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Sample records for sara project reflooding

  1. Severe Accident Recriticality Analyses (SARA)

    Energy Technology Data Exchange (ETDEWEB)

    Frid, W. [Swedish Nuclear Power Inspectorate, Stockholm (Sweden); Hoejerup, F. [Risoe National Lab. (Denmark); Lindholm, I.; Miettinen, J.; Puska, E.K. [VTT Energy, Helsinki (Finland); Nilsson, Lars [Studsvik Eco and Safety AB, Nykoeping (Sweden); Sjoevall, H. [Teoliisuuden Voima Oy (Finland)

    1999-11-01

    Recriticality in a BWR has been studied for a total loss of electric power accident scenario. In a BWR, the B{sub 4}C control rods would melt and relocate from the core before the fuel during core uncovery and heat-up. If electric power returns during this time-window unborated water from ECCS systems will start to reflood the partly control rod free core. Recriticality might take place for which the only mitigating mechanisms are the Doppler effect and void formation. In order to assess the impact of recriticality on reactor safety, including accident management measures, the following issues have been investigated in the SARA project: 1. the energy deposition in the fuel during super-prompt power burst, 2. the quasi steady-state reactor power following the initial power burst and 3. containment response to elevated quasi steady-state reactor power. The approach was to use three computer codes and to further develop and adapt them for the task. The codes were SIMULATE-3K, APROS and RECRIT. Recriticality analyses were carried out for a number of selected reflooding transients for the Oskarshamn 3 plant in Sweden with SIMULATE-3K and for the Olkiluoto 1 plant in Finland with all three codes. The core state initial and boundary conditions prior to recriticality have been studied with the severe accident codes SCDAP/RELAP5, MELCOR and MAAP4. The results of the analyses show that all three codes predict recriticality - both superprompt power bursts and quasi steady-state power generation - for the studied range of parameters, i. e. with core uncovery and heat-up to maximum core temperatures around 1800 K and water flow rates of 45 kg/s to 2000 kg/s injected into the downcomer. Since the recriticality takes place in a small fraction of the core the power densities are high which results in large energy deposition in the fuel during power burst in some accident scenarios. The highest value, 418 cal/g, was obtained with SIMULATE-3K for an Oskarshamn 3 case with reflooding

  2. Severe accident recriticality analyses (SARA)

    Energy Technology Data Exchange (ETDEWEB)

    Frid, W. E-mail: wiktor.frid@ski.se; Hoejerup, F.; Lindholm, I.; Miettinen, J.; Nilsson, L.; Puska, E.K.; Sjoevall, H

    2001-11-01

    Recriticality in a BWR during reflooding of an overheated partly degraded core, i.e. with relocated control rods, has been studied for a total loss of electric power accident scenario. In order to assess the impact of recriticality on reactor safety, including accident management strategies, the following issues have been investigated in the SARA project: (1) the energy deposition in the fuel during super-prompt power burst; (2) the quasi steady-state reactor power following the initial power burst; and (3) containment response to elevated quasi steady-state reactor power. The approach was to use three computer codes and to further develop and adapt them for the task. The codes were SIMULATE-3K, APROS and RECRIT. Recriticality analyses were carried out for a number of selected reflooding transients for the Oskarshamn 3 plant in Sweden with SIMULATE-3K and for the Olkiluoto 1 plant in Finland with all three codes. The core initial and boundary conditions prior to recriticality have been studied with the severe accident codes SCDAP/RELAP5, MELCOR and MAAP4. The results of the analyses show that all three codes predict recriticality--both super-prompt power bursts and quasi steady-state power generation--for the range of parameters studied, i.e. with core uncovering and heat-up to maximum core temperatures of approximately 1800 K, and water flow rates of 45-2000 kg s{sup -1} injected into the downcomer. Since recriticality takes place in a small fraction of the core, the power densities are high, which results in large energy deposition in the fuel during power burst in some accident scenarios. The highest value, 418 cal g{sup -1}, was obtained with SIMULATE-3K for an Oskarshamn 3 case with reflooding rate of 2000 kg s{sup -1}. In most cases, however, the predicted energy deposition was smaller, below the regulatory limits for fuel failure, but close to or above recently observed thresholds for fragmentation and dispersion of high burn-up fuel. The highest calculated

  3. Severe accident recriticality analyses (SARA)

    International Nuclear Information System (INIS)

    Frid, W.; Hoejerup, F.; Lindholm, I.; Miettinen, J.; Nilsson, L.; Puska, E.K.; Sjoevall, H.

    2001-01-01

    Recriticality in a BWR during reflooding of an overheated partly degraded core, i.e. with relocated control rods, has been studied for a total loss of electric power accident scenario. In order to assess the impact of recriticality on reactor safety, including accident management strategies, the following issues have been investigated in the SARA project: (1) the energy deposition in the fuel during super-prompt power burst; (2) the quasi steady-state reactor power following the initial power burst; and (3) containment response to elevated quasi steady-state reactor power. The approach was to use three computer codes and to further develop and adapt them for the task. The codes were SIMULATE-3K, APROS and RECRIT. Recriticality analyses were carried out for a number of selected reflooding transients for the Oskarshamn 3 plant in Sweden with SIMULATE-3K and for the Olkiluoto 1 plant in Finland with all three codes. The core initial and boundary conditions prior to recriticality have been studied with the severe accident codes SCDAP/RELAP5, MELCOR and MAAP4. The results of the analyses show that all three codes predict recriticality--both super-prompt power bursts and quasi steady-state power generation--for the range of parameters studied, i.e. with core uncovering and heat-up to maximum core temperatures of approximately 1800 K, and water flow rates of 45-2000 kg s -1 injected into the downcomer. Since recriticality takes place in a small fraction of the core, the power densities are high, which results in large energy deposition in the fuel during power burst in some accident scenarios. The highest value, 418 cal g -1 , was obtained with SIMULATE-3K for an Oskarshamn 3 case with reflooding rate of 2000 kg s -1 . In most cases, however, the predicted energy deposition was smaller, below the regulatory limits for fuel failure, but close to or above recently observed thresholds for fragmentation and dispersion of high burn-up fuel. The highest calculated quasi steady

  4. Severe Accident Recriticality Analyses (SARA)

    International Nuclear Information System (INIS)

    Frid, W.; Hoejerup, F.; Lindholm, I.; Miettinen, J.; Puska, E.K.; Nilsson, Lars; Sjoevall, H.

    1999-11-01

    Recriticality in a BWR has been studied for a total loss of electric power accident scenario. In a BWR, the B 4 C control rods would melt and relocate from the core before the fuel during core uncovery and heat-up. If electric power returns during this time-window unborated water from ECCS systems will start to reflood the partly control rod free core. Recriticality might take place for which the only mitigating mechanisms are the Doppler effect and void formation. In order to assess the impact of recriticality on reactor safety, including accident management measures, the following issues have been investigated in the SARA project: 1. the energy deposition in the fuel during super-prompt power burst, 2. the quasi steady-state reactor power following the initial power burst and 3. containment response to elevated quasi steady-state reactor power. The approach was to use three computer codes and to further develop and adapt them for the task. The codes were SIMULATE-3K, APROS and RECRIT. Recriticality analyses were carried out for a number of selected reflooding transients for the Oskarshamn 3 plant in Sweden with SIMULATE-3K and for the Olkiluoto 1 plant in Finland with all three codes. The core state initial and boundary conditions prior to recriticality have been studied with the severe accident codes SCDAP/RELAP5, MELCOR and MAAP4. The results of the analyses show that all three codes predict recriticality - both superprompt power bursts and quasi steady-state power generation - for the studied range of parameters, i. e. with core uncovery and heat-up to maximum core temperatures around 1800 K and water flow rates of 45 kg/s to 2000 kg/s injected into the downcomer. Since the recriticality takes place in a small fraction of the core the power densities are high which results in large energy deposition in the fuel during power burst in some accident scenarios. The highest value, 418 cal/g, was obtained with SIMULATE-3K for an Oskarshamn 3 case with reflooding

  5. The SARA REU Site Program

    Science.gov (United States)

    Wood, M. A.; Oswalt, T. D.; SARA Collaboration

    2000-12-01

    We present an overview of the Research Experiences for Undergraduates (REU) Site Program hosted by the Southeastern Association for Research in Astronomy (SARA) for the past 6 years. SARA is a consortium of the six universities: Florida Institute of Technology, East Tennessee State University, Florida International University, The University of Georgia, Valdosta State University, and Clemson University. We host 10-11 student interns per year out of an application pool of ~150-200. Recruiting flyers are sent to the ~3400 undergraduate institutions in the United States, and we use a web-based application form and review process. We are a distributed REU Site, but come together for group meetings at the beginning and end of the summer program and stay in contact in between using email list manager software. Interns complete a research project working one-on-one with a faculty mentor, and each intern travels to observe at the SARA Observatory at Kitt Peak National Observatory. Interns give both oral and display presentations of their results at the final group meeting. In addition, all interns write a paper for publication in the IAPPP Communications, an international amateur-professional journal, and several present at professional meetings and in refereed publications. We include in the group meetings a ``how-to'' session on giving talks and posters, an Ethics Session, and a session on Women in Astronomy. This work was supported by the NSF Research Experiences for Undergraduates (REU) Site Program through grant AST 96169939 to The Florida Institute of Technology.

  6. Large scale reflood test

    International Nuclear Information System (INIS)

    Hirano, Kemmei; Murao, Yoshio

    1980-01-01

    The large-scale reflood test with a view to ensuring the safety of light water reactors was started in fiscal 1976 based on the special account act for power source development promotion measures by the entrustment from the Science and Technology Agency. Thereafter, to establish the safety of PWRs in loss-of-coolant accidents by joint international efforts, the Japan-West Germany-U.S. research cooperation program was started in April, 1980. Thereupon, the large-scale reflood test is now included in this program. It consists of two tests using a cylindrical core testing apparatus for examining the overall system effect and a plate core testing apparatus for testing individual effects. Each apparatus is composed of the mock-ups of pressure vessel, primary loop, containment vessel and ECCS. The testing method, the test results and the research cooperation program are described. (J.P.N.)

  7. News developments at Sara

    International Nuclear Information System (INIS)

    Belmont, J.L.; Fruneau, M.; Martin, P.

    1989-05-01

    SARA was one of the first cyclotrons to operate with an ECR ion source. Experience since 1983 showed it would be useful to have two sources situated outside the cyclotron vault to manage continuous operation of the accelerator and development of new ions. A 18 m long injection line for FERROMAFIOS and MINIMAFIOS has been constructed. One of its principal features is a 11 m long electrostatic guide with periodic focusing. Transmission ratios from the source to the internal beam are close to 30%. Experiences involving time of flight measurements require short beam bunches; in order to reduce their duration, a phase selecting system will be installed in the centre of the injector of SARA. A RF voltage at four times the frequency of the dees will vertically deflect early orbits while particles close to the central phase will cross the deflector at zero voltage and will undergo normal acceleration

  8. Safety Research Program for Light Water Reactors. Technical report 2: BMFT support project RS 0036 B. Reflooding experiments with regard to primary circuits (PKL) instrumentation of experimental setup

    International Nuclear Information System (INIS)

    Schweickert, H.; Mandl, R.

    The reflooding of the hot core of a PWR will be investigated in a model of the complete primary system. The demands that the instrumentation must meet as well as a description of the measurement methods used in the circuit are described. Data on the efficiency of the instruments, error estimates and constructive solutions to design problems are also given

  9. Safety Technology Research Program in the field of pressurized water reactors. 1. Technical report on advancement project RS 36/2. Emergency cooling program service life experiments: reflooding experiments involving the primary loop systems

    International Nuclear Information System (INIS)

    Schweickert, H.; Kremin, H.; Mandl, R.; Riedle, V.; Ruthrof, K.; Sarkar, J.; Schmidt, H.

    The reflooding of the hot reactor core is to be examined for a pressurized water reactor (PWR), using a model of the entire primary loop system. The scale of the model is to be 1:340 in cross-section, with the heights represented full-scale. In addition to the goals of the project, a description of the test facility, including data collection and control equipment is presented. The instrumentation, the planned test program and the test procedure are briefly set forth

  10. Severe accident recriticality analyses (SARA)

    DEFF Research Database (Denmark)

    Frid, W.; Højerup, C.F.; Lindholm, I.

    2001-01-01

    with all three codes. The core initial and boundary conditions prior to recriticality have been studied with the severe accident codes SCDAP/RELAP5, MELCOR and MAAP4. The results of the analyses show that all three codes predict recriticality-both super-prompt power bursts and quasi steady-state power......Recriticality in a BWR during reflooding of an overheated partly degraded core, i.e. with relocated control rods, has been studied for a total loss of electric power accident scenario. In order to assess the impact of recriticality on reactor safety, including accident management strategies......, which results in large energy deposition in the fuel during power burst in some accident scenarios. The highest value, 418 cal g(-1), was obtained with SIMULATE-3K for an Oskarshamn 3 case with reflooding rate of 2000 kg s(-1). In most cases, however, the predicted energy deposition was smaller, below...

  11. Numerical modelling of reflood processes

    International Nuclear Information System (INIS)

    Glynn, D.R.; Rhodes, N.; Tatchell, D.G.

    1983-01-01

    The use of a detailed computer model to investigate the effects of grid size and the choice of wall-to-fluid heat-transfer correlations on the predictions obtained for reflooding of a vertical heated channel is described. The model employs equations for the momentum and enthalpy of vapour and liquid and hence accounts for both thermal non-equilibrium and slip between the phases. Empirical correlations are used to calculate interphase and wall-to-fluid friction and heat-transfer as functions of flow regime and local conditions. The empirical formulae have remained fixed with the exception of the wall-to-fluid heat-transfer correlations. These have been varied according to the practices adopted in other computer codes used to model reflood, namely REFLUX, RELAP and TRAC. Calculations have been performed to predict the CSNI standard problem number 7, and the results are compared with experiment. It is shown that the results are substantially grid-independent, and that the choice of correlation has a significant influence on the general flow behaviour, the rate of quenching and on the maximum cladding temperature predicted by the model. It is concluded that good predictions of reflooding rates can be obtained with particular correlation sets. (author)

  12. Study on thermocouple attachment in reflood experiments

    International Nuclear Information System (INIS)

    Sugimoto, Jun

    1977-03-01

    The method of thermocouple attachment to a heater rods has been studied for surface temperature measurement in reflood experiments. The method used as far in JAERI's reflood experiments had some possibilities of not estimating exactly the quench times. Various attachment method have been tested and some proved to be effective in the respect. (auth.)

  13. 2012 SARA Students Technical Report

    International Nuclear Information System (INIS)

    Briccetti, Angelo; Lorei, Nathan; Yonkings, David; Lorio, David; Goorley, John T.; Sood, Avneet

    2012-01-01

    The Service Academy Research Associates (SARA) program provides an opportunity for Midshipmen and Cadets from US Service Academies to participate in research at Los Alamos National Laboratory (LANL), Lawrence Livermore National Laboratory (LLNL), and Sandia National Laboratory for several weeks during the summer as part of their summer training assignments. During the summer of 2012, three Midshipmen were assigned to work with the XCP Division at LANL for approximately 5-6 weeks. As one of the nation's top national security science laboratories, LANL stretches across 36 square miles, has over 2,100 facilities, and employs over 9,000 individuals including a significant number of students and postdocs. LANL's mission is to 'apply science and technology to: ensure the safety, security, and reliability of the US nuclear deterrent, reduce global threats, and solve other emerging national security challenges.' While LANL officially operates under the US Department of Energy (DoE), fulfilling this mission requires mutual cooperation with the US Department of Defense (DoD) as well. LANL's high concentration of knowledge and experience provides interns a chance to perform research in many disciplines, and its connection with the DoD in both operation and personnel gives SARA students insight to career possibilities both during and after military service. SARA students have plenty of opportunity to enjoy hiking, camping, the Los Alamos YMCA, and many other outdoor activities in New Mexico while staying at the Buffalo Thunder Resort, located 20 miles east of the lab. XCP Division is the Computational Physics division of LANL's Weapons Department. Working with XCP Division requires individuals to be Q cleared by the DoE. This means it is significantly more convenient for SARA students to be assigned to XCP Division than their civilian counterparts as the DoD CNWDI clearance held by SARA students is easily transferred to the lab prior to the students arriving at the start of

  14. 2012 SARA Students Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Briccetti, Angelo [Los Alamos National Laboratory; Lorei, Nathan [Los Alamos National Laboratory; Yonkings, David [Los Alamos National Laboratory; Lorio, David [Los Alamos National Laboratory; Goorley, John T. [Los Alamos National Laboratory; Sood, Avneet [Los Alamos National Laboratory

    2012-07-30

    The Service Academy Research Associates (SARA) program provides an opportunity for Midshipmen and Cadets from US Service Academies to participate in research at Los Alamos National Laboratory (LANL), Lawrence Livermore National Laboratory (LLNL), and Sandia National Laboratory for several weeks during the summer as part of their summer training assignments. During the summer of 2012, three Midshipmen were assigned to work with the XCP Division at LANL for approximately 5-6 weeks. As one of the nation's top national security science laboratories, LANL stretches across 36 square miles, has over 2,100 facilities, and employs over 9,000 individuals including a significant number of students and postdocs. LANL's mission is to 'apply science and technology to: ensure the safety, security, and reliability of the US nuclear deterrent, reduce global threats, and solve other emerging national security challenges.' While LANL officially operates under the US Department of Energy (DoE), fulfilling this mission requires mutual cooperation with the US Department of Defense (DoD) as well. LANL's high concentration of knowledge and experience provides interns a chance to perform research in many disciplines, and its connection with the DoD in both operation and personnel gives SARA students insight to career possibilities both during and after military service. SARA students have plenty of opportunity to enjoy hiking, camping, the Los Alamos YMCA, and many other outdoor activities in New Mexico while staying at the Buffalo Thunder Resort, located 20 miles east of the lab. XCP Division is the Computational Physics division of LANL's Weapons Department. Working with XCP Division requires individuals to be Q cleared by the DoE. This means it is significantly more convenient for SARA students to be assigned to XCP Division than their civilian counterparts as the DoD CNWDI clearance held by SARA students is easily transferred to the lab prior to the

  15. Droplet generation during core reflood

    International Nuclear Information System (INIS)

    Kocamustafaogullari, G.; De Jarlais, G.; Ishii, M.

