole gaps computed from these data with HTGR design code predictions. The codes included in this system are STAT, STRAIN, GAPS, and DRWDIM. STAT statistically evaluates test element metrology data yielding fuel rod, fuel body, and sleeve irradiation-induced strains; fuel rod anisotropy; and additional data characterizing each analyzed fuel element. STRAIN compares test element fuel rod and fuel body irradiation-induced strains computed from metrology data with the corresponding design code predictions. GAPS compares test element fuel rod, fuel hole heat transfer gaps computed from metrology data with the corresponding design code predictions. DRWDIM plots the measured and predicted gaps and strains. Although specifically developed to expedite the analysis of Peach Bottom fuel test elements, this system can be applied, without extensive modification, to the analysis of Fort St. Vrain or other HTGR-type fuel test elements.

  18. Manual Therapy

    OpenAIRE

    Hakgüder, Aral; Kokino, Siranuş

    2002-01-01

    Manual therapy has been used in the treatment of pain and dysfunction of spinal and peripheral joints for more than a hundred years. Manual medicine includes manipulation, mobilization, and postisometric relaxation techniques. The aim of manual therapy is to enhance restricted movement caused by blockage of joints keeping postural balance, restore function and maintain optimal body mechanics. Anatomic, biomechanical, and neurophysiological evaluations of the leucomotor system is essential for...

  19. A feasibility study on the longer cycle operation of Yonggwang nuclear power plants 3 and 4 (3 rd quarter report)

    Energy Technology Data Exchange (ETDEWEB)

    Zee Sung Kyun; Song, Jae Woong; Ha, Young Joon; Kim, Kyu Tae [Korea Advanced Institute of Science and Technolgoy, Taejon (Korea, Republic of)

    1996-04-01

    In this report, described are results of the feasibility study on applying for the 18-month cycle in Korean Standard Nuclear Power Plants (KSNPs). This report contains results of safety and economic evaluations, radiation source analysis, an effect on changing the calibration period for each component of NSSS, and review on the related regulating codes. 12 refs., 34 tabs., 28 figs. (author)

  20. User's manual to the ICRP Code: a series of computer programs to perform dosimetric calculations for the ICRP Committee 2 report

    International Nuclear Information System (INIS)

    Watson, S.B.; Ford, M.R.

    1980-02-01

    A computer code has been developed that implements the recommendations of ICRP Committee 2 for computing limits for occupational exposure of radionuclides. The purpose of this report is to describe the various modules of the computer code and to present a description of the methods and criteria used to compute the tables published in the Committee 2 report. The computer code contains three modules of which: (1) one computes specific effective energy; (2) one calculates cumulated activity; and (3) one computes dose and the series of ICRP tables. The description of the first two modules emphasizes the new ICRP Committee 2 recommendations in computing specific effective energy and cumulated activity. For the third module, the complex criteria are discussed for calculating the tables of committed dose equivalent, weighted committed dose equivalents, annual limit of intake, and derived air concentration

  1. User's manual to the ICRP Code: a series of computer programs to perform dosimetric calculations for the ICRP Committee 2 report

    Energy Technology Data Exchange (ETDEWEB)

    Watson, S.B.; Ford, M.R.

    1980-02-01

    A computer code has been developed that implements the recommendations of ICRP Committee 2 for computing limits for occupational exposure of radionuclides. The purpose of this report is to describe the various modules of the computer code and to present a description of the methods and criteria used to compute the tables published in the Committee 2 report. The computer code contains three modules of which: (1) one computes specific effective energy; (2) one calculates cumulated activity; and (3) one computes dose and the series of ICRP tables. The description of the first two modules emphasizes the new ICRP Committee 2 recommendations in computing specific effective energy and cumulated activity. For the third module, the complex criteria are discussed for calculating the tables of committed dose equivalent, weighted committed dose equivalents, annual limit of intake, and derived air concentration.