    1983-01-01

    The process of entrainment and disintegration of liquid droplets by a flow of steam has considerable practical importance in calculating the effectivenes of the emergency core cooling system. Liquid entrainment is also important in determination of the critical heat flux point in general. Thus the analysis of the reflooding phase of a LOCA requires detailed knowledge of droplet size. Droplet size is mainly determined by the droplet generation mechanisms involved. To study these mechanisms, data generated in the PWR FLECHT SEASET series of experiments was analyzed. In addition, an experiment was performed in which the hydrodynamics of low quality post-CHF flow (inverted annular flow) were simulated in an adiabatic test section

  16. Report on series 3 reflood experiment

    International Nuclear Information System (INIS)

    Murao, Yoshio; Iguchi, Tadashi; Sudoh, Takashi; Sudo, Yukio; Sugimoto, Jun

    1977-03-01

    Series 3 reflood experiment was carried out from December 1975 to January 1976. The purpose was to confirm temperature response and durability of the improved thermocouple installation and to examine system effect with parameters, flow housing temperature and primary loop flow resistance. The results are : 1) The improved thermocouples installation still has some problems, but is generally satisfactory up to 1000 0 C. 2) The flow housing temperature has large influence on the reflood phenomena, especially oscillation. 3) The primary loop resistance determines the flooding rate, and so influences the reflood phenomena. (auth.)

  17. Sara

    International Nuclear Information System (INIS)

    Aparo, M.; Dionisi, M.; Vicini, C.; Zeppa, P.; Frazzoli, F.V.; Remetti, R.; Portale, C.

    1989-01-01

    Nuclear Material Accountability, supported by Containment and Surveillance measures, is a foundamental means for an effective International Safeguard implemention in nuclear plants. Accountability is based on the verification that difference between a material quantity entering a given material balance and the quantity leaving that area in a given period of time, correspond and the amount of material actually present at the moment of the inspection. In the recent years International Safeguards appealing to the needs of timeliness in detecting diversion and concealing activities, devoted ReD efforts on a new Dynamic Accountability procedures (NRTMA) with particular concern with reprocessing plants. The present paper, which is the result of a research activity carried out in the frame of the Italian Support Programme to IAEA for Safeguards implementation, deals with a feasibility study of a NRTMA system to be applied to the EUREX pilot reprocessing plant. Such a feasibility study was performed by developing a computer program based on simulated plant generated data

  18. Coolability of degraded core under reflooding conditions in Nordic boiling water reactors

    Energy Technology Data Exchange (ETDEWEB)

    Lindholm, I; Pekkarinen, E [VTT Energy, Espoo (Finland); Nilsson, L [Studsvik EcoSafe AB, Nykoeping (Sweden); Sjoevall, H [Teollisuuden Voima Oy, Olkiluoto (Finland)

    1995-09-01

    Present work is part of the first phase of subproject RAK-2.1 of the new Nordic Co-operative Reactor Safety Program, NKS. The first phase comprises reflooding calculations for the boiling water reactors (BWRs) TVO I/II in Finland and Forsmark 3 in Sweden, as a continuation of earlier severe accident analyses which were made in the SIK-2 project. The objective of the core reflooding studies is to evaluate when and how the core is still coolable with water and what are the probable consequences of water cooling. In the following phase of the RAK-2.1 project, recriticality studies will be performed. Conditions for recriticality might occur if control rods have melted away with the fuel rods intact in a shape that critical conditions can be created in reflooding with insufficiently borated water. Core coolability was investigated for two reference plants, TVO I/II and Forsmark 3. The selected accident cases were anticipated station blackout with or without successful depressurization of reactor coolant system (RCS). The effects of the recovery of emergency core cooling (ECC) were studied by varying the starting time of core reflooding. The start of ECC systems were assigned to reaching a maximum cladding temperature: 1400 K, 1600 K, 1800 K and 2000 K in the core. Cases with coolant injection through the downcomer were studied for TVO I/II and both downcomer injection and core top spray were investigated for Forsmark 3. Calculations with three different computer codes: MAAP 4, MELCOR 1.8.3 and SCDA/RELAP5/MOD 3.1 for the basis for the presented reflooding studies. Presently, and experimental programme on core reflooding phenomena has been started in Kernforschungszentrum Karlsruhe in QUENCH test facility. (EG) 17 refs.

  19. Data report on reflood experiment, 8

    International Nuclear Information System (INIS)

    Sugimoto, Jun; Murao, Yoshio; Iguchi, Tadashi; Sudoh, Takashi; Sudo, Yukio

    1979-03-01

    Heat transfer behavior in series 6 reflood experiment is reported including test conditions and data processing. To develop an analysis code, the purpose of the series 6 reflood experiment was as follows: (1) Overall reflood phenomena in a 4 x 4 array indirectly heated heater rod bundle. Sheathed thermocouples were completely embedded in the heater rod cladding. (2) Quench characteristics at low flooding rate. (3) Differential pressure response in the core. (4) Heat transfer coefficients downstream of the quench point. (5) Water effluence behavior at outlet of the core. (6) Effect of non-heated rod in the core. (7) System response under intermittent-flow-rate core forced injection. The tests were in three groups according to the water injection methods to the core: (1) Constant-flow-rate core forced injection, (2) intermittent-flow-rate core forced injection, and (3) system effect test. (author)

  20. Report on series 2B reflood experiment

    International Nuclear Information System (INIS)

    Murao, Yoshio; Iguchi, Tadashi; Sudoh, Takashi; Sudo, Yukio; Sugimoto, Jun

    1976-12-01

    Series 2B reflood experiment was carried out from April to May 1975, as follows: 1) injection of coolant water from the downcomer at a constant head into the test section having a flow resistance simulator of the primary loop, 2) under an atmospheric pressure, 3) in constant power density, 4) with heater rod temperature up to 600 0 C. The objectives are to examine quantitatively system effect and to check performance of the reflood test rig. The effect of the coolant injection mode, relation between oscillatory phenomena and core thermo-hydrodynamics, and technological problems of the test rig were observed. (auth.)

  1. UC-B reflood experimental plan

    International Nuclear Information System (INIS)

    Yu, K.P.; Abdollahian, D.; Peake, W.T.; Elias, E.; Yadigaroglu, G.; Greif, R.

    1977-04-01

    The EPRI sponsored single tube reflooding heat transfer facility is described. The facility is located at the University of California, Berkeley. The physical systems which constitute the facility as well as the objectives and background of the program are described. The steam-water separator is described in detail Finally, the operating procedure and the test apparatus performance are discussed

  2. Interpreting the SARA and RCRA training requirements

    International Nuclear Information System (INIS)

    Moreland, W.M.; Wells, S.M.

    1987-01-01

    The Resource Conservation and Recovery Act (RCRA) and the Superfund Amendments and Reauthorization Act (SARA) promulgated by the EPA (RCRA) and the OSHA (SARA) require hazardous materials training for all individuals working with hazardous materials. Facilities that are involved in the generation, storage, treatment, transportation, or disposal/removal of hazardous materials/waste must comply with all relevant training regulations. Using the guidelines contained in the RCRA and SARA regulations, decisions must be made to determine: the type of regulatory requirement based on facility function (i.e., whether the facility is a RCRA or CERCLA facility). The type of training required for specific categories of workers (e.g. managers, supervisors, or general site workers). The level of training needed for each category of worker. This presentation outlines how the Environmental Compliance and Health Protection Technical Resources and Training Group, working with waste operations personnel, establishes specific training requirements

  3. The top-down reflooding model in the Cathare code

    International Nuclear Information System (INIS)

    Bartak, J.; Bestion, D.; Haapalehto, T.

    1993-01-01

    A top-down reflooding model was developed for the French best-estimate thermalhydraulic code CATHARE. The paper presents the current state of development of this model. Based on a literature survey and on compatibility considerations with respect to the existing CATHARE bottom reflooding package, a falling film top-down reflooding model was developed and implemented into CATHARE version 1.3E. Following a brief review of previous work, the paper describes the most important features of the model. The model was validated with the WINFRITH single tube top-down reflooding experiment and with the REWET - II simultaneous bottom and top-down reflooding experiment in rod bundle geometry. The results demonstrate the ability of the new package to describe the falling film rewetting phenomena and the main parametric trends both in a simple analytical experimental setup and in a much more complex rod bundle reflooding experiment. (authors). 9 figs., 28 refs

  4. Data report on series 6 reflood experiment

    International Nuclear Information System (INIS)

    Iguchi, Tadashi; Murao, Yoshio; Sudoh, Takashi; Sudo, Yukio; Sugimoto, Jun

    1979-03-01

    Series 6 reflood experiments (experiment with 4 x 4 indirectly heated rods) were carried out from March to June 1978. The purpose of the experiments was: 1) to observe overall reflood phenomena in a 4 x 4 indirectly heated heater rod bundle with thermocouples inbedded completely in the cladding, 2) to examine the quench characteristics at low flooding rate, 3) to measure steady-state differential pressures in the core, 4) to investigate the heat transfer coefficients before quenching, 5) to investigate the water effluence behavior at outlet of the core, 6) to investigate the effect of a non-heated rod, and 7) to examine the response characteristics of the system at forced oscillating flooding rate. Described are the experimental conditions and the results (cladding temperatures, pressure differences and flow rates) in the constant flooding rate experiments in series 6 experiment. (author)

  5. Report on series 2A reflood experiment

    International Nuclear Information System (INIS)

    Murao, Yoshio; Iguchi, Tadashi; Sudoh, Takashi; Sudo, Yukio; Sugimoto, Jun

    1976-11-01

    Series 2A reflood experiment was carried out from February to April 1975 to obtain thermo-hydrodynamic data during reflood phase of a typical PWR. The main test conditions are as follows: - direct water injection into the simulated core at constant flow rate - operation under an atmospheric pressure, and - temperature of heater rods up to 600 0 C. Study of the data showed that several heat transfer phases exist in the core, i.e. adiabatic, droplet-dispersed vapor flow, film boiling, quench, and nucleate boiling phase. The relation between heat transfer phases and heat transfer coefficients was discussed qualitatively, and the following phenomena were found out: Pressure oscillation exists in the core, and it has large influence upon heat transfer coeficient characteristic as well as heater rod surface temperature response, and the inlet water velocity influences the carry over fraction. (auth.)

  6. Reflood modeling under oscillatory flow conditions with Cathare

    Energy Technology Data Exchange (ETDEWEB)

    Kelly, J M; Bartak, J; Janicot, A

    1994-12-31

    The problems and the current status in oscillatory reflood modelling with the CATHARE code are presented. The physical models used in CATHARE for reflood modelling predicted globally very well the forced reflood experiments. Significant drawbacks existed in predicting experiments with oscillatory flow (both forced and gravity driven). First, the more simple case of forced flow oscillations was analyzed. Modelling improvements within the reflooding package resolved the problem of quench front blockages and unphysical oscillations. Good agreements with experiment for the ERSEC forced oscillations reflood tests is now obtained. For gravity driven reflood, CATHARE predicted sustained flow oscillations during 100-150 s after the start of the reflood, whereas in the experiment flow oscillations were observed only during 25-30 s. Possible areas of modeling improvements are identified and several new correlations are suggested. The first test calculations of the BETHSY test 6.7A4 have shown that the oscillations are mostly sensitive to heat flux modeling downstream of the quench front. A much better agreement between CATHARE results and the experiment was obtained. However, further effort is necessary to obtain globally satisfactory predictions of gravity driven system reflood tests. (authors) 6 figs., 35 refs.

  7. Reflood modeling under oscillatory flow conditions with Cathare

    International Nuclear Information System (INIS)

    Kelly, J.M.; Bartak, J.; Janicot, A.

    1993-01-01

    The problems and the current status in oscillatory reflood modelling with the CATHARE code are presented. The physical models used in CATHARE for reflood modelling predicted globally very well the forced reflood experiments. Significant drawbacks existed in predicting experiments with oscillatory flow (both forced and gravity driven). First, the more simple case of forced flow oscillations was analyzed. Modelling improvements within the reflooding package resolved the problem of quench front blockages and unphysical oscillations. Good agreements with experiment for the ERSEC forced oscillations reflood tests is now obtained. For gravity driven reflood, CATHARE predicted sustained flow oscillations during 100-150 s after the start of the reflood, whereas in the experiment flow oscillations were observed only during 25-30 s. Possible areas of modeling improvements are identified and several new correlations are suggested. The first test calculations of the BETHSY test 6.7A4 have shown that the oscillations are mostly sensitive to heat flux modeling downstream of the quench front. A much better agreement between CATHARE results and the experiment was obtained. However, further effort is necessary to obtain globally satisfactory predictions of gravity driven system reflood tests. (authors) 6 figs., 35 refs

  8. System Analysis and Risk Assessment (SARA) system

    International Nuclear Information System (INIS)

    Krantz, E.A.; Russell, K.D.; Stewart, H.D.; Van Siclen, V.S.

    1986-01-01

    Utilization of Probabilistic Risk Assessment (PRA) related information in the day-to-day operation of plant systems has, in the past, been impracticable due to the size of the computers needed to run PRA codes. This paper discusses a microcomputer-based database system which can greatly enhance the capability of operators or regulators to incorporate PRA methodologies into their routine decision making. This system is called the System Analysis and Risk Assessment (SARA) system. SARA was developed by EG and G Idaho, Inc. at the Idaho National Engineering Laboratory to facilitate the study of frequency and consequence analyses of accident sequences from a large number of light water reactors (LWRs) in this country. This information is being amassed by several studies sponsored by the United States Nuclear Regulatory Commission (USNRC). To meet the need of portability and accessibility, and to perform the variety of calculations necessary, it was felt that a microcomputer-based system would be most suitable

  9. Report on series 4 reflood experiment

    International Nuclear Information System (INIS)

    Murao, Yoshio; Iguchi, Tadashi; Sudoh, Takashi; Sudo, Yukio; Sugimoto, Jun

    1977-03-01

    Series 4 reflood experiment was carried out from June to July 1976. The purpose was to examine system-pressure effect and system effect with heater rods having about the same heat capacity as the real ones and flow resistance of the primary loop. The results are: 1) The core flood velocity increases and the quench time decreases with system pressure. 2) The relation between core differential pressure (accumulation head of the core) and core power density, which indicates coolability of the core, is obtainable in map with the system pressure as a parameter. 3) The steady-state thermal condition occurs in the test section with constant power density. (auth.)

  10. Influential input parameters for reflood model of MARS code

    Energy Technology Data Exchange (ETDEWEB)

    Oh, Deog Yeon; Bang, Young Seok [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2012-10-15

    Best Estimate (BE) calculation has been more broadly used in nuclear industries and regulations to reduce the significant conservatism for evaluating Loss of Coolant Accident (LOCA). Reflood model has been identified as one of the problems in BE calculation. The objective of the Post BEMUSE Reflood Model Input Uncertainty Methods (PREMIUM) program of OECD/NEA is to make progress the issue of the quantification of the uncertainty of the physical models in system thermal hydraulic codes, by considering an experimental result especially for reflood. It is important to establish a methodology to identify and select the parameters influential to the response of reflood phenomena following Large Break LOCA. For this aspect, a reference calculation and sensitivity analysis to select the dominant influential parameters for FEBA experiment are performed.

  11. Oxidation during reflood of reactor core with melting cladding

    Energy Technology Data Exchange (ETDEWEB)

    Siefken, L.J.; Allison, C.M.; Davis, K.L. [and others

    1995-09-01

    Models were recently developed and incorporated into the SCDAP/RELAP5 code for calculating the oxidation of fuel rods during cladding meltdown and reflood. Experiments have shown that a period of intense oxidation may occur when a hot partially oxidized reactor core is reflooded. This paper offers an explanation of the cladding meltdown and oxidation processes that cause this intense period of oxidation. Models for the cladding meltdown and oxidation processes are developed. The models are assessed by simulating a severe fuel damage experiment that involved reflood. The models for cladding meltdown and oxidation were found to improve calculation of the temperature and oxidation of fuel rods during the period in which hot fuel rods are reflooded.

  12. Experimental study on reflooding in advanced tight lattice PWR

    International Nuclear Information System (INIS)

    Hori, K.; Kodama, J.; Teramae, T.

    2000-01-01

    This paper is related to the experimental study on the feasibility of core cooling by re-flooding in a large break loss of coolant accident (LOCA) for the advanced tight lattice pressurized water reactor (PWR). The tight lattice core design should be adopted to improve the conversion ratio. Major one of the key questions of such tight lattice core is the cooling capability under the re-flood condition in a large break LOCA. Forced feed bottom re-flooding experiments have been performed by use of a 4x4 triangular array rod bundle. The rod gap is 0.5 mm, 1.0 mm, or 1.5 mm. The measured peak temperature is below around 1273 K even in case of 1.0/0.5 mm rod gap. And, the evaluation based on the experimental results of rod temperatures and core pressure drop also shows that the core cooling under re-flooding condition is feasible. (author)

  13. Study on thermal-hydraulics during a PWR reflood phase

    Energy Technology Data Exchange (ETDEWEB)

    Iguchi, Tadashi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1998-10-01

    In-core thermal-hydraulics during a PWR reflood phase following a large-break LOCA are quite unique in comparison with two-phase flow which has been studied widely in previous researches, because the geometry of the flow path is complicated (bundle geometry) and water is at extremely low superficial velocity and almost under stagnant condition. Hence, some phenomena realized during a PWR reflood phase are not understood enough and appropriate analytical models have not been developed, although they are important in a viewpoint of reactor safety evaluation. Therefore, author investigated some phenomena specified as important issues for quantitative prediction, i.e. (1) void fraction in a bundle during a PWR reflood phase, (2) effect of radial core power profile on reflood behavior, (3) effect of combined emergency core coolant injection on reflood behavior, and (4) the core separation into two thermal-hydraulically different regions and the in-core flow circulation behavior observed during a combined injection PWR reflood phase. Further, author made analytical models for these specified issues, and succeeded to predict reflood behaviors at representative types of PWRs, i.e.cold leg injection PWRs and Combined injection PWRs, in good accuracy. Above results were incorporated into REFLA code which is developed at JAERI, and they improved accuracy in prediction and enlarged applicability of the code. In the present study, models were intended to be utilized in a practical use, and hence these models are simplified ones. However, physical understanding on the specified issues in the present study is basic and principal for reflood behavior, and then it is considered to be used in a future advanced code development and improvement. (author). 110 refs.

  14. BWR Refill-Reflood Program. Final report

    International Nuclear Information System (INIS)

    Myers, L.L.

    1983-09-01

    The BWR Refill-Reflood Program is part of the continuing Loss of Coolant Accident (LOCA) research in the United States which is jointly sponsored by the Nuclear Regulatory Commission, the Electric Power Research Institute, and the General Electric Company. The current program expanded the focus of this research to include full scale experimental evaluations of multidimensional and multichannel effects during system refill. The program has also made major contributions to the BWR version of the Transient Reactor Analysis Code (TRAC) which has been developed cooperatively with the Idaho National Engineering Laboratory (INEL) for application to BWR transients. A summary description of the complete program is provided including the principal findings and main conclusions of the program. The results of the program have shown that multidimensional and parallel channel effects have the potential to significantly improve the system response over that observed in single channel tests

  15. Improvement of MARS code reflood model

    International Nuclear Information System (INIS)

    Hwang, Moonkyu; Chung, Bub-Dong

    2011-01-01

    A specifically designed heat transfer model for the reflood process which normally occurs at low flow and low pressure was originally incorporated in the MARS code. The model is essentially identical to that of the RELAP5/MOD3.3 code. The model, however, is known to have under-estimated the peak cladding temperature (PCT) with earlier turn-over. In this study, the original MARS code reflood model is improved. Based on the extensive sensitivity studies for both hydraulic and wall heat transfer models, it is found that the dispersed flow film boiling (DFFB) wall heat transfer is the most influential process determining the PCT, whereas the interfacial drag model most affects the quenching time through the liquid carryover phenomenon. The model proposed by Bajorek and Young is incorporated for the DFFB wall heat transfer. Both space grid and droplet enhancement models are incorporated. Inverted annular film boiling (IAFB) is modeled by using the original PSI model of the code. The flow transition between the DFFB and IABF, is modeled using the TRACE code interpolation. A gas velocity threshold is also added to limit the top-down quenching effect. Assessment calculations are performed for the original and modified MARS codes for the Flecht-Seaset test and RBHT test. Improvements are observed in terms of the PCT and quenching time predictions in the Flecht-Seaset assessment. In case of the RBHT assessment, the improvement over the original MARS code is found marginal. A space grid effect, however, is clearly seen from the modified version of the MARS code. (author)

  16. RELAP4/MOD6 reflood heat transfer and data comparison

    International Nuclear Information System (INIS)

    Nelson, R.A.; Sullivan, L.H.

    1981-01-01

    This discussion of RELAP4/MOD6 will be limited to the reflood heat transfer models and evaluation of these models by comparison of calculation with results from three reflood experiments. The discussion of the model includes the heat transfer surface concept, the heat transfer correlations, the superheat model and the entrainment model which presents both the two-phase heat transfer and hydraulic models. In the discussion of the reflood heat transfer, the mathematical concept of a multidimensional surface is used to represent the heat flux of a given heat transfer correlation or correlations dependent upon such variables as quality, wall superheat and flux. This concept has been used to investigate the characteristics of the correlations, which are discusssed in detail, and the way they are applied to the two-phase mixture. Of primary importance in the reflood core heat transfer is the consideration of thermal nonequilibrium between the phases and the liquid entrainment, and its distribution up the core. Results obtained to date show the heat transfer and hydraulics to be closely coupled. Comparison of the RELAP4/MOD6 reflood calculations with the data from the forced feed FLECHT and gravity feed FLECHT-SET and Semiscale reflood experiments indicates that the heat transfer and hydraulic models are operational and yield good results

  17. The SARA Consortium: Providing Undergraduate Access to a 0.9-m Telescope at Kitt Peak National Observatory

    Science.gov (United States)

    Wood, M. A.

    2003-12-01

    The Southeastern Research for Astronomy (SARA) operates a 0.9-m telescope at Kitt Peak National Observatory (KPNO). The member institutions are Florida Institute of Technology, East Tennessee State University, Florida International University, The University of Georgia at Athens, Valdosta State University, and Clemson University. The NSF awarded the KPNO #1 0.9-m telescope to the SARA Consortium in 1990. We built a new facility and began routine on-site observations in 1995. We began routine remote observations in 1999 using VNC to export the telescope and CCD control screens, and a web-cam in the dome to provide critical visual feedback on the status of the telescope and dome. The mission of the SARA Consortium is to foster astronomical research and education in the Southeastern United States. Although only two of the member institutions have no graduate programs, all six have a strong emphasis on undergraduate research and education. By pooling our resources, we are able to operate a research-grade facility that none of the individual schools could manage by itself, and in the process we can offer our undergraduate students the opportunity to assist in our research projects as well as to complete their own independent research projects using a facility at a premier site. The SARA Consortium also hosts a NSF REU Summer Intern Program in Astronomy, in which we support 11-12 students that work one-on-one with a SARA faculty mentor. Most of these interns are selected from primarily undergraduate institutions, and have not had significant previous research experience. As part of the program, interns and mentors travel to KPNO for a 4-5 night observing run at the telescope. The SARA NSF REU Program is funded through NSF grant AST-0097616.

  18. EFLOD code for reflood heat transfer

    International Nuclear Information System (INIS)

    Gay, R.R.

    1979-01-01

    A computer code called EFLOD has been developed for simulation of the heat transfer and hydrodynamics of a nuclear power reactor during the reflood phase of a loss-of-coolant accident. EFLOD models the downcomer, lower plenum, core, and upper plenum of a nuclear reactor vessel using seven control volumes assuming either homogeneous or unequal-velocity, unequal-temperature (UVUT) models of two-phase flow, depending on location within the vessel. The moving control volume concept in which a single control volume models the quench region in the core and moves with the core liquid level was developed and implemented in EFLOD so that three control volumes suffice to model the core region. A simplified UVUT model that assumes saturated liquid above the quench front was developed to handle the nonhomogeneous flow situation above the quench region. An explicit finite difference routine is used to model conduction heat transfer in the fuel, gap, and cladding regions of the fuel rod. In simulation of a selected FLECHT-SET experimental run, EFLOD successfully predicted the midplane maximum temperature and turnaround time as well as the time-dependent advance of the core liquid level. However, the rate of advancement of the quench level and the ensuing liquid entrainment were overpredicted during the early part of the transient

  19. Improved guidelines for RELAP4/MOD6 reflood calculations

    International Nuclear Information System (INIS)

    Chen, T.H.; Fletcher, C.D.

    1980-01-01

    Computer simulations were performed for an extensive selection of forced- and gravity-feed reflood experiments. This effort was a portion of the assessment procedure for the RELAP4/MOD6 thermal hydraulic computer code. A common set of guidelines, based on recommendations from the code developers, was used in determining the model and user-selected input options for each calculation. The comparison of code-calculated and experimental data was then used to assess the capability of the RELAP4/MOD6 code to model the reflood phenomena. As a result of the assessment, the guidelines for determining the user-selected input options were improved

  20. Innovative Stormwater Quality Tools by SARA for Holistic Watershed Master Planning

    Science.gov (United States)

    Thomas, S. M.; Su, Y. C.; Hummel, P. R.

    2016-12-01

    Stormwater management strategies such as Best Management Practices (BMP) and Low-Impact Development (LID) have increasingly gained attention in urban runoff control, becoming vital to holistic watershed master plans. These strategies can help address existing water quality impairments and support regulatory compliance, as well as guide planning and management of future development when substantial population growth and urbanization is projected to occur. However, past efforts have been limited to qualitative planning due to the lack of suitable tools to conduct quantitative assessment. The San Antonio River Authority (SARA), with the assistance of Lockwood, Andrews & Newnam, Inc. (LAN) and AQUA TERRA Consultants (a division of RESPEC), developed comprehensive hydrodynamic and water quality models using the Hydrological Simulation Program-FORTRAN (HSPF) for several urban watersheds in the San Antonio River Basin. These models enabled watershed management to look at water quality issues on a more refined temporal and spatial scale than the limited monitoring data. They also provided a means to locate and quantify potential water quality impairments and evaluate the effects of mitigation measures. To support the models, a suite of software tools were developed. including: 1) SARA Timeseries Utility Tool for managing and processing of large model timeseries files, 2) SARA Load Reduction Tool to determine load reductions needed to achieve screening levels for each modeled constituent on a sub-basin basis, and 3) SARA Enhanced BMP Tool to determine the optimal combination of BMP types and units needed to achieve the required load reductions. Using these SARA models and tools, water quality agencies and stormwater professionals can determine the optimal combinations of BMP/LID to accomplish their goals and save substantial stormwater infrastructure and management costs. The tools can also help regulators and permittees evaluate the feasibility of achieving compliance

  1. Reflooding phase of the LOCA - state of the art I. Heat transfer and fluid flow during reflooding

    International Nuclear Information System (INIS)

    Yadigaroglu, G.

    1977-01-01

    Complex heat transfer processes take place during the reflooding phase of the Loss-of-Coolant Accident in Light-Water Reactors. Reflooding experiments conducted with simple single-channel geometries (round tubes and annuli) and with rod bundles are reviewed. The experimental findings and various parametric trends are critically discussed, explained, and summarized. Analytical methods that are in use in safety analysis and features of advanced models that have been proposed are outlined. These advanced models attempt to solve the conservation equations in the core channels in order to find the local coolant conditions. The values of the heat transfer coefficients are related to local parameters to arrive at cladding temperature predictions

  2. Social humanoid robot SARA: development of the wrist mechanism

    Science.gov (United States)

    Penčić, M.; Rackov, M.; Čavić, M.; Kiss, I.; Cioată, V. G.

    2018-01-01

    This paper presents the development of a wrist mechanism for humanoid robots. The research was conducted within the project which develops social humanoid robot Sara - a mobile anthropomorphic platform for researching the social behaviour of robots. There are two basic ways for the realization of humanoid wrist. The first one is based on biologically inspired structures that have variable stiffness, and the second one on low backlash mechanisms that have high stiffness. Our solution is low backlash differential mechanism that requires small actuators. Based on the kinematic-dynamic requirements, a dynamic model of the robot wrist is formed. A dynamic simulation for several hand positions was performed and the driving torques of the wrist mechanism were determined. The realized wrist has 2 DOFs and enables movements in the direction of flexion/extension 115°, ulnar/radial deviation ±45° and the combination of these two movements. It consists of a differential mechanism with three spur bevel gears, two of which are driving and identical, while the last one is the driven gear to which the robot hand is attached. Power transmission and motion from the actuator to the input links of the differential mechanism is realized with two parallel placed identical gear mechanisms. The wrist mechanism has high carrying capacity and reliability, high efficiency, a compact design and low backlash that provides high positioning accuracy and repeatability of movements, which is essential for motion control.

  3. Multi-dimensional reflooding experiments: the PEARL program

    International Nuclear Information System (INIS)

    Stenne, N.; Pradier, M.; Olivieri, J.; Eymery, S.; Fichot, F.; March, P.; Fleurot, J.

    2011-01-01

    PEARL is an experimental program to study heat transfer and flow regime during the reflooding of a severely damaged PWR core where a large part of the core has collapsed and formed a debris bed. PEARL device will consist in a water-steam loop where the key component is an autoclave capable of housing a test section containing the particle bed and its instrumentation made of thermocouples, pressure sensors and flow rate meters. An electromagnetic induction heating system will generate a predefined specific power in the debris bed and maintains the power during the water reflooding phase. A preliminary experimental investigation has been launched with the setting of the PRELUDE facility, which is one-dimensional. The main aim was to test the particle bed heating system and instrumentation during the reflooding phase. PRELUDE results obtained so far show that the chosen technology is able to deposit a sufficient power density during the reflooding phase. Moreover a temperature of 1000 Celsius degrees for the debris bed is reached accurately with the induction system

  4. The relationship between SARA fractions and crude oil stability

    Directory of Open Access Journals (Sweden)

    Siavash Ashoori

    2017-03-01

    Full Text Available Asphaltene precipitation and deposition are drastic issues in the petroleum industry. Monitoring the asphaltene stability in crude oil is still a serious problem and has been subject of many studies. To investigate crude oil stability by saturate, aromatic, resin and asphaltene (SARA analysis seven types of crudes with different components were used. The applied methods for SARA quantification are IP-143 and ASTM D893-69 and the colloidal instability index (CII is computed from the SARA values as well. In comparison between CII results, the values of oil compositions demonstrated that the stability of asphaltenes in crude oils is a phenomenon that is related to all these components and it cannot be associated only with one of them, individually.

  5. Layering of life (Sara novel of Peter Sarić

    Directory of Open Access Journals (Sweden)

    Kostić Dragomir J.

    2015-01-01

    Full Text Available Novel Sara of Petar Sarić consists of two parts; in it are processed or present two wars, two major wars in the region of Montenegro and Herzegovina, the First and Second World War. However, it is more novel about divisions within the family and the man himself, (and infamous assault of godfather Luka on Sarah also and his murder are in that function, in the first part; and on the divisions among the people, in general, in the second part of the novel. The second part is, in fact, the image layering of life, not a symbolic one, full of hope, faith, reliance, rather than a concrete, real life, that life which is transformed into a fear of life. Separate, poetical, part of the novel, is his main character, Sara. It is no coincidence that her name novel entitled. Because she is one of most beautiful characters in the newer Serbian prose. Speech about the Sara precedes speech about her book. The book is Sara, Sara's book! Possession of book is her main feature of the exterior. Sara comes out from the Book and disappears in the book. Self contained and independent, therefore doomed to conflict with the environment. Loyal to husband and family, loyal to the truth and for justice, she ,,not hurt anything and anyone, no one is standing in the way, to anyone not wroth, nor has anyone looked wrong.' At the same time, the strange beauty, beauty that could not fit into some sort of scheme, one particular image or idea of beauty that again and again renewed, changed, remaining distant, and unmet. Strange goodness, marvelous beauty, she suffered unusual way; her life was transformed into continuous abstinence, repression, in anxiety and fear. In a word: in martirizam! Finally, in order to safe­guard children, sacrificed herself. Novel is a strong critique of society which is not able to recognize the beauty / goodness!.

  6. LOFT reflood as a function of accumulator initial gas volume

    International Nuclear Information System (INIS)

    Rhodes, H.F.

    1978-01-01

    The effect of the initial gas volume in the LOFT accumulators on the time to start of core reflood, after a LOCA, has been studied. The bases of the calculations are the data used and results presented in the Safety Analysis Report, Rev.1, August 1977, and the data in the RELAP and TOODEE2 program input and output listings. The results of this study show that an initial nitrogen volume of 12 cu ft, or more (at 600 psig initial pressure), would cause start of core reflood in time to prevent the cladding temperature from reaching 2200 0 F. The 12 cu ft initial volume will expand from 600 psig, initial pressure, to about 10 psig (containment pressure shortly after start of LOCA is approximately 8 psig) when all ECC liquid has been expelled from the accumulator. This pressure margin is considered too small; the ECC flowrate will be zero before the accumulator is empty

  7. Subacute ruminal acidosis (SARA) in grazing Irish dairy cows.

    Science.gov (United States)

    O'Grady, Luke; Doherty, Michael L; Mulligan, Finbar J

    2008-04-01

    Subacute ruminal acidosis (SARA) is a significant production disease of dairy cattle. Previous concerns have been raised over the occurrence of SARA in pasture-fed dairy cattle and the potential consequences of laminitis and lameness. Highly digestible perennial rye grass contains high concentrations of rapidly fermentable carbohydrate and low concentrations of physical effective fibre that may result in SARA. This study conducted a point prevalence survey of rumen health status in grazing Irish dairy cattle fed predominantly perennial rye grass-based pasture. The survey assessed rumen fluid, animal health status, milk production data and pasture composition. A total of 144 cows between 80 and 150 days in milk were sampled on 12 farms. Eleven percent of cows were classified as affected with SARA (pH 5.8). The study showed that low rumen pH is prevalent in grazing Irish dairy cattle consuming perennial rye grass-based pasture and raises concerns regarding effective pasture utilisation and possible consequences for animal health.