  2. User's manual of a computer code for seismic hazard evaluation for assessing the threat to a facility by fault model. SHEAT-FM

    International Nuclear Information System (INIS)

    Sugino, Hideharu; Onizawa, Kunio; Suzuki, Masahide

    2005-09-01

    To establish the reliability evaluation method for aged structural component, we developed a probabilistic seismic hazard evaluation code SHEAT-FM (Seismic Hazard Evaluation for Assessing the Threat to a facility site - Fault Model) using a seismic motion prediction method based on fault model. In order to improve the seismic hazard evaluation, this code takes the latest knowledge in the field of earthquake engineering into account. For example, the code involves a group delay time of observed records and an update process model of active fault. This report describes the user's guide of SHEAT-FM, including the outline of the seismic hazard evaluation, specification of input data, sample problem for a model site, system information and execution method. (author)

  3. GRSAC Users Manual

    International Nuclear Information System (INIS)

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

    1999-01-01

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

  4. GRSAC Users Manual

    Energy Technology Data Exchange (ETDEWEB)

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

    1999-02-01

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

  5. THEAP-I: A computer program for thermal hydraulic analysis of a thermally interacting channel bundle of complex geometry. Code description and user`s manual

    Energy Technology Data Exchange (ETDEWEB)

    Bartzis, J G; Megaritou, A; Belessiotis, V

    1987-09-01

    THEAP-I is a computer code developed in NRCPS `DEMOCRITUS` with the aim to contribute to the safety analysis of the open pool research reactors. THEAP-I is designed for three dimensional, transient thermal/hydraulic analysis of a thermally interacting channel bundle totally immersed into water or air, such as the reactor core. In the present report the mathematical and physical models and methods of the solution are given as well as the code description and the input data. A sample problem is also included, refering to the Greek Research Reactor analysis, under an hypothetical severe loss of coolant accident.

  6. Universal health coverage and intersectoral action for health: key messages from Disease Control Priorities, 3rd edition

    Science.gov (United States)

    Jamison, Dean T; Adeyi, Olusoji; Anand, Shuchi; Atun, Rifat; Bertozzi, Stefano; Bhutta, Zulfiqar; Binagwaho, Agnes; Black, Robert; Blecher, Mark; Bloom, Barry R; Brouwer, Elizabeth; Bundy, Donald A P; Chisholm, Dan; Cieza, Alarcos; Cullen, Mark; Danforth, Kristen; de Silva, Nilanthi; Debas, Haile T; Donkor, Peter; Dua, Tarun; Fleming, Kenneth A; Gallivan, Mark; Garcia, Patricia J; Gawande, Atul; Gaziano, Thomas; Gelband, Hellen; Glass, Roger; Glassman, Amanda; Gray, Glenda; Habte, Demissie; Holmes, King K; Horton, Susan; Hutton, Guy; Jha, Prabhat; Knaul, Felicia M; Kobusingye, Olive; Krakauer, Eric L; Kruk, Margaret E; Lachmann, Peter; Laxminarayan, Ramanan; Levin, Carol; Looi, Lai Meng; Madhav, Nita; Mahmoud, Adel; Mbanya, Jean Claude; Measham, Anthony; Medina-Mora, María Elena; Medlin, Carol; Mills, Anne; Mills, Jody-Anne; Montoya, Jaime; Norheim, Ole; Olson, Zachary; Omokhodion, Folashade; Oppenheim, Ben; Ord, Toby; Patel, Vikram; Patton, George C; Peabody, John; Prabhakaran, Dorairaj; Qi, Jinyuan; Reynolds, Teri; Ruacan, Sevket; Sankaranarayanan, Rengaswamy; Sepúlveda, Jaime; Skolnik, Richard; Smith, Kirk R; Temmerman, Marleen; Tollman, Stephen; Verguet, Stéphane; Walker, Damian G; Walker, Neff; Wu, Yangfeng; Zhao, Kun

    2018-01-01

    The World Bank is publishing nine volumes of Disease Control Priorities, 3rd edition (DCP3) between 2015 and 2018. Volume 9, Improving Health and Reducing Poverty, summarises the main messages from all the volumes and contains cross-cutting analyses. This Review draws on all nine volumes to convey conclusions. The analysis in DCP3 is built around 21 essential packages that were developed in the nine volumes. Each essential package addresses the concerns of a major professional community (eg, child health or surgery) and contains a mix of intersectoral policies and health-sector interventions. 71 intersectoral prevention policies were identified in total, 29 of which are priorities for early introduction. Interventions within the health sector were grouped onto five platforms (population based, community level, health centre, first-level hospital, and referral hospital). DCP3 defines a model concept of essential universal health coverage (EUHC) with 218 interventions that provides a starting point for country-specific analysis of priorities. Assuming steady-state implementation by 2030, EUHC in lower-middle-income countries would reduce premature deaths by an estimated 4·2 million per year. Estimated total costs prove substantial: about 9·1% of (current) gross national income (GNI) in low-income countries and 5·2% of GNI in lower-middle-income countries. Financing provision of continuing intervention against chronic conditions accounts for about half of estimated incremental costs. For lower-middle-income countries, the mortality reduction from implementing the EUHC can only reach about half the mortality reduction in non-communicable diseases called for by the Sustainable Development Goals. Full achievement will require increased investment or sustained intersectoral action, and actions by finance ministries to tax smoking and polluting emissions and to reduce or eliminate (often large) subsidies on fossil fuels appear of central importance. DCP3 is intended to

  7. Universal health coverage and intersectoral action for health: key messages from Disease Control Priorities, 3rd edition.