  8. Gene : CBRC-SARA-01-1996 [SEVENS

    Lifescience Database Archive (English)

    Full Text Available CBRC-SARA-01-1996 Novel UN D UNKNOWN NU2C_ANTFO 0.004 26% gb|AAQ05281.1| NADH dehydrogenase subunit B [Metas...equoia glyptostroboides] 0.044 26% MILMLFLLGSSPRSLIHPRAILKTFPIVCCCLYAFCSLTSLILSLAVL

  9. Improvements to the RELAP5/MOD3 reflood model and uncertainty quantification of reflood peak clad temperature

    International Nuclear Information System (INIS)

    Lee, Sang Yong; Chung, Bob Dong; Lee, Young Jin; Park, Chan Eok; Lee, Guy Hyung; Choi, Chul Jin

    1994-06-01

    This research aims to develop reliable, advanced system thermal-hydraulic computer code and to quantify the uncertainties of code to introduce the best estimate methodology of ECCS for LBLOCA. Although the one of best estimate code, RELAP5/MOD3.1 was introduced from USNRC, several deficiencies in its reflood model and some improvements have been made. The improvements consist of modification of reflood wall heat transfer package and adjusting the drop size in dispersed flow regime. The tome smoothing of wall vaporization and level tracking model are also added to eliminate the pressure spike and level oscillation. For the verification of improved model and quantification of associated uncertainty, the FLECHT-SEASET data were used and upper limit of uncertainty at 95% confidence level is evaluated. (Author) 30 refs., 49 figs., 2 tabs

  10. Improvements to the RELAP5/MOD3 reflood model and uncertainty quantification of reflood peak clad temperature

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Sang Yong; Chung, Bob Dong; Lee, Young Jin; Park, Chan Eok; Lee, Guy Hyung; Choi, Chul Jin [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1994-06-01

    This research aims to develop reliable, advanced system thermal-hydraulic computer code and to quantify the uncertainties of code to introduce the best estimate methodology of ECCS for LBLOCA. Although the one of best estimate code, RELAP5/MOD3.1 was introduced from USNRC, several deficiencies in its reflood model and some improvements have been made. The improvements consist of modification of reflood wall heat transfer package and adjusting the drop size in dispersed flow regime. The tome smoothing of wall vaporization and level tracking model are also added to eliminate the pressure spike and level oscillation. For the verification of improved model and quantification of associated uncertainty, the FLECHT-SEASET data were used and upper limit of uncertainty at 95% confidence level is evaluated. (Author) 30 refs., 49 figs., 2 tabs.

  11. Fluiddynamic effects in the fuel element top nozzle area during refilling and reflooding

    International Nuclear Information System (INIS)

    Hawighorst, A.; Kroening, H.; Mewes, D.; Spatz, R.; Mayinger, F.

    1985-01-01

    During the refilling and reflooding phase following a hypothetical loss of coolant accident in lightwater cooled nuclear reactors, there will be countercurrent flow between discharging steam and the feed of emergency core cooling water. It was the objective of this research project to contribute to a better physical understanding of the fluiddynamic processes in the area of the fuel element top nozzle and so to improve emergency core cooling calculations. Therefore, experimental and theoretical investigations about the entrainment and countercurrent behaviour of gas/liquid flows have been implemented within this project. Fluiddynamic processes in the fuel element top nozzle area were simulated during the reflooding and refilling phase. Based on special internals as single and multiple-hole orifices, basic phenomena of fluidynamics were studied first with air-water. Subsequently, investigations of the system steam/water were conducted. The reactor geometry was approximated step by step, until a complete reactor fuel assembly top nozzle was constituted. The system pressure was 4.8 bars (abs), in accordance with the conditions in the reactor pressure vessel at the end of the blowdown phase. The water was initially fed in at saturation temperature, then, as a second step, fed in at subcooled condition relative to the steam temperature, in order to be able to study condensation effects as well. First, investigations on gas/liquid countercurrent flows in the fluid system air/water are presented. Then one studies countercurrent flow in the system steam/water, including the investigation of condensation effects. Finally, a detailed description of the research on droplet size determination is given

  12. Determination of the hydrogen source term during the reflooding of an overheated core: Calculation results of the integral reflood test QUENCH-03 with PWR-type bundle

    International Nuclear Information System (INIS)

    Chikhi, Nourdine; Nguyen, Nam Giang; Fleurot, Joelle

    2012-01-01

    Highlights: ► Calculation of QUENCH-03 experiment with ASTEC/CATHARE. ► Validation of reflooding model in severe accidents conditions. ► Demonstration of a minimum flow rate for a successful reflood by using a system code. ► Effect of injection flow rate on hydrogen production. ► Effect of initial core temperature on hydrogen production. - Abstract: During a severe accident, one of the main accident management procedure consists of injecting water in the reactor core by means of various safety injection devices. Nevertheless, the success of a core reflood is not guaranteed because of possible negative effects: temperature escalation, enhanced hydrogen production, enhanced release of fission products, core degradation due to thermal shock, shattering, debris and melt formation. The QUENCH-03 experiment was carried out to investigate the behavior on reflooding at high temperature of LWR fuel rods with little oxidation. Posttest calculations with the ASTEC-CATHARE V2 code were made for code assessment and validation of the new reflooding model. This thermal–hydraulic model is used to detect the quench front position and to calculate the heat transfer between fuel and fluid in the transition boiling region. Comparisons between the calculational and experimental results are presented. Emphasis has been placed on clad temperature, hydrogen production and melt relocation. The effects of core state damage (initial temperature at reflooding onset) and the reflood mass flow rate on the hydrogen source term were investigated using the QUENCH-03 test as a base case. Calculations were made by varying both parameters in the input data deck. The results demonstrate (and confirm) the existence of a minimum flow rate for a successful reflood.

  13. SARAS MEASUREMENT OF THE RADIO BACKGROUND AT LONG WAVELENGTHS

    International Nuclear Information System (INIS)

    Patra, Nipanjana; Subrahmanyan, Ravi; Sethi, Shiv; Shankar, N. Udaya; Raghunathan, A.

    2015-01-01

    SARAS is a correlation spectrometer connected to a frequency independent antenna that is purpose-designed for precision measurements of the radio background at long wavelengths. The design, calibration, and observing strategies admit solutions for the internal additive contributions to the radiometer response, and hence a separation of these contaminants from the antenna temperature. We present here a wideband measurement of the radio sky spectrum by SARAS that provides an accurate measurement of the absolute brightness and spectral index between 110 and 175 MHz. Accuracy in the measurement of absolute sky brightness is limited by systematic errors of magnitude 1.2%; errors in calibration and in the joint estimation of sky and system model parameters are relatively smaller. We use this wide-angle measurement of the sky brightness using the precision wide-band dipole antenna to provide an improved absolute calibration for the 150 MHz all-sky map of Landecker and Wielebinski: subtracting an offset of 21.4 K and scaling by a factor of 1.05 will reduce the overall offset error to 8 K (from 50 K) and scale error to 0.8% (from 5%). The SARAS measurement of the temperature spectral index is in the range −2.3 to −2.45 in the 110–175 MHz band and indicates that the region toward the Galactic bulge has a relatively flatter index

  14. Teologi Politik Berbalu SARA Antara Ambisi dan Konspirasi

    Directory of Open Access Journals (Sweden)

    M. Sidi Ritau'din

    2017-06-01

    Full Text Available In a multi-cultural democracy based on Pancasila philosophy of independence, ethnic, religious, racial and intergroup issues it call (SARA are political indicators that can trigger conflict and division. If the player is ambitious and power-hungry, then he will not hesitate to do everything he can to gain power, even build a big conspiracy using SARA as a tool to divide the ummah, then he emerges as a unifier and presents programs prestigious sympathetic, there Imaging actions and slogans of the pro poor people, but essentially no more as political deceit, a false gift of hope, it familiar said (PHP that never realized, only reap the political advantage in the game of SARA, even not hesitate to shout thief when he Itself is a thieving thief based on greed and greed where the horizontal relations of fellow human beings deny the bond of faith as the foundation. Political conspiracy based on political interests and abuse of power, an action of political pathology that is not civilized that has become a trend of contemporary politics and globalization.

  15. Experimental study and modelling of pressure losses during reflooding of a debris beds

    International Nuclear Information System (INIS)

    Clavier, Remi

    2015-01-01

    This work deals with single and two-phase flow pressure losses in porous media. The aim is to improve understanding and modeling of momentum transfer inside particle beds, in relation with nuclear safety issues concerning the reflooding of debris beds during severe nuclear accidents. Indeed, the degradation of the core during such accidents can lead to the collapse of the fuel assemblies, and to the formation of a debris bed, which can be described as a hot porous medium. This thesis is included in a nuclear safety research project on coolability of debris beds during reflooding sequences. An experimental study of single and two-phase cold-flow pressure losses in particle beds is proposed. The geometrical characteristics of the debris and the hydrodynamic conditions are representative of the real case, in terms of granulometry, particle shapes, and flow velocities. The new data constitute an important contribution. In particular, they contain pressure losses and void fraction measurements in two-phase air-water flows with non-zero liquid Reynolds numbers, which did not exist before. Predictive models for pressure losses in single and two-phase flow through particle beds have been established from experimental data. Their structures are based on macroscopic equations obtained from the volume averaging of local conservation equations. Single-phase flow pressure losses can be described by a Darcy-Forchheimer law with a quadratic correction, in terms of filtration velocity, with a better-than-10 % precision. Numerical study of single-phase flows through porous media shows that this correlation is valid for disordered smooth particle beds. Two-phase flow pressure losses are described using a generalized Darcy-Forchheimer structure, involving inertial and cross flow terms. A new model is proposed and compared to the experimental data and to the usual models used in severe accident simulation codes. (author)

  16. 1980 Annual status report: super-SARA

    International Nuclear Information System (INIS)

    1981-01-01

    The essential tasks of the JRC for the SUPERSARA project during 1980 were therefore twofold: 1. Actuation of an international Task Force with which to: a. discuss in depth the test objectives and the relationships between the SSTP and the world mosaic of activities in the field of LWR fuel behaviour; b. establish a consensus test matrix; c. identify and discuss the major technological problems affecting the feasibility of attaining the consensus test objectives, especially for the boil-down SFD tests. A Task Force with these objectives was necessary in order to provide the elements for a Council decision on phase II. 2. Conservation of the rythm of the main contractor (UKAEA-Harwell) and subcontractors for the timely fabrication of loop components and the timely design of those new aspects of the plant necessary for the boil-down SFD tests

  17. Simulation of reflooding on two parallel heated channel by TRACE

    Energy Technology Data Exchange (ETDEWEB)

    Zakir, Md. Ghulam [Department of Nuclear Engineering, Chalmers University of Technology, Gothenburg (Sweden)

    2016-07-12

    In case of Loss-Of-Coolant accident (LOCA) in a Boiling Water Reactor (BWR), heat generated in the nuclear fuel is not adequately removed because of the decrease of the coolant mass flow rate in the reactor core. This fact leads to an increase of the fuel temperature that can cause damage to the core and leakage of the radioactive fission products. In order to reflood the core and to discontinue the increase of temperature, an Emergency Core Cooling System (ECCS) delivers water under this kind of conditions. This study is an investigation of how the power distribution between two channels can affect the process of reflooding when the emergency water is injected from the top of the channels. The peak cladding temperature (PCT) on LOCA transient for different axial level is determined as well. A thermal-hydraulic system code TRACE has been used. A TRACE model of the two heated channels has been developed, and three hypothetical cases with different power distributions have been studied. Later, a comparison between a simulated and experimental data has been shown as well.

  18. Use of moving heat conductor mesh to perform reflood calculations with RELAP4/MOD6

    International Nuclear Information System (INIS)

    Fischer, S.R.; Ellis, L.V.; Chen, Y.S.

    1979-01-01

    RELAP4 is a computer code which can be used for the transient thermal hydraulic analysis of light water reactors and related systems. RELAP4/MOD6 includes many new analytical models which were developed primarily for the analysis of the reflood phase of a PWR loss-of-coolant accident (LOCA) transient. The key feature forming the basis for the MOD6 reflood calculation is a unique moving finite differenced heat conductor. The development and application of the moving heat conductor mesh for use in reflood analysis are described

  19. Cylindrical core reflood test facility (CCTF) and slab core reflood test facility (SCTF) for Japan Atomic Energy Research Institute (JAERI)

    International Nuclear Information System (INIS)

    1981-01-01

    IHI has designed and constructed the CCTF at JAERI to be used in the safety analysis research on the loss of coolant accident in a PWR plant. This test facility is planned so that reflood phenomenon in the PWR plant (a phenomenon is that the bared and overheated core is reflooded by the emergency core cooling system when the coolant loss accident occurred) is simulated under various test conditions. The CCTF is the largest-scale test plant in the world, composed of approximately 2000 simulated fuel rods (electric heaters), 1 simulated pressure vessel, 4 primary cooling loops, 2 simulated steam generators, emergency core cooling system, and so on. The test conditions are controlled, and the test steps are sequentially progressed by the computing system, and test data are collected by the data acquisition system. Furthermore, IHI is now designing and constructing the SCTF in accordance with the JAERI research plan. The SCTF is similar to the CCTF in scale. Main feature of the SCTF is the form of the simulated core and the simulated pressure vessel, which is of slab construction to be representative of the radial section of the PWR reactor. Reliable and various data for safety analysis are expected by the CCTF and the SCTF. (author)

  20. Layering of life (Sara novel of Peter Sarić)

    OpenAIRE

    Kostić, Dragomir J.

    2015-01-01

    Novel Sara of Petar Sarić consists of two parts; in it are processed or present two wars, two major wars in the region of Montenegro and Herzegovina, the First and Second World War. However, it is more novel about divisions within the family and the man himself, (and infamous assault of godfather Luka on Sarah also and his murder are in that function), in the first part; and on the divisions among the people, in general, in the second part of the novel. The second part is, in fact, the image ...

  1. A simple blowdown code for SUPER-SARA loop conditions

    International Nuclear Information System (INIS)

    Fritz, G.

    1981-01-01

    The Super Sara test programme (SSTP) is aimed to study in pile the fuel and cluster behaviour under two types of accident conditions: - the ''Large break loss of coolant'' condition (LB-Loca), - the ''Severe fuel damage'' (SFD) in a boildown caused by a small break. BIVOL was developed for the LB-Loca situation. This code is made for a loop where essentially two volumes define the thermohydraulics during the blowdown. In the SUPERSARA loop these two volumes are represented by the hot leg and cold leg pipings together with the respective upper and lower plenum of the test section

  2. Assessment of one dimensional reflood model in REFLA/TRAC code

    International Nuclear Information System (INIS)

    Akimoto, Hajime; Ohnuki, Akira; Murao, Yoshio

    1993-12-01

    Post-test calculations for twelve selected SSRTF, SCTF and CCTF tests were performed to assess the predictive capability of the one-dimensional reflood model in the REFLA/TRAC code for core thermal behavior during the reflood in a PWR LOCA. Both core void fraction profile and clad temperature transients were predicted excellently by the REFLA/TRAC code including parameter effect of core inlet subcooling, core flooding rate, core configuration, core power, system pressure, initial clad temperature and so on. The peak clad temperature was predicted within an error of 50 K. Based on these assessment results, it is verified that the core thermal hydraulic behaviors during the reflood can be predicted excellently with the REFLA/TRAC code under various conditions where the reflood may occur in a PWR LOCA. (author)

  3. The effect of inlet flow oscillations on reflooding of a tubular test section

    International Nuclear Information System (INIS)

    Oh, S.; Banerjee, S.; Yadigaroglu, G.

    1983-01-01

    The reflooding of a vertical channel under oscillatory inlet flow conditions has been investigated experimentally. Compared to constant injection, oscillations always increase the liquid carryover in the early stages of reflooding. As reflooding progresses, the enhancement diminishes. The crossover point roughly coincides with saturation of the liquid at the quench front (QF). The higher liquid carryover at the beginning increases downstream heat transfer and speeds up QF propagation. But this higher liquid carryover, in turn, reduces the test section mass accumulation rate and delays QF propagation at later stages. The enhancement of liquid carryover, and the early increase and subsequent decrease in quench velocity are all accentuated as the oscillation amplitude and frequency increase. Large amplitude oscillations change the characteristics of QF propagation and the heat transfer immediately downstream of QF substantially. Correlations based on constant-injection reflooding data are not adequate, even if they are applied on an average local-conditions basis

  4. A study on quench phenomena during reflood phase, 1

    International Nuclear Information System (INIS)

    Murao, Yoshio; Sudoh, Takashi

    1977-03-01

    Based on the observation with an outside-heated quartz tube experiment of the reflood phase, three quench modes for bottom flooding are proposed : 1) liquid column type, 2) dryout type, 3) droplet-rewetting type. Using Blair's correlation for quench velocity, the approximate correlation for maximum liquid superheat, the assumption that the heat transfer upstream of the quench front is a function of the local liquid subcooling and the data of PWR-FLECHT experiments, the correlation for quench velocity of the liquid column type and of the dryout type are obtained. The quench temperature for the droplet-rewetting type is also derived. These relations are compared with the results of PWR-FLECHT Group 1 experiments and of Piggott and Porthouse's experiments. The agreements among them are fairly good. (auth.)

  5. Modeling of reflood of severely damaged reactor core

    International Nuclear Information System (INIS)

    Bachrata, A.

    2012-01-01

    The TMI-2 accident and recently Fukushima accident demonstrated that the nuclear safety philosophy has to cover accident sequences involving massive core melt in order to develop reliable mitigation strategies for both, existing and advanced reactors. Although severe accidents are low likelihood and might be caused only by multiple failures, accident management is implemented for controlling their course and mitigating their consequences. In case of severe accident, the fuel rods may be severely damaged and oxidized. Finally, they collapse and form a debris bed on core support plate. Removal of decay heat from a damaged core is a challenging issue because of the difficulty for water to penetrate inside a porous medium. The reflooding (injection of water into core) may be applied only if the availability of safety injection is recovered during accident. If the injection becomes available only in the late phase of accident, water will enter a core configuration that will differ from original rod bundle geometry and will resemble to the severe damaged core observed in TMI-2. The higher temperatures and smaller hydraulic diameters in a porous medium make the coolability more difficult than for intact fuel rods under typical loss of coolant accident conditions. The modeling of this kind of hydraulic and heat transfer is a one of key objectives of this. At IRSN, part of the studies is realized using an European thermo-hydraulic computer code for severe accident analysis ICARE-CATHARE. The objective of this thesis is to develop a 3D reflood model (implemented into ICARE-CATHARE) that is able to treat different configurations of degraded core in a case of severe accident. The proposed model is characterized by treating of non-equilibrium thermal between the solid, liquid and gas phase. It includes also two momentum balance equations. The model is based on a previously developed model but is improved in order to take into account intense boiling regimes (in particular

  6. Rumen Microbiome Composition in Cattle during Grain-Induced Subacute Ruminal Acidosis (SARA)

    DEFF Research Database (Denmark)

    Danscher, Anne Mette; Derakshani, Hooman; Li, Shucong

    2014-01-01

    at the genus level. The rumen bacterial communities were altered in response to SARA (P=0.01). The proportion of several taxa was significantly higher in SARA samples, including S24-7, Erysipelotrichales. Lactobacillus, C lostridia, Moryella, Butyrivibrio, Olsenella, and C oprococcus. Microbiome profiling...

  7. Code option guideline improvement using comparisons of RELAP4/MOD6 with forced and gravity-feed reflood data. [PWR

    Energy Technology Data Exchange (ETDEWEB)

    Chen, T H; Fletcher, C D

    1978-09-01

    Improved guidelines are developed for the selection of RELAP4/MOD6 reflood heat transfer options. The development, involving modifications to the original guidelines, assessed the effect of those modifications on RELAP4/MOD6 data comparisons using previously analyzed reflood experiments. The report also presents an evaluation of the application of the revised guidelines. Data comparisons between RELAP4/MOD6, using the original and revised guidelines, and experimental data are presented for Semiscale and FLECHT, forced-feed reflood tests and Semiscale and FLECHT-SET gravity-feed reflood tests. Because a general improvement was evident in data comparisons using the revised guidelines, their use is recommended in future calculations.

  8. Fish fauna recovery in a newly re-flooded Mediterranean coastal lagoon

    Science.gov (United States)

    Koutrakis, Emmanuil; Sylaios, Georgios; Kamidis, Nikolaos; Markou, Dimitrios; Sapounidis, Argyris

    2009-08-01

    Drana Lagoon, located at the NW site of Evros River Delta, was drained in 1987 and re-flooded in 2004 within the framework of an integrated wetland restoration project. This study presents the results of a monitoring program of the lagoon's oceanographic, water quality and fish fauna characteristics, during the pre- and post-restoration period. Results depict the presence of high salinity water (up to 41) due to seawater intrusion, strong evaporation in its interior and inadequate freshwater inflows. Overall, nutrient levels were low depicting local changes. Tidal variability at the mouth was approximately 0.2 m, producing high velocity tidal currents (up to 0.75 m/s). Eleven fish fauna species were collected; seven species were caught in both the inlet channel and the lagoon during the pre-restoration period and nine species in the post-restoration period. Atherina boyeri (37.6%) and Pomatoschistus marmoratus (31.7%) dominated the lagoon during the post-restoration period. Most of the A. boyeri specimens (88.5%) were caught inside the lagoon, while P. marmoratus had an almost equal distribution in the inlet channel and the lagoon (56.3% and 43.7% respectively). The presence of species of the Mugilidae family (5.2% total average catches after lagoon re-flooding) was mainly in the inlet channel (12.6% of the average catches) and not inside the lagoon (only 1.3% of the average catches). The small number of fish species inhabiting the lagoon might be the result of the recent restoration or it could be related with the increased water flow observed at the lagoon mouth during the flood and ebb tidal phases, and also in the presence of a smooth bank in the concrete waterspout that connects the entrance channel with the lagoon. The limited presence of the Mugilidae juveniles inside the lagoon could be related to the prevailing tidal inlet dynamics (i.e. strong ebb flow at lagoon inlet), thus preventing the species to enter the lagoon. In order to restore the lagoon

  9. Sara, a patient with borderline personality structure: A "crisis" management

    Directory of Open Access Journals (Sweden)

    Paola Marinelli

    2015-05-01

    Full Text Available In this article the author examines some significant passages of his treatment of a patient with borderline personality structure, with the intention of giving a formative contribution to the delicate issue of the search for congruence between theory and clinic operations. This reflection is therefore an opportunity to integrate these aspects. The individualization of the therapeutic relationship in the theoretical framework of group analysis allowed the emotional investment in the person of the therapist, which is useful in the construction of a meaningful relationship on the human, emotional and cognitive plane; a space within which it has become increasingly possible for Sara, share and process emotions, re-build, contact parts of the self frustrated and disappointed, perceive less and less the void and become less vulnerable, being able to pull over to the original trauma. 

  10. Staphylococcus aureus sarA regulates inflammation and colonization during central nervous system biofilm formation.

    Directory of Open Access Journals (Sweden)

    Jessica N Snowden

    Full Text Available Infection is a frequent and serious complication following the treatment of hydrocephalus with CSF shunts, with limited therapeutic options because of biofilm formation along the catheter surface. Here we evaluated the possibility that the sarA regulatory locus engenders S. aureus more resistant to immune recognition in the central nervous system (CNS based on its reported ability to regulate biofilm formation. We utilized our established model of CNS catheter-associated infection, similar to CSF shunt infections seen in humans, to compare the kinetics of bacterial titers, cytokine production and inflammatory cell influx elicited by wild type S. aureus versus an isogenic sarA mutant. The sarA mutant was more rapidly cleared from infected catheters compared to its isogenic wild type strain. Consistent with this finding, several pro-inflammatory cytokines and chemokines, including IL-17, CXCL1, and IL-1β were significantly increased in the brain following infection with the sarA mutant versus wild type S. aureus, in agreement with the fact that the sarA mutant displayed impaired biofilm growth and favored a planktonic state. Neutrophil influx into the infected hemisphere was also increased in the animals infected with the sarA mutant compared to wild type bacteria. These changes were not attributable to extracellular protease activity, which is increased in the context of SarA mutation, since similar responses were observed between sarA and a sarA/protease mutant. Overall, these results demonstrate that sarA plays an important role in attenuating the inflammatory response during staphylococcal biofilm infection in the CNS via a mechanism that remains to be determined.

  11. Statistical Uncertainty Quantification of Physical Models during Reflood of LBLOCA

    Energy Technology Data Exchange (ETDEWEB)

    Oh, Deog Yeon; Seul, Kwang Won; Woo, Sweng Woong [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2015-05-15

    The use of the best-estimate (BE) computer codes in safety analysis for loss-of-coolant accident (LOCA) is the major trend in many countries to reduce the significant conservatism. A key feature of this BE evaluation requires the licensee to quantify the uncertainty of the calculations. So, it is very important how to determine the uncertainty distribution before conducting the uncertainty evaluation. Uncertainty includes those of physical model and correlation, plant operational parameters, and so forth. The quantification process is often performed mainly by subjective expert judgment or obtained from reference documents of computer code. In this respect, more mathematical methods are needed to reasonably determine the uncertainty ranges. The first uncertainty quantification are performed with the various increments for two influential uncertainty parameters to get the calculated responses and their derivatives. The different data set with two influential uncertainty parameters for FEBA tests, are chosen applying more strict criteria for selecting responses and their derivatives, which may be considered as the user’s effect in the CIRCÉ applications. Finally, three influential uncertainty parameters are considered to study the effect on the number of uncertainty parameters due to the limitation of CIRCÉ method. With the determined uncertainty ranges, uncertainty evaluations for FEBA tests are performed to check whether the experimental responses such as the cladding temperature or pressure drop are inside the limits of calculated uncertainty bounds. A confirmation step will be performed to evaluate the quality of the information in the case of the different reflooding PERICLES experiments. The uncertainty ranges of physical model in MARS-KS thermal-hydraulic code during the reflooding were quantified by CIRCÉ method using FEBA experiment tests, instead of expert judgment. Also, through the uncertainty evaluation for FEBA and PERICLES tests, it was confirmed

  12. System Analysis and Risk Assessment system (SARA) Version 4.0

    International Nuclear Information System (INIS)

    Sattison, M.B.; Russell, K.D.; Skinner, N.L.

    1992-01-01

    This NUREG is the tutorial for the System Analysis and Risk Assessment System (SARA) Version 4.0, a microcomputer-based system used to analyze the safety issues of a family [i.e., a power plant, a manufacturing facility, any facility on which a probabilistic risk assessment (PRA) might be performed]. A series of lessons are provided that walk the user through some basic steps common to most analyses performed with SARA. The example problems presented in the lessons build on one another, and in combination, lead the user through all aspects of SARA sensitivity analysis

  13. Assessment of reflood heat transfer model of COBRA-TIF against ABB-CE evaluation model

    Energy Technology Data Exchange (ETDEWEB)

    Lee, S. I.; Lee, S. Y.; Park, C. E.; Choi, H. R.; Choi, C. J. [Korea Power Engineering Company Inc., Taejon (Korea, Republic of)

    2000-05-01

    According to 10 CFR 50 Appendix K, ECCS performance evaluation model should be based on the experimental data of FLECHT and have the conservatism compared with experimental data. To meet this requirement ABB-CE has the complicate code structure as follows: COMPERC-II calculates three reflood rates, and FLELAPC and HTCOF calculate the reflood heat transfer coefficients, and finally STRIKIN-II calculates the cladding temperature using the reflood heat transfer calculated in previous stage. In this paper, to investigate whether or not COBRA-TF satisfies the requirement of Appendix K, the reflood heat transfer coefficient of COBRA-TF was assessed against ABB-CE MOD-2C model. It was found out that COBRA-TF predicts properly the experimental data and has more conservatism than the results of ABB-CE MOD-2C model. Based on these results, it can be concluded that the reflood heat transfer coefficients calculated by COBRA-TF meet the requirement of Appendix K.

  14. Reactor hydrodynamics during the reflood phase of a loss-of-coolant accident

    International Nuclear Information System (INIS)

    Gay, R.R.

    1977-01-01

    The thermohydraulics of a nuclear reactor during the reflood phase of a hypothetical loss-of-coolant accident can be represented by moving control volume methodology in which six control volumes are used to represent the downcomer, lower plenum, and reactor core. The one-dimensional, homogeneous, equilibrium constitutive equations for two-phase steam/water flow are solved in each control volume and connecting junctions. One of the three core control volumes represents the quench region; it changes size and position based on the axial location of the clad quench temperature and the condensed liquid level in the flow channel. The lengths of the remaining two core control volumes are determined by the position of the quench region. Simulation of actual reflood experiments demonstrates that the methodology predicts reflood-like flow oscillations and reproduces the correct trends in experimental data. The moving control volume methodology has proven itself as a valid concept for reflood hydrodynamics, but further development of the existing EFLOD code is required for simulation of actual reflood experiments

  15. RELAP/REFLA (Mod 0): a system reflooding analysis computer program

    International Nuclear Information System (INIS)

    Fujiki, Kazuo; Murao, Yoshio; Shimooke, Takanori.

    1981-03-01

    A new computer code RELAP/REFLA has been developed, aiming at analyses of the core reflooding phenomena during the postulated loss-of-coolant accident of PWRs. The code was originated from the combination of two distinct codes, RELAP4-FLOOD and REFLA-1D. The characteristics of the code are: (1) Kinematical model based on the observation and analysis of quench experiments is used for the thermal-hydraulic analysis of reflooding core, (2) it has the capability to analyse the reflooding phenomena in an arbitrary type of PWR or experimental facility, including the system feedback effects, (3) the flow paths in the actual system are represented by the combination of 1-dimentional flow paths, and vapor-liquid equilibrium model is applied except the reflooding core. This report is a code manual of RELAP/REFLA (version Mod 0) and contains the descriptions of the basic models, basic equations, code structure and input format. The calculated results of two kinds of sample problems, i.e., reflooding problem on the 4 loop PWR and FLECHT-SET experiment, are also presented. Relatively close agreement between FLECHT-SET data and the calculated results was obtained for the lower portion of the core, but poor agreement for the temperature histories in the upper core and carryover ratio. Running speed and core memory size are almost equal to those of RELAP 4/Mod 3. (author)

  16. Reflooding experiments on a 49-rod cluster containing a long 90% blockage

    International Nuclear Information System (INIS)

    Pearson, K.G.; Cooper, C.A.; Jowitt, D.; Kinneir, J.H.

    1983-01-01

    A series of reflooding experiments was performed on a model fuel assembly, containing a very severe partial blockage, in the THETIS rig. The assembly comprised 49 full length, electrically heated fuel rod simulators and the blockage was created by attaching thin-walled, preformed swellings to a group of 16 rods. Results are presented for single phase and forced reflooding experiments. The most important findings relate to the improvements in heat transfer created by spacer grids and the nature of the heat transfer processes within the blockage. Spacer grids are shown to improve heat transfer by increasing turbulence and also, when wet, by cooling the steam flowing through them. Liquid penetration evidently deteriorates as the rewetting front approaches the blockage, allowing the steam through the blockage to superheat strongly and giving rise to a late peak in cladding temperature. At low reflooding rates there is a temperature penalty associated with the blockage which becomes increasingly larger as the reflooding rate is reduced. The adequacy of cooling in this very severe blockage becomes questionable when the reflooding rate falls to about 2cm/s. (U.K.)

  17. A moving subgrid model for simulation of reflood heat transfer

    International Nuclear Information System (INIS)

    Frepoli, Cesare; Mahaffy, John H.; Hochreiter, Lawrence E.

    2003-01-01

    In the quench front and froth region the thermal-hydraulic parameters experience a sharp axial variation. The heat transfer regime changes from single-phase liquid, to nucleate boiling, to transition boiling and finally to film boiling in a small axial distance. One of the major limitations of all the current best-estimate codes is that a relatively coarse mesh is used to solve the complex fluid flow and heat transfer problem in proximity of the quench front during reflood. The use of a fine axial mesh for the entire core becomes prohibitive because of the large computational costs involved. Moreover, as the mesh size decreases, the standard numerical methods based on a semi-implicit scheme, tend to become unstable. A subgrid model was developed to resolve the complex thermal-hydraulic problem at the quench front and froth region. This model is a Fine Hydraulic Moving Grid (FHMG) that overlies a coarse Eulerian mesh in the proximity of the quench front and froth region. The fine mesh moves in the core and follows the quench front as it advances in the core while the rods cool and quench. The FHMG software package was developed and implemented into the COBRA-TF computer code. This paper presents the model and discusses preliminary results obtained with the COBRA-TF/FHMG computer code

  18. The new species of Mysidacea (Crustacea), Anchialina labatus and Gastrosaccus sarae, from south west Australia

    Digital Repository Service at National Institute of Oceanography (India)

    Panampunnayil, S.U.

    on the third segment of the mandibular palp and by the modification of the exopod of the third pleopod of the male. G. sarae is distinguished from the other species by the shape and armature of the telson...

  19. A 'quick-look' report on the THETIS 80% blocked cluster forced reflood experiments

    International Nuclear Information System (INIS)

    Cooper, C.A.; Pearson, K.G.

    1984-01-01

    A brief selection of results of forced reflooding experiments with the THETIS 80 percent blocked cluster is presented. A description of the THETIS blocked cluster test assemblies, and details of the test conditions, are given. The two forced reflooding experiments have been the subject of a blind calculation exercise with the BART code, and the results of these experiments are compared with the results from corresponding experiments with the 90 percent blocked cluster test assembly. Some general observations are made, arising from the comparison of these two series of experiments, and a qualitative explanation for the relatively complex variation of the heat transfer within the THETIS blockages is advanced. A full report on the 80 percent blocked cluster forced reflooding experiments will be available later. (U.K.)