    Science.gov (United States)

    Jamison, Dean T; Alwan, Ala; Mock, Charles N; Nugent, Rachel; Watkins, David; Adeyi, Olusoji; Anand, Shuchi; Atun, Rifat; Bertozzi, Stefano; Bhutta, Zulfiqar; Binagwaho, Agnes; Black, Robert; Blecher, Mark; Bloom, Barry R; Brouwer, Elizabeth; Bundy, Donald A P; Chisholm, Dan; Cieza, Alarcos; Cullen, Mark; Danforth, Kristen; de Silva, Nilanthi; Debas, Haile T; Donkor, Peter; Dua, Tarun; Fleming, Kenneth A; Gallivan, Mark; Garcia, Patricia J; Gawande, Atul; Gaziano, Thomas; Gelband, Hellen; Glass, Roger; Glassman, Amanda; Gray, Glenda; Habte, Demissie; Holmes, King K; Horton, Susan; Hutton, Guy; Jha, Prabhat; Knaul, Felicia M; Kobusingye, Olive; Krakauer, Eric L; Kruk, Margaret E; Lachmann, Peter; Laxminarayan, Ramanan; Levin, Carol; Looi, Lai Meng; Madhav, Nita; Mahmoud, Adel; Mbanya, Jean Claude; Measham, Anthony; Medina-Mora, María Elena; Medlin, Carol; Mills, Anne; Mills, Jody-Anne; Montoya, Jaime; Norheim, Ole; Olson, Zachary; Omokhodion, Folashade; Oppenheim, Ben; Ord, Toby; Patel, Vikram; Patton, George C; Peabody, John; Prabhakaran, Dorairaj; Qi, Jinyuan; Reynolds, Teri; Ruacan, Sevket; Sankaranarayanan, Rengaswamy; Sepúlveda, Jaime; Skolnik, Richard; Smith, Kirk R; Temmerman, Marleen; Tollman, Stephen; Verguet, Stéphane; Walker, Damian G; Walker, Neff; Wu, Yangfeng; Zhao, Kun

    2018-03-17

    The World Bank is publishing nine volumes of Disease Control Priorities, 3rd edition (DCP3) between 2015 and 2018. Volume 9, Improving Health and Reducing Poverty, summarises the main messages from all the volumes and contains cross-cutting analyses. This Review draws on all nine volumes to convey conclusions. The analysis in DCP3 is built around 21 essential packages that were developed in the nine volumes. Each essential package addresses the concerns of a major professional community (eg, child health or surgery) and contains a mix of intersectoral policies and health-sector interventions. 71 intersectoral prevention policies were identified in total, 29 of which are priorities for early introduction. Interventions within the health sector were grouped onto five platforms (population based, community level, health centre, first-level hospital, and referral hospital). DCP3 defines a model concept of essential universal health coverage (EUHC) with 218 interventions that provides a starting point for country-specific analysis of priorities. Assuming steady-state implementation by 2030, EUHC in lower-middle-income countries would reduce premature deaths by an estimated 4·2 million per year. Estimated total costs prove substantial: about 9·1% of (current) gross national income (GNI) in low-income countries and 5·2% of GNI in lower-middle-income countries. Financing provision of continuing intervention against chronic conditions accounts for about half of estimated incremental costs. For lower-middle-income countries, the mortality reduction from implementing the EUHC can only reach about half the mortality reduction in non-communicable diseases called for by the Sustainable Development Goals. Full achievement will require increased investment or sustained intersectoral action, and actions by finance ministries to tax smoking and polluting emissions and to reduce or eliminate (often large) subsidies on fossil fuels appear of central importance. DCP3 is intended to

  8. 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

  9. SES2D user's manual

    International Nuclear Information System (INIS)

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

    1982-04-01

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

  10. Summary Staging Manual 2000 - SEER

    Science.gov (United States)

    Access this manual of codes and coding instructions for the summary stage field for cases diagnosed 2001-2017. 2000 version applies to every anatomic site. It uses all information in the medical record. Also called General Staging, California Staging, and SEER Staging.