  20. RELAP4/MOD6 analysis of forced- and gravity-feed reflood tests

    International Nuclear Information System (INIS)

    Chen, T.H.; Fletcher, C.D.

    1980-01-01

    The RELAP4/MOD6 computer code is used for the analysis of the reactor core heat transfer during the reflooding phase of a postulated loss-of-coolant accident (LOCA) in a pressurized water reactor (PWR). The code requires the user to specify input parameters for the reflood heat transfer models. Results of previous comparisons of code calculations with experimental data have indicated no single selection of input parameters is adequate for a spectrum of tests and test facilities. This paper presents the development of revised quidelines and assesses the effect of those modifications on RELAP4/MOD6 data comparisons using previously analyzed reflood experiments. The paper also presents an assessment of the revised guidelines and the original guidelines against experimental data significantly different from previously analyzed tests

  1. Geometric effects of spacer grid in an annulus flow channel during reflooding period

    International Nuclear Information System (INIS)

    Cho, S.; Chun, S. Y.; Kim, B. D.; Park, J. K.; Yun, Y. J.; Baek, W. P.

    2004-01-01

    A number of studies on the reflooding phase were actively carried out from the early 70's due to its importance for the safety of the nuclear reactor. (Martini et al., 1973; Henry, 1974; Chung, 1978;) However, few studies have presented the spacer grid effect during the reflooding period. Since the grid is an obstruction in the flow passage, it causes an increased pressure drop due to form and skin friction losses. On the other hand, the spacer grid tends to increase the local wall heat transfer. The present work has been performed in a vertical annulus flow channel with various flow conditions. The objective of this paper is to evaluate the effects of a swirl-vane spacer grid on the rewetting phenomena during the reflooding phase

  2. ORNL instrumentation performance for Slab Core Test Facility (SCTF)-Core I Reflood Test Facility

    International Nuclear Information System (INIS)

    Hardy, J.E.; Hess, R.A.; Hylton, J.O.

    1983-11-01

    Instrumentation was developed for making measurements in experimental refill-reflood test facilities. These unique instrumentation systems were designed to survive the severe environmental conditions that exist during a simulated pressurized water reactor loss-of-coolant accident (LOCA). Measurement of in-vessel fluid phenomena such as two-phase flow velocity and void fraction and film thickness and film velocity are required for better understanding of reactor behavior during LOCAs. The Advanced Instrumentation for Reflood Studies (AIRS) Program fabricated and delivered instrumentation systems and data reduction software algorithms that allowed the above measurements to be made. Data produced by AIRS sensors during three experimental runs in the Japanese Slab Core Test Facility are presented. Although many of the sensors failed before any useful data could be obtained, the remaining probes gave encouraging and useful results. These results are the first of their kind produced during simulated refill-reflood stage of a LOCA near actual thermohydrodynamic conditions

  3. Calculations for the design and modification of the 2 cyclotrons of S.A.R.A

    International Nuclear Information System (INIS)

    Albrand, P.S.; Belmont, J.L.; Ripouteau, F.

    1983-09-01

    S.A.R.A. is a heavy ion accelerator constituted by 2 cyclotrons. The second cyclotron (post-accelerator) was entirely calculated at the I.S.N. The pole tips of the first cyclotron which is much older, have recently been modified. An almost identical procedure was used for the calculation of each element of the post-accelerator of S.A.R.A. and also for the modifications to the first cyclotron

  4. Reflooding phase after loss of coolant of an advanced pressurized water reactor with high conversion ratio

    International Nuclear Information System (INIS)

    Schumann, S.

    1984-01-01

    The emergency core cooling behaviour of an advanced pressurized water reactor (APWR) during the reflooding phase of the LOCA with double-ended break is analysed and compared to a common pressurized water reactor (PWR). The code FLUT-BS, its models and correlations are explained in detail and have been verified by numerous PWR-reflood experiments with large parameter range. The influence of core-design on ECC-behaviour as well as the influences of initial and boundary values are examined. The results show the essential differences of ECC-behaviour between PWR and APWR. (orig.) [de

  5. A Study on Uncertainty Quantification of Reflood Model using CIRCE Methodology

    International Nuclear Information System (INIS)

    Jeon, Seongsu; Hong, Soonjoon; Oh, Deogyeon; Bang, Youngseok

    2013-01-01

    The CIRCE method is intended to quantify the uncertainties of the correlations of a code. It may replace the expert judgment generally used. In this study, an uncertainty quantification of reflood model was performed using CIRCE methodology. In this paper, the application process of CIRCE methodology and main results are briefly described. This research is expected to be useful to improve the present audit calculation methodology, KINS-REM. In this study, an uncertainty quantification of reflood model was performed using CIRCE methodology. The application of CIRCE provided the satisfactory results. This research is expected to be useful to improve the present audit calculation methodology, KINS-REM

  6. Evaluation of the Trac-PF1 code for simulating the Neptun reflooding experiment

    International Nuclear Information System (INIS)

    Pontedeiro, A.C.; Galetti, M.R.S.

    1991-01-01

    The present work presents an assessment of the TRAC-BF1 code using the results of the NEPTUN experiment which simulates the reflooding in a loss-of-coolant accident (LOCA) in a PWR. The NEPTUN experiment is composed of an array of electrically-heated tubes where the reflooding condition can be tested. Two types of tests results are presented and compared with the values obtained with the TRAC-BF1 code. From this comparison it is concluded that TRAC is suitable for verifying accident analysis. (author)

  7. Evaluation of the pressure difference across the core during PWR-LOCA reflood phase

    International Nuclear Information System (INIS)

    Iguchi, Tadashi; Murao, Yoshio

    1979-03-01

    The flooding rate of the core influences largely cooling of the core during the reflood phase of a PWR-LOCA. Since the void fraction of two-phase flow in the core is important determining the flooding rate, it is essential to examine this void fraction. The void fraction in the core during the reflood phase obtained by experiment was compared with those predicted by the correlations respectively of Akagawa, Nicklin, Zuber, Yeh, Griffice, Behringer and Jhonson. Only Yeh's correlation was found to be usable for the purpose. The pressure difference of the core during the reflood phase was calculated by reflood analyzing code REFLA-1D using Yeh's correlation. Following are the results: (1) During the steady-state period after quenching of the heaters, the prediction agrees within +-15% with the experiment. (2) During the transient period when the quench front is advancing, the prediction is not in agreement with the experiment, the difference being about +-40%. Influence of the advancing quench front upon the void fraction in the core must further be studied. (author)

  8. Calculations of film boiling heat transfer above the quench front during reflooding

    International Nuclear Information System (INIS)

    Chan, K.C.; Yadigaroglu, G.

    1980-01-01

    An analytical method for calculating inverted-annular film boiling heat transfer above the quench front during the reflooding phase of a LOCA is presented. A two-fluid model comprising a laminar vapor film and a turbulent liquid-vapor mixture core is used. 12 refs

  9. Experimental study of the reflooding of a constricted tube in the REFLEX rig

    International Nuclear Information System (INIS)

    Denham, M.K.; Elliott, D.F.; Britton-Jones, K.A.

    1982-08-01

    The Winfrith experimental programme in support of the PWR is focussed on fuel thermal and hydraulic performance under hypothetical accident conditions, and includes studies of reflooding heat transfer of single tubes and fuel rod clusters under simulated accident conditions, aimed at improving understanding of the processes involved and providing data for code development and validation. The work described is part of a study of the possible effects of clad ballooning on ECCS effectiveness. During a large loss of coolant accident the primary circuit will depressurise and the core will overheat. The Zircaloy fuel cladding may swell, partially blocking the coolant passages by the formation of local ''balloons''. An experiment was carried out in the REFLEX single tube reflooding rig, to study, in a simple geometry, the effect of the partial blockage of the tube on the fluid flow and heat transfer during reflooding. The blockage consisted of a tapering entrance with a flow area 60 percent less than the unconstricted tube, and a tapering exit. The flow could be viewed through windows. 66 refloods were carried out over a pressure range of 1 to 4 bar. Results of these tests are presented. (U.K.)

  10. Prediction of reflood behavior for tests with differing axial power shapes using WCOBRA/TRAC

    International Nuclear Information System (INIS)

    Bajorek, S.M.; Hochreiter, L.E.

    1991-01-01

    The rector core power shape can vary over the fuel cycle due to load follow, control rod movement, burnup effects and Xenon transients. a best estimate thermal-hydraulic code must be able to accurately predict the reflooding behavior for different axial power shapes in order to find the power shapes effects on the loss-of-coolant peak cladding temperature. Several different reflood heat transfer experiments have been performed at the same or similar PWR reflood conditions with different axial power shapes. These experiments have different rod diameters, were full length, 3.65 m (12 feet) in height, and had simple egg crate grids. The WCOBRA/TRAC code has been used to model several different tests from these three experiments to examine the code's capability to predict the reflood transient for different power shapes, with a consistent model and noding scheme. This paper describes these different experiments, their power shapes, and the test conditions. The WCOBRA/TRAC code is described as well as the noding scheme, and the calculated results will be compared in detail with the test data rod temperatures. An overall assessment of the code's predictions of these experiments is presented

  11. Experimental and theoretical study of large scale debris bed reflood in the PEARL facility

    Energy Technology Data Exchange (ETDEWEB)

    Chikhi, Nourdine, E-mail: nourdine.chikhi@irsn.fr; Fichot, F.

    2017-02-15

    Highlights: • Five reflooding tests have been carried out with an experimental bed, 500 mm in height and 500 mm in diameter, made of 4 mm stainless steel balls. • For the first time, such a large bed was heated practically homogenously. • The quench front velocity was determined according to thermocouple measurements inside the bed. • An analytical model, assuming a quasi-steady progression of the quench front, allows to predict the conversion ratio in most cases. • It appears that the efficiency of cooling can be increased only up to a certain limit when increasing the inlet water flow rate. - Abstract: During a severe accident in a nuclear power plant, the degradation of fuel rods and melting of materials lead to the accumulation of core materials, which are commonly, called “debris beds”. To stop core degradation and avoid the reactor vessel rupture, the main accident management procedure consists in injecting water. In the case of debris bed, the reflooding models used for Loss of Coolant Accident are not applicable. The IRSN has launched an experimental program on debris bed reflooding to develop new models and to validate severe accident codes. The PEARL facility has been designed to perform, for the first time, the reflooding of large scale debris bed (Ø540 mm, h = 500 mm and 500 kg of steel debris) in a pressurized containment. The bed is heated by means of an induction system. A specific instrumentation has been developed to measure the debris bed temperature, pressure drop inside the bed and the steam flow rate during the reflooding. In this paper, the results of the first integral reflooding tests performed in the PEARL facility at atmospheric pressure up to 700 °C are presented. Focus is made on the quench front propagation and on the steam flow rate during reflooding. The effect of water injection flow rate, debris initial temperature and residual power are also discussed. Finally, an analytical model providing the steam flow rate and

  12. Evaluation report on CCTF Core-II reflood test C2-1 (Run 55)

    International Nuclear Information System (INIS)

    Iguchi, Tadashi; Sugimoto, Jun; Akimoto, Hajime; Okubo, Tsutomu; Murao, Yoshio

    1991-10-01

    A high pressure test (0.42 MPa) on the reflood phenomena was performed with the CCTF. The result of the test was compared with the experimental result of the base case test (0.2 MPa). (1) The overall flow characteristics in the high pressure test were qualitatively similar to that of the base case test. Any qualitatively different phenomena were not recognized during reflood phase. This indicates that it is reasonable to utilize the physical reflood model developed from the result of the base case test to the high pressure condition at least up to 0.42 MPa for prediction of reflood behavior of PWRs. (2) On the other hand, following quantitative influence of high pressure on reflood phenomena was observed. The core cooling was better, and the mass flow rate of the steam generated in the core was larger. However, the steam velocity was smaller due to higher density of the steam. Therefore, the steam discharge through loops was easier and hence the so-called steam binding effect was weaker. And, the water accumulation rate in the core was larger. Consequently the core flooding mass flow rate was larger. Since the core cooling was better, the maximum core temperature was lower and the last quenching was earlier. This result was the same as that previously observed in CCTF tests in the scope of the pressure upto 0.3 MPa. (3) The higher pressure leads to the better core cooling, and hence the safety margin increases with the increase in the pressure. (author)

  13. Phosphorus Dynamics in Long-Term Flooded, Drained, and Reflooded Soils

    Directory of Open Access Journals (Sweden)

    Juan Tian

    2017-07-01

    Full Text Available In flooded areas, soils are often exposed to standing water and subsequent drainage, thus over fertilization can release excess phosphorus (P into surface water and groundwater. To investigate P release and transformation processes in flooded alkaline soils, wheat-growing soil and vegetable-growing soil were selected. We flooded-drained-reflooded two soils for 35 d, then drained the soils, and 10 d later reflooded the soils for 17 d. Dissolved reactive phosphorus (DRP, soil inorganic P fractions, Olsen P, pH, and Eh in floodwater and pore water were analyzed. The wheat-growing soil had significantly higher floodwater DRP concentrations than vegetable-growing soil, and floodwater DRP in both soils decreased with the number of flooding days. During the reflooding period, DRP in overlying floodwater from both soils was less than 0.87 mg/L, which was 3–25 times less than that during the flooding period. Regardless of flooding or reflooding, pore water DRP decreased with flooding days. The highest concentration of pore water DRP observed at a 5-cm depth. Under the effect of fertilizing and flooding, the risk of vertical P movement in 10–50 cm was enhanced. P diffusion occurred from the top to the bottom of the soils. After flooding, Al-P increased in both soils, and Fe-P, O-P, Ca2-P decreased, while Fe-P, Al-P, and O-P increased after reflooding, When Olsen P in the vegetable-growing soil exceeded 180.7 mg/kg and Olsen P in the wheat-growing soil exceeded 40.8 mg/kg, the concentration of DRP in pore water increased significantly. Our results showed that changes in floodwater and pore water DRP concentrations, soil inorganic P fractions, and Olsen P are significantly affected by fertilizing and flooding; therefore, careful fertilizer management should be employed on flooded soils to avoid excess P loss.

  14. Study of the thermo-hydrodynamic phenomena in the nuclear core during reflood phase

    International Nuclear Information System (INIS)

    Murao, Yoshio

    1983-03-01

    This paper describes the development of the core thermo-hydrodynamic model on the reflood phenomena during a loss-of-coolant accident in a light water reactor. This model was developed based on the physical understanding in order to obtain the flexibility of application to safety analysis. For this purpose, the flow pattern was modeled and the fundamental equations were derived. The equations were used to know the suitable variables for assembling the thermo-hydrodynamic model of each flow regime in a reflood analysis code. Then the hydrodynamic models and the heat transfer models of all flow regimes and the quench model were derived. Some of them were newly developed. It was found that water accumulation above the quench front occurred in some cases, however the criteria was not clarified. One-dimensional forced-feed reflood tests were performed and the models were assessed and partly improved by using the data of the tests. The verified models were built in a one-dimensional reflood analysis code and totally assessed with the data of the test mentioned above. Except for the location just below a grid spacer and cases of high flooding rate, the calculational results indicated good comparison with the experimental results when the water accumulation was assumed above the quench front. Additionally the test data from the other test facility were used for the verification of the model. The results also showed good comparison with the experimental results. It was found that better comparisons were obtained when the water accumulation was not assumed above quench front. From these assessment of the model, it was found that the model derived here describes the over-all reflood phenomena, while it has to be partly improved and the water accumulation phenomena should be further investigated. (author)

  15. Investigation of reflood models by coupling REFLA-1D and multi-loop system model

    International Nuclear Information System (INIS)

    Sugimoto, Jun; Murao, Yoshio

    1983-09-01

    A system analysis code REFLA-1DS was developed by coupling reflood analysis code REFLA-1D and a multi-loop primary system model. The reflood models in the code were investigated for the development of the integral system analysis code. The REFLA-1D, which was developed with the small scale reflood experiment at JAERI, consists of one-dimensional core model and a primary system model with a constant loop resistance. The multi-loop primary system model was developed with the Cylindrical Core Test Facility of JAERI's large scale reflood tests. The components modeled in the code are the upper plenum, the steam generator, the coolant pump, the ECC injection port, the downcomer and the broken cold leg nozzle. The coupling between the two models in REFLA-1DS is accomplished by applying the equivalent flow resistance calculated with the multiloop model to the REFLA-1D. The characteristics of the code is its simplicity of the system model and the solution method which enables the fast running and the easy reflood analysis for the further model development. A fairly good agreement was obtained with the results of the Cylindrical Core Test Facility for the calculated water levels in the downcomer, the core and the upper plenum. A qualitatively good agreement was obtained concerning the parametric effects of the system pressure, the ECC flow rate and the initial clad temperature. Needs for further code improvements of the models, however, were pointed out. These include the problem concerning the generation rate of the steam and water droplets in the core in an early period, the effect of the flow oscillation on the core cooling, the heat release from the downcomer wall, and the stable system calculation. (author)

  16. Evaluation report on CCTF core-II reflood test C2 - 18 (Run 78)

    International Nuclear Information System (INIS)

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

    1987-03-01

    This report presents the result of the upper plenum injection (UPI) test C2 - 18 (Run 78), which was conducted on November 13, 1984 with the Cylindrical Core Test Facility (CCTF) at Japan Atomic Energy Research Institute (JAERI). The CCTF is a 1/21.4 scale model of a 1,100 MWe PWR with four loop active components to provide information on the system and core thermo-hydrodynamics during reflood phase. The objectives of the test are to investigate the refill behavior with UPI condition and to investigate the reflood behavior with UPI Best-Estimate (BE) condition. The test was performed to simulate refill/reflood behavior with UPI and BE conditions (However, the LPCI flow rate was determined based on single failure of LPCI pumps.). The result of the test showed the followings. (1) Little special phenomena were recognized under UPI and BE conditions in comparison with those under UPI and Evaluation-Model (EM) conditions, although certain special phenoma (i.e. significant fluid oscillation) were recognized under Cold-Leg-Injection (CLI) and BE conditions in comparison with those under CLI and EM conditions. (2) Water inventory in lower plenum increased smoothly due to water injected into both upper plenum and cold leg during refill phase, similarly to that in refill-simulation test with CLI condition. Small difference in refill behavior with UPI condition is the existing of steam condensation in upper plenum, resulting in lower steam binding and higher core cooling during early reflood phase. This indicates the conservatism of UPI against CLI during early reflood phase. (3) The good core-cooling capability was confirmed under UPI and BE conditions. (author)

  17. Study of top reflooding in case of severe accident and in particular oxidation of Uranium, Zirconium, Oxygen melts

    International Nuclear Information System (INIS)

    Brunet-Thibault, E.

    2006-12-01

    In 1979, the Three Mile Island (TMI) accident occurred in United States and accelerated research activities in the field of severe accidents. Severe accident management procedures imply massive water injections to flood the core. The work of this thesis bent principally over this reflooding. The first part of the study concerns the core oxidation enhancement during the reflooding phase which leads to a rough increase of the concentration of burnable hydrogen in the containment. This is why the study carried on the analysis of the contribution of the oxidation of U-Zr-O mixtures, towards the total production of hydrogen during reflooding. In the second part, the study concerns top flooding modelling i.e.: with injection of water in the hot legs. Here, we attempted to define bases and realize a model allowing to describe this type of reflooding. These models were validated on the simulation of the parameter with MAAP4 code. (author)

  18. Mengukur Politisasi Agama dalam Ruang Publik: Komunikasi SARA dalam Perdebatan Rational Choice Theory

    Directory of Open Access Journals (Sweden)

    Mohammad Supriyadi

    2015-12-01

    Full Text Available Tulisan ini memberikan gambaran runtuhnya pengaruh isu primordialisme di ruang publik dan digantikan dengan kearifan konvensional. Penelitian ini mengambil aspek pengaruh isu SARA pada aspek rasionalitas pemilih. Penulis menemukan beberapa aspek yang mendukung kesimpulan penelitian, antara lain; bahwa isu SARA tidak terlalu direspek pemilih rasional. Pemilih rasional lebih melihat masalah yang ada dan mengevaluasi kinerja pemerintahan sebelumnya. Di lain pihak, emosi antusias terhadap isu etnisitas akan memantabkan pilihan politik terhadap pemilih etnis minoritas, sebagai bentuk penguatan komunitas. Dengan menggunakan pendekatan teori pilihan rasional (rational choice theory, penulis melihat bahwa komunikasi politik yang dibangun melalui isu SARA di ruang publik dalam kehidupan masyarakat modern, tidak lagi mampu memengaruhi pemilih rasional. Pemilih rasional (rational choice, menentukan pilihan berdasarkan pada keuntungan yang diperolehnya (maximizing benefit. Dalam faktor ini sikap pemilih lebih dipengaruhi karakteristik dan track record kandidat.

  19. Concurrent software system design supported by SARA at the age of one

    Energy Technology Data Exchange (ETDEWEB)

    Campos, I.M.; Estrin, G.

    A multilevel modeling method suitable for the design of concurrent hardware or software systems is presented. The methodology is requirement driven and uses tools incorporated in a programming system called SARA (Systems ARchitect's Apprentice). Both top-down refinement and bottom-up abstraction are supported. The design of an asynchronous sender-receiver illustrates the key steps in going smoothly from programing in the large to programing in the small or actual code. The same methodology can be used to design hardware systems by applying different pragmatics from those proposed for software systems. SARA consists of a set of interactive tools implemented both at UCLA and also on the MIT-Multics system. Although SARA continues in long-term development, completed design tools are accessible for experimentation by authorized users at either location via the ARPANET. 9 figures, 2 tables.

  20. ESTETIKA TARIAN SARA DOUDA DALAM MASYARAKAT ADAT LOLI (SEBUAH PENDEKATAN LINGUISTIK KEBUDAYAAN

    Directory of Open Access Journals (Sweden)

    Sulistyastuti Sutomo

    2015-01-01

    Full Text Available Not only does art   have   self-fullfillment, but  it also has axiological  benefits both socially, culturally, religiously, and economiclally.  So does Sara Douda dance.  Sara Douda aesthetics  is first contained  in its whole dance movements. In addition, it  can also be found in the whole dance equipments.  Moreover,  this dance aesthetics  may  also be contained in the verbal symbols in the speech forms  prior to the dance performance. However,  both verbal and non-verbal aesthetical forms are incorporated by the pieces of socio-cultural and  religious values in the Loli community about  their honoring their ancestors,  having social harmony, and  highly respecting each other among the community members. This study uses a cultural linguistic approach to find out and to review the aesthetics of Sara Douda dance.   Seni memang memiliki kepenuhan dalam dirinya sendiri. Tetapi ia juga sekaligus punya faedah aksiologis, baik secara sosial, kultural, religius maupun secara ekonomis. Tarian Sara Douda pun demikian. Estetika Sara Douda pertama-tama ada dalam semua gerak tariannya. Juga dalam seluruh perlengkapan tarian tersebut. Bukan itu saja, estetika tarian ini juga ada dalam simbol-simbol verbal berupa tuturan menjelang tarian. Tetapi baik bentuk-bentuk estetisasi nonverbal maupun verbal, sama-sama disatukan oleh kepingan-kepingan nilai-nilai sosio-kultural dan religius masyarakat Loli tentang penghormatan kepada leluhur, tentang harmoni sosial, dan tentang penghargaan yang tinggi terhadap satu sama lain. Penelitian ini menggunakan pendekatan linguistik kebudayaan demi menemukan dan menelaah estetika dalam tarian Sara Douda

  1. Criterion for the onset of quench for low-flow reflood

    International Nuclear Information System (INIS)

    Hsu, Y.Y.; Young, M.W.

    1982-07-01

    This study provides a criterion for the onset of quench for low flow reflood. The criterion is a combination of two conditions: T/sub clad/ < T/sub limiting quench/ where T = Temperature, and α < 0.95 where α = void fraction. This criterion was obtained by examining temperature data from tests simulating PWR reflood, such as FLECHT, THTF, PBF, CCTF, and FEBA tests, with void fraction data from CCTF, FEBA, and FLECHT low flood tests. The data show that quenching initiated at α = 0.95 and that the majority of quench occurred at void fractions near 0.85. The results show that rods can be completely quenched by entrained droplets even if the collapsed liquid level does not advance. A thorough discussion of the analysis which supports this quench criterion is given in the text of this report

  2. Numerical analysis of reflood simulation based on a mechanistic, best-estimate, approach by KREWET code

    International Nuclear Information System (INIS)

    Chun, Moon-Hyun; Jeong, Eun-Soo

    1983-01-01

    A new computer code entitled KREWET has been developed in an effort to improve the accuracy and applicability of the existing reflood heat transfer simulation computer code. Sample calculations for temperature histories and heat transfer coefficient are made using KREWET code and the results are compared with the predictions of REFLUX, QUEN1D, and the PWR-FLECHT data for various conditions. These show favourable agreement in terms of clad temperature versus time. For high flooding rates (5-15cm/sec) and high pressure (∼413 Kpa), reflood predictions are reasonably well predicted by KREWET code as well as with other codes. For low flooding rates (less than ∼4cm/sec) and low pressure (∼138Kpa), predictions show considerable error in evaluating the rewet position versus time. This observation is common to all the codes examined in the present work

  3. Numerical analysis for reflood simulation based on a mechanistic, best-estimate, approach by KREWET code

    International Nuclear Information System (INIS)

    Chun, M.-H.; Jeong, E.-S.

    1983-01-01

    A new computer code entitled KREWET has been developed in an effort to improve the accuracy and applicability of the existing reflood heat transfer simulation computer code. Sample calculations for temperature histories and heat transfer coefficient are made using KREWET code and the results are compared with the predictions of REFLUX, QUENID, and the PWR-FLECHT data for various conditions. These show favorable agreement in terms of clad temperature versus time. For high flooding rates (5-15cm/sec) and high pressure (approx. =413 Kpa), reflood predictions are reasonably well predicted by KREWET code as well as with other codes. For low flooding rates (less than approx. =4cm/sec) and low pressure (approx. =138 Kpa), predictions show considerable error in evaluating the rewet position versus time. This observation is common to all the codes examined in the present work

  4. Adaptation of Toodee-2 computer code for reflood analysis in Angra-1 reactor

    International Nuclear Information System (INIS)

    Praes, J.G.L.; Onusic Junior, J.

    1981-01-01

    A method of calculation the heat transfer coefficient used in Toodee-2 computer code for core reflood analysis in a loss of coolant accident, is presented. Preliminary results are presented with the use of heat transfer correlations based on FLECHT experiments adequate to a geometric arrangement such as 16 x 16 (Angra I). Optional calculations are suggested for the heat transfer coefficients when the cooling of fuel cladding by steam is used. (Author) [pt

  5. Study on thermo-hydraulic behavior during reflood phase of a PWR-LOCA

    International Nuclear Information System (INIS)

    Sugimoto, Jun

    1989-01-01

    This paper describes thermo-hydraulic behavior during the reflood phase in a postulated large-break loss-of-coolant accident (LOCA) of a PWR. In order to better predict the reflood transient in a nuclear safety analysis specific analytical models have been developed for, saturated film boiling heat transfer in inverted slung flow, the effect of grid spacers on core thermo-hydraulics, overall system thermo-hydraulic behavior, and the thermal response similarity between nuclear fuel rods and simulated rods. A heat transfer correlation has been newly developed for saturated film boiling based on a 4 x 4-rod experiment conducted at JAERI. The correlation provides a good agreement with existing experiments except in the vicinity of grid spacer locations. An analytical model has then been developed addressing the effect of grid spacers. The thermo-hydraulic behavior near the grid spacers was found to be predicted well with this model by considering the breakup of droplets in dispersed flow and water accumulation above the grid spacers in inverted slung flow. A system analysis code has been developed which couples the one-dimensional core and multi-loop primary system component models. It provides fairly good agreement with system behavior obtained in a large-scale integral reflood experiment with active primary system components. An analytical model for the radial temperature distribution in a rod has been developed and verified with data from existing experiments. It was found that a nuclear fuel rod has a lower cladding temperature and an earlier quench time than an electrically heated rod in a typical reflood condition. (author)

  6. The blowdown, refill and reflood phase during a LOCA. Survey of the main physical phenomena

    International Nuclear Information System (INIS)

    Reocreux, M.

    1980-05-01

    In this paper, the main physical phenomena occuring during a LOCA are reviewed. They are presented in a chronological order. For each phenomena, a detailed physical description is given followed by the review of the general modelling problems. For some of these phenomena, modelling details are given for critical flow, for two-phase flow and heat transfer, for critical heat flux and post critical heat flux heat transfer, for reflood and rewet heat transfer and in the survey on LOCA computation codes

  7. NCBI nr-aa BLAST: CBRC-SARA-01-1323 [SEVENS

    Lifescience Database Archive (English)

    Full Text Available CBRC-SARA-01-1323 ref|NP_001008277.1| rhodopsin [Canis lupus familiaris] ref|XP_855...608.1| PREDICTED: rhodopsin [Canis familiaris] emb|CAA70209.1| unnamed protein product [Canis familiaris] NP_001008277.1 2e-62 94% ...

  8. NCBI nr-aa BLAST: CBRC-SARA-01-1746 [SEVENS

    Lifescience Database Archive (English)

    Full Text Available CBRC-SARA-01-1746 ref|NP_001100989.1| non imprinted in Prader-Willi/Angelman syndro...me 1 homolog [Rattus norvegicus] gb|EDL86455.1| non imprinted in Prader-Willi/Angelman syndrome 1 homolog (human) (predicted) [Rattus norvegicus] NP_001100989.1 1e-113 80% ...

  9. NCBI nr-aa BLAST: CBRC-SARA-01-1273 [SEVENS

    Lifescience Database Archive (English)

    Full Text Available CBRC-SARA-01-1273 ref|ZP_00367235.1| competence locus E (comE3), putative [Campylob...acter coli RM2228] gb|EAL57139.1| competence locus E (comE3), putative [Campylobacter coli RM2228] ZP_00367235.1 0.001 28% ...

  10. NCBI nr-aa BLAST: CBRC-SARA-01-1089 [SEVENS

    Lifescience Database Archive (English)

    Full Text Available CBRC-SARA-01-1089 ref|ZP_00518636.1| Major facilitator superfamily [Crocosphaera watson...ii WH 8501] gb|EAM48279.1| Major facilitator superfamily [Crocosphaera watsonii WH 8501] ZP_00518636.1 1.3 32% ...

  11. NCBI nr-aa BLAST: CBRC-SARA-01-0322 [SEVENS

    Lifescience Database Archive (English)

    Full Text Available CBRC-SARA-01-0322 ref|ZP_01459778.1| conserved hypothetical protein [Stigmatella au...rantiaca DW4/3-1] gb|EAU69359.1| conserved hypothetical protein [Stigmatella aurantiaca DW4/3-1] ZP_01459778.1 5.2 34% ...

  12. NCBI nr-aa BLAST: CBRC-SARA-01-1488 [SEVENS

    Lifescience Database Archive (English)

    Full Text Available CBRC-SARA-01-1488 ref|ZP_01187451.1| conserved hypothetical protein [Bacillus weihenstep...hanensis KBAB4] gb|EAR73176.1| conserved hypothetical protein [Bacillus weihenstephanensis KBAB4] ZP_01187451.1 0.78 25% ...

  13. Reading, Laterality, and the Brain: Early Contributions on Reading Disabilities by Sara S. Sparrow

    Science.gov (United States)

    Fletcher, Jack M.; Morris, Robin D.

    2014-01-01

    Although best known for work with children and adults with intellectual disabilities and autism spectrum disorders, training in speech pathology and a doctorate in clinical psychology and neuropsychology was the foundation for Sara Sparrow's long-term interest in reading disabilities. Her first papers were on dyslexia and laterality, and the…

  14. NCBI nr-aa BLAST: CBRC-SARA-01-1967 [SEVENS

    Lifescience Database Archive (English)

    Full Text Available CBRC-SARA-01-1967 ref|ZP_00370594.1| Predicted DNA repair exonuclease [Campylobacter upsaliens...is RM3195] gb|EAL53370.1| Predicted DNA repair exonuclease [Campylobacter upsaliensis RM3195] ZP_00370594.1 0.047 31% ...

  15. NCBI nr-aa BLAST: CBRC-SARA-01-0488 [SEVENS

    Lifescience Database Archive (English)

    Full Text Available CBRC-SARA-01-0488 ref|YP_064024.1| sulfate permease (SulP) [Desulfotalea psychrophi...la LSv54] emb|CAG35017.1| probable sulfate permease (SulP) [Desulfotalea psychrophila LSv54] YP_064024.1 6.1 37% ...

  16. NCBI nr-aa BLAST: CBRC-SARA-01-0900 [SEVENS

    Lifescience Database Archive (English)

    Full Text Available CBRC-SARA-01-0900 ref|YP_898010.1| phosphatidylserine synthase [Francisella tularen...sis subsp. novicida U112] gb|ABK89256.1| phosphatidylserine synthase [Francisella tularensis subsp. novicida U112] YP_898010.1 3.0 27% ...

  17. NCBI nr-aa BLAST: CBRC-SARA-01-0144 [SEVENS

    Lifescience Database Archive (English)

    Full Text Available CBRC-SARA-01-0144 ref|YP_438659.1| alcohol dehydrogenase, zinc-containing [Burkholderia thailand...ensis E264] gb|ABC35120.1| alcohol dehydrogenase, zinc-containing [Burkholderia thailandensis E264] YP_438659.1 0.69 35% ...

  18. NCBI nr-aa BLAST: CBRC-SARA-01-0472 [SEVENS

    Lifescience Database Archive (English)

    Full Text Available CBRC-SARA-01-0472 sp|Q8NH41|OR4KF_HUMAN Olfactory receptor 4K15 dbj|BAC05798.1| sev...en transmembrane helix receptor [Homo sapiens] gb|EAW66492.1| olfactory receptor, family 4, subfamily K, member 15 [Homo sapiens] Q8NH41 1e-164 89% ...

  19. NCBI nr-aa BLAST: CBRC-SARA-01-1206 [SEVENS

    Lifescience Database Archive (English)

    Full Text Available CBRC-SARA-01-1206 sp|Q8NH41|OR4KF_HUMAN Olfactory receptor 4K15 dbj|BAC05798.1| sev...en transmembrane helix receptor [Homo sapiens] gb|EAW66492.1| olfactory receptor, family 4, subfamily K, member 15 [Homo sapiens] Q8NH41 1e-40 85% ...