  11. Radiological control manual. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Kloepping, R.

    1996-05-01

    This Lawrence Berkeley National Laboratory Radiological Control Manual (LBNL RCM) has been prepared to provide guidance for site-specific additions, supplements and interpretation of the DOE Radiological Control Manual. The guidance provided in this manual is one methodology to implement the requirements given in Title 10 Code of Federal Regulations Part 835 (10 CFR 835) and the DOE Radiological Control Manual. Information given in this manual is also intended to provide demonstration of compliance to specific requirements in 10 CFR 835. The LBNL RCM (Publication 3113) and LBNL Health and Safety Manual Publication-3000 form the technical basis for the LBNL RPP and will be revised as necessary to ensure that current requirements from Rules and Orders are represented. The LBNL RCM will form the standard for excellence in the implementation of the LBNL RPP.

  12. Radiological control manual. Revision 1

    International Nuclear Information System (INIS)

    Kloepping, R.

    1996-05-01

    This Lawrence Berkeley National Laboratory Radiological Control Manual (LBNL RCM) has been prepared to provide guidance for site-specific additions, supplements and interpretation of the DOE Radiological Control Manual. The guidance provided in this manual is one methodology to implement the requirements given in Title 10 Code of Federal Regulations Part 835 (10 CFR 835) and the DOE Radiological Control Manual. Information given in this manual is also intended to provide demonstration of compliance to specific requirements in 10 CFR 835. The LBNL RCM (Publication 3113) and LBNL Health and Safety Manual Publication-3000 form the technical basis for the LBNL RPP and will be revised as necessary to ensure that current requirements from Rules and Orders are represented. The LBNL RCM will form the standard for excellence in the implementation of the LBNL RPP

  13. The WECHSL-Mod3 code: A computer program for the interaction of a core melt with concrete including the long term behavior. Model description and user's manual

    International Nuclear Information System (INIS)

    Foit, J.J.; Adroguer, B.; Cenerino, G.; Stiefel, S.

    1995-02-01

    The WECHSL-Mod3 code is a mechanistic computer code developed for the analysis of the thermal and chemical interaction of initially molten reactor materials with concrete in a two-dimensional as well as in a one-dimensional, axisymmetrical concrete cavity. The code performs calculations from the time of initial contact of a hot molten pool over start of solidification processes until long term basemat erosion over several days with the possibility of basemat penetration. It is assumed that an underlying metallic layer exists covered by an oxidic layer or that only one oxidic layer is present which can contain a homogeneously dispersed metallic phase. Heat generation in the melt is by decay heat and chemical reactions from metal oxidation. Energy is lost to the melting concrete and to the upper containment by radiation or evaporation of sumpwater possibly flooding the surface of the melt. Thermodynamic and transport properties as well as criteria for heat transfer and solidification processes are internally calculated for each time step. Heat transfer is modelled taking into account the high gas flux from the decomposing concrete and the heat conduction in the crusts possibly forming in the long term at the melt/concrete interface. The CALTHER code (developed at CEA, France) which models the radiative heat transfer from the upper surface of the corium melt to the surrounding cavity is implemented in the present WECHSL version. The WECHSL code in its present version was validated by the BETA, ACE and SURC experiments. The test samples include a BETA and the SURC2 post test calculations and a WECHSL application to a reactor accident. (orig.) [de

  14. Structures manual

    Science.gov (United States)

    2001-01-01

    This manual was written as a guide for use by design personnel in the Vermont Agency of Transportation Structures Section. This manual covers the design responsibilities of the Section. It does not cover other functions that are a part of the Structu...

  15. Quality Manual

    Science.gov (United States)

    Koch, Michael

    The quality manual is the “heart” of every management system related to quality. Quality assurance in analytical laboratories is most frequently linked with ISO/IEC 17025, which lists the standard requirements for a quality manual. In this chapter examples are used to demonstrate, how these requirements can be met. But, certainly, there are many other ways to do this.

  16. User's manual for DELSOL2: a computer code for calculating the optical performance and optimal system design for solar-thermal central-receiver plants

    Energy Technology Data Exchange (ETDEWEB)

    Dellin, T.A.; Fish, M.J.; Yang, C.L.

    1981-08-01

    DELSOL2 is a revised and substantially extended version of the DELSOL computer program for calculating collector field performance and layout, and optimal system design for solar thermal central receiver plants. The code consists of a detailed model of the optical performance, a simpler model of the non-optical performance, an algorithm for field layout, and a searching algorithm to find the best system design. The latter two features are coupled to a cost model of central receiver components and an economic model for calculating energy costs. The code can handle flat, focused and/or canted heliostats, and external cylindrical, multi-aperture cavity, and flat plate receivers. The program optimizes the tower height, receiver size, field layout, heliostat spacings, and tower position at user specified power levels subject to flux limits on the receiver and land constraints for field layout. The advantages of speed and accuracy characteristic of Version I are maintained in DELSOL2.

  17. THE CLINICAL EFFICACY OF FOSFOMYCIN TROMETAMOL VERSUS AMOXICILLIN-CLAVULANIC ACID IN THE TREATMENT OF SYMPTOMATİC AND ASYMPTOMATİC BACTERIURIA IN 3rd TRIMESTER PREGNANCY

    OpenAIRE

    Süleyman Akarsu; Cengiz Kara; Ömer Faruk Bozkurt; Zeynep Çizmeci; Nermin Akdemir; Ali Ünsal

    2010-01-01

    PURPOSE: This study was conducted to assess the clinical efficacy of a single dose of fosfomycin trometamol for the treatment of both asymptomatic and symptomatic bacteriuria in the third trimester of pregnancy compared with a 7-day regimen of amoxicillin-clavulanic acid MATERIAL – METHODS: In this study clinical efficiency of single dose of 3 g fosfomycin trometamol and 7 day 675 mg amoxicillin-clavulanic acid were compared on 85 pregnant women in 3rd trimester with symptomatic and...

  18. The construction of the CMS electromagnetic calorimeter: delivery of the 3rd and 4th endcap "Dees" and Ring Flanges to CERN

    CERN Multimedia

    2006-01-01

    Delivery of the 3rd and 4th Dees and Ring Flanges of the CMS-ECAL endcaps to CERN. The pictures show also an endcap crystal with its VPT (Vacuum PhotoTriode), the aluminium blackplates of the endcap Dees and four mock supercrystals (5x5 crystals) attached in their position on the backplate, along with 138 positional spacers. Finally, endcap assembly in the CMS construction hall in Cessy (neighbouring France) is also shown.

  19. Medical students’ skills in image interpretation before and after training: A comparison between 3rd-year and 6th-year students from two different medical curricula

    International Nuclear Information System (INIS)

    Sendra-Portero, Francisco; Torales-Chaparro, Oscar E.; Ruiz-Gómez, Miguel J.

    2012-01-01

    The purpose of this study was to assess student's performance in the interpretation of images before and after training in radiology, by comparing two groups, 6th-year and 3rd-year students, from two different medical curricula. Students participated in an anonymous evaluation consisting of the interpretation of 12 radiological images accompanied with the salient history and clinical data by answering 60 open-ended questions about technique, anatomy, semiology, and clinics. The number of correct, incorrect and blank responses of each group was used to compare pre- and post-training results. Unpaired two-sample t-test was used to evaluate differences between groups. A significant increase in correct responses was found in both groups after training. The comparison between both groups did not show differences for incorrect answers of the whole test and correct answers about anatomy in the pre-training evaluation. The percentage of correct answers to the median question improved from 15.5% to 53.3% for 6th-year students and from 8.3% to 41.1% for 3rd-year students. The post-training evaluation showed a significant increase of correct answers of 6th-year students with respect to 3rd-year students (mean ± standard deviation 53.6 ± 31.3% and 38.7 ± 29.9% respectively), mainly due to differences in technical and clinical questions. This study provides objective and quantitative evidence of pre- and post-training student skills in image interpretation. The similarities found in the previous level of knowledge and skills of both groups emphasizes the suitable change of the first-time training in radiology, from the 6th to the 3rd year course in medical curricula.

  20. Radioactive waste management. Introductory statement of the 3rd scientific forum during the 44th session of the IAEA General Conference. Vienna, 19 September 2000

    International Nuclear Information System (INIS)

    ElBaradei, M.

    2000-01-01

    The document reproduces the text of the introductory statement made by the Director General of the IAEA at the 3rd scientific forum organized during the 44th session of the IAEA General Conference, Vienna, 19 september 2000, on the management of radioactive waste. He emphasized the following aspects: progress made in technology and public acceptance, global challenges, international co-operation, building a stronger framework