  20. NCBI nr-aa BLAST: CBRC-SARA-01-1608 [SEVENS

    Lifescience Database Archive (English)

    Full Text Available CBRC-SARA-01-1608 ref|XP_513201.1| PREDICTED: cannabinoid receptor 2 (macrophage) i...soform 2 [Pan troglodytes] ref|XP_001166334.1| PREDICTED: cannabinoid receptor 2 (macrophage) isoform 1 [Pan troglodytes] XP_513201.1 1e-155 77% ...

  1. Indicators of induced subacute ruminal acidosis (SARA) in Danish Holstein cows

    DEFF Research Database (Denmark)

    Danscher, Anne Mette; Li, Shucong; Andersen, Pia H.

    2015-01-01

    BACKGROUND: The prevalence of subacute ruminal acidosis (SARA) in dairy cows is high with large impact on economy and welfare. Its current field diagnosis is based on point ruminal pH measurements by oral probe or rumenocentesis. These techniques are invasive and inaccurate, and better markers fo...

  2. NCBI nr-aa BLAST: CBRC-SARA-01-1419 [SEVENS

    Lifescience Database Archive (English)

    Full Text Available CBRC-SARA-01-1419 ref|YP_101126.1| hypothetical protein BF3850 [Bacteroides fragili...s YCH46] dbj|BAD50592.1| hypothetical protein [Bacteroides fragilis YCH46] YP_101126.1 5e-09 92% ...

  3. NCBI nr-aa BLAST: CBRC-SARA-01-1309 [SEVENS

    Lifescience Database Archive (English)

    Full Text Available CBRC-SARA-01-1309 ref|YP_001125845.1| hypothetical protein GTNG_1736 [Geobacillus thermoden...itrificans NG80-2] gb|ABO67100.1| Conserved hypothetical protein [Geobacillus thermodenitrificans NG80-2] YP_001125845.1 0.47 23% ...

  4. NCBI nr-aa BLAST: CBRC-SARA-01-0256 [SEVENS

    Lifescience Database Archive (English)

    Full Text Available CBRC-SARA-01-0256 ref|ZP_00739965.1| Integral membrane protein [Bacillus thuringiensis serovar israel...ensis ATCC 35646] gb|EAO55770.1| Integral membrane protein [Bacillus thuringiensis serovar israelensis ATCC 35646] ZP_00739965.1 1.3 24% ...

  5. NCBI nr-aa BLAST: CBRC-SARA-01-1804 [SEVENS

    Lifescience Database Archive (English)

    Full Text Available CBRC-SARA-01-1804 ref|ZP_00743402.1| Sensory box/GGDEF family protein [Bacillus thuringiensis serovar israel...ensis ATCC 35646] gb|EAO52327.1| Sensory box/GGDEF family protein [Bacillus thuringiensis serovar israelensis ATCC 35646] ZP_00743402.1 0.20 36% ...

  6. NCBI nr-aa BLAST: CBRC-SARA-01-0522 [SEVENS

    Lifescience Database Archive (English)

    Full Text Available CBRC-SARA-01-0522 ref|YP_001499570.1| Peptidyl-tRNA hydrolase [Rickettsia massiliae... MTU5] gb|ABV85023.1| Peptidyl-tRNA hydrolase [Rickettsia massiliae MTU5] YP_001499570.1 4.7 36% ...

  7. NCBI nr-aa BLAST: CBRC-SARA-01-1578 [SEVENS

    Lifescience Database Archive (English)

    Full Text Available CBRC-SARA-01-1578 ref|NP_001077100.1| cOR52N9 olfactory receptor family 52 subfamily N-like [Canis lupus... familiaris] gb|ABO36681.1| 52N9 olfactory receptor protein [Canis lupus familiaris] NP_001077100.1 1e-146 78% ...

  8. NCBI nr-aa BLAST: CBRC-SARA-01-1099 [SEVENS

    Lifescience Database Archive (English)

    Full Text Available CBRC-SARA-01-1099 ref|YP_001337495.1| hypothetical protein KPN_03841 [Klebsiella pneumoniae subsp. pneumonia...e MGH 78578] gb|ABR79228.1| hypothetical protein KPN_03841 [Klebsiella pneumoniae subsp. pneumoniae MGH 78578] YP_001337495.1 0.93 29% ...

  9. NCBI nr-aa BLAST: CBRC-SARA-01-0489 [SEVENS

    Lifescience Database Archive (English)

    Full Text Available CBRC-SARA-01-0489 ref|ZP_01035526.1| exopolysaccharide biosynthesis domain protein [Rose...ovarius sp. 217] gb|EAQ25691.1| exopolysaccharide biosynthesis domain protein [Roseovarius sp. 217] ZP_01035526.1 1.0 26% ...

  10. Konflik SARA pada Pilkada DKI Jakarta di Grup WhatsApp dengan Anggota Multikultural

    Directory of Open Access Journals (Sweden)

    Tiara Kharisma

    2017-12-01

    Full Text Available Keanekaragaman SARA di Indonesia melahirkan masyarakat multikultural. Dalam kehidupannya, komunikasi antarbudaya tidak dapat dihindarkan. Salah satu medium dalam melakukan komunikasi antarbudaya adalah media sosial. Pada masyarakat multikultural isu SARA menjadi faktor utama penyebab terjadinya konflik. Di Pilkada DKI Jakarta 2017, isu SARA di grup WhatsApp marak menyebar termasuk anggota grup yang heterogen. Penelitian ini bertujuan untuk mengetahui pengelolaan konflik isu SARA pada Pilkada DKI Jakarta 2017 di grup WhatsApp dengan anggota multikultural. Penelitian ini menggunakan pendekatan kualitatif dengan teknik pengumpulan data melalui wawancara dan studi literatur. Dalam membahas penelitian ini, peneliti menggunakan kerangka teori manajemen konflik dari Martin, J. N. dan Nakayama. Hasil penelitian menunjukkan bahwa konflik terjadi karena ada anggota grup menyampaikan pesan bukan berangkat dari kesamaan anggota grup, yakni kepentingan dan tujuan awal dibentuknya grup. Pesan disebarkan dengan menganggap wujud pembelaan terhadap suatu agama. Ketika konflik terjadi, strategi pengelolaan konflik yang diterapkan adalah strategi mengompromikan (compromising dan menghindar (avoiding. Dalam grup terdapat anggota yang berperan sebagai cultural brokers.

  11. NCBI nr-aa BLAST: CBRC-SARA-01-1753 [SEVENS

    Lifescience Database Archive (English)

    Full Text Available CBRC-SARA-01-1753 ref|YP_001476411.1| amino acid permease-associated region [Serratia proteam...aculans 568] gb|ABV39283.1| amino acid permease-associated region [Serratia proteamaculans 568] YP_001476411.1 0.83 35% ...

  12. NCBI nr-aa BLAST: CBRC-SARA-01-0771 [SEVENS

    Lifescience Database Archive (English)

    Full Text Available CBRC-SARA-01-0771 ref|NP_001029253.1| progestin and adipoQ receptor family member V...II [Rattus norvegicus] gb|AAY67652.1| progestin membrane receptor alpha [Rattus norvegicus] NP_001029253.1 1e-167 82% ...

  13. NCBI nr-aa BLAST: CBRC-SARA-01-0771 [SEVENS

    Lifescience Database Archive (English)

    Full Text Available CBRC-SARA-01-0771 ref|NP_001033642.1| progestin and adipoQ receptor family member V...II [Bos taurus] gb|AAI11285.1| Progestin and adipoQ receptor family member VII [Bos taurus] NP_001033642.1 1e-180 87% ...

  14. Implementation of JAERI's reflood model into TRAC-PF1/MOD1 code

    International Nuclear Information System (INIS)

    Akimoto, Hajime; Ohnuki, Akira; Murao, Yoshio

    1993-02-01

    Selected physical models of REFLA code, that is a reflood analysis code developed at JAERI, were implemented into the TRAC-PF1/MOD1 code in order to improve the predictive capability of the TRAC-PF1/MOD1 code for the core thermal hydraulic behaviors during the reflood phase in a PWR LOCA. Through comparisons of physical models between both codes, (1) Murao-Iguchi void fraction correlation, (2) the drag coefficient correlation acting to drops, (3) the correlation for wall heat transfer coefficient in the film boiling regime, (4) the quench velocity correlation and (5) heat transfer correlations for the dispersed flow regime were selected from the REFLA code to be implemented into the TRAC-PF1/MOD1 code. A method for the transformation of the void fraction correlation to the equivalent interfacial friction model was developed and the effect of the transformation method on the stability of the solution was discussed. Through assessment calculation using data from CCTF (Cylindrical Core Test Facility) flat power test, it was confirmed that the predictive capability of the TRAC code for the core thermal hydraulic behaviors during the reflood can be improved by the implementation of selected physical models of the REFLA code. Several user guidelines for the modified TRAC code were proposed based on the sensitivity studies on fluid cell number in the hydraulic calculation and on node number and effect of axial heat conduction in the heat conduction calculation of fuel rod. (author)

  15. Experimental study of effect of initial clad temperature on reflood phenomena during PWR-LOCA

    International Nuclear Information System (INIS)

    Sugimoto, Jun; Murao, Yoshio

    1983-01-01

    Integral system tests with the Cylindrical Core Test Facility (CCTF) were performed to investigate the effect of the initial clad temperature on the reflood phenomena in a PWR-LOCA. The initial peak clad temperatures in these three tests were 871, 968 and 1,047K, respectively. The feedback of the system on the core inlet mass flow rate was estimated to be little influenced by the variation of the initial clad temperature except for the first 20s in the transient. The observed temperature rise from the reflood initiation was lower with the higher initial clad temperature. This qualitatively agreed with the results of the small scale forced feed reflood experiments. However, the magnitude of the temperature rise in CCTF was significantly low due to the high initial core inlet mass flow rate. Also observed were the multi-dimensional thermal behaviors for the three cases in the CCTF wide core. The analysis codes REFLA and TRAC reasonably predicted the effect of the initial clad temperature on the core thermo-hydraulics under the simulated core inlet flow conditions. However, the calculated temperature rise of the maximum powered rod based on the one-dimensional core analysis was higher than that of the average powered rod, which contradicts the tendency observed in CCTF tests. (author)

  16. Calculations of flow oscillations during reflood using RELAP4/MOD6

    International Nuclear Information System (INIS)

    Chen, Y.S.; Fischer, S.R.; Sullivan, L.H.

    1979-01-01

    RELAP4/MOD6 is an analytical computer code which can be used for best-estimate analysis of LWR reactor system blowdown and reflood response to a postulated LOCA. In this study, flow oscillations in the PKL reflood test K5A were investigated using RELAP4/MOD6. Both calculated and measured oscillations exhibited transient characteristics of density-wave and pressure-drop oscillations. The calculated average core mixture level rising rate agrees closely with the test data. Several mechanisms which appear to be responsible for initiation and continuation of calculated or experimental reflood flow oscillations are (a) the coupling between the vapor generation in the core channel and the U-tube geometrical arrangement of a downcomer and a heated core; (b) the inherent low core inlet resistance and the high system outlet resistance; (c) the dependence of heat transfer rate on mass flow rate especially in the dispersed flow ially in the dispersed flow regime; (d) the amount of the liquid entrainment fraction of the heated core channel

  17. Impacts of Mesopotamian wetland re-flooding on the lipid biomarker distributions in sediments

    Science.gov (United States)

    Rushdi, Ahmed I.; DouAbul, Ali A. Z.; Al-Maarofi, Sama S.; Simoneit, Bernd R. T.

    2018-03-01

    Shallow sediment core samples from two locales in the Mesopotamian marshlands of Iraq were analyzed to characterize the extractable organic (lipid) compounds, and their sources and distributions after hydrological restoration by re-flooding of the marshes. Dried samples were extracted with a dichloromethane/methanol mixture before analysis by gas chromatography-mass spectrometry (GC-MS). The major compounds were n-alkanes, fatty acids and alcohols, steroids, terpenoids, hopanes, steranes, unresolved complex mixture (UCM), and plasticizers. The lipid compounds in Kurmashia (Al-Hammar marshes) were generally higher in concentration than in Abu Zirig (Central marshes), and decreased with core depths for both sites. This concentration decrease with core depth is attributed to transformation, biodegradation and variable input processes. The distribution patterns of the lipids in the sediment cores indicated that the Abu Zirig area was drier than Kurmashia before the re-flooding process. Furthermore, the concentration of the compounds in the surface sediment the Abu Zirig core was as high and similar to that in Kurmashia, reflecting the re-flooding impacts on the marsh and the revival of the wetland. The major sources of these lipids were from natural terrestrial vegetation (35-66% for Abu Zirig; 40-49% for Kurmashia), microbial (plankton) residues and bacteria (27-52% for Abu Zirig; 39-43% for Kurmashia), with a minor contribution from anthropogenic sources including plastic wastes and petroleum (6-13% for Abu Zirig; 9-18% for Kurmashia).

  18. Evaluation report on CCTF Core-II reflood test C2-16 (Run 76)

    International Nuclear Information System (INIS)

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

    1987-03-01

    This report presents the result of the upper plenum injection (UPI) test C2-16 (Run 76), which was conducted on October 23, 1984, with the Cylindrical Core Test Facility (CCTF) at Japan Atomic Energy Research Institute (JAERI). The CCTF is a 1/21.4 scale model of a 1,100 MWe PWR with four loop active components to provide information on the system and core thermo-hydrodynamics during reflood. The objectives of the test are to investigate the reflood phenomena with single failure UPI condition and to investigate the effect of the asymmetry of UPI on the reflood phenomena. The test was performed with an asymmetric UPI condition at the injection rate simulating single failure of LPCI pumps. It was observed that, (1) a UPI test simulating no LPCI pump failure gave the slightly lower peak clad temperature than a UPI test simulating single LPCI pump failure, indicating that single LPCI pump failure assumption is conserrative for UPI condition, and (2) an asymmetric UPI lead to a higher core water accumulation and then a higher heat transfer coefficient, resultantly a lower peak clad temperature than a symmetric UPI, indicating that asymmetric UPI does not lead to a poorer core cooling than symmetric UPI. (author)

  19. System pressure effects on reflooding phenomena observed in the SCTF Core-I forced flooding tests

    International Nuclear Information System (INIS)

    Adachi, Hiromichi; Sudo, Yukio; Sobajima, Makoto; Iwamura, Takamichi; Osakabe, Masahiro; Ohnuki, Akira; Abe, Yutaka

    1983-06-01

    The Slab Core Test Facility was constructed to investigate two-dimensional thermo-hydrodynamics in the core and the interaction in fluid behavior between the core and the upper plenum during the last part of blowdown, refill and reflood phases of a posturated loss-of-coolant accident (LOCA) of a pressurized water reactor (PWR). The present report described the analytical results on the effects of system pressure on reflooding phenomena observed in Tests Sl-SH2, Sl-01 and Sl-02 which are belonging to the SCTF Core-I forced-feed reflooding test series. Nominal system pressures in these tests are 0.4, 0.2 and 0.15 MPa, respectively. By comparison among the data of these three tests, the effects of system pressure on thermo-hydrodynamic behavior in the pressure vessel including the core and the primary coolant loops of the SCTF can be clarified under the forced flooding condition. Major items investigated in the present report are (1) overall temperature behaviors in the core, (2) change of heat transfer coefficient and heat flux at the rod surface before the quench, (3) two-dimensional thermo-hydrodynamic behaviors in the core and upper plenum and (4) hot leg carryover. (author)

  20. Sensitive analysis and modifications to reflood-related constitutive models of RELAP5

    International Nuclear Information System (INIS)

    Li Dong; Liu Xiaojing; Yang Yanhua

    2014-01-01

    Previous system code calculation reveals that the cladding temperature is underestimated and quench front appears too early during reflood process. To find out the parameters shows important effect on the results, sensitive analysis is performed on parameters of constitutive physical models. Based on the phenomenological and theoretical analysis, four parameters are selected: wall to vapor film boiling heat transfer coefficient, wall to liquid film boiling heat transfer coefficient, dry wall interfacial friction coefficient and minimum droplet diameter. In order to improve the reflood simulation ability of RELAP5 code, the film boiling heat transfer model and dry wall interfacial friction model which are corresponding models of those influential parameters are studied. Modifications have been made and installed into RELAP5 code. Six tests of FEBA are simulated by RELAP5 to study the predictability of reflood-related physical models. A dispersed flow film boiling heat transfer (DFFB) model is applied when void fraction is above 0.9. And a factor is multiplied to the post-CHF drag coefficient to fit the experiment better. Finally, the six FEBA tests are calculated again so as to assess the modifications. Better results are obtained which prove the advantage of the modified models. (author)

  1. Investigations of the reflood-phase after a loss-of-coolant-accident of an advanced pressurized water reactor (APWR)

    International Nuclear Information System (INIS)

    Schumann, S.; Oldekop, W.

    1983-01-01

    Differences between a high converting advanced pressurized-water reactor (APWR) and a conventional PWR, which are relevant to the reflood-phase after LOCA are presented. The used code and its verification by PWR-reflood experiments is explained. Comparative calculations for APWR and PWR with several conservative assumptions for example cold-leg-injection only, yield nearly the same maximum midplane-temperatures for the average-channel. For the APWR, however, the upper half of the rod shows higher temperatures. Quenchfront and core-water-level increase more slowly. The differences in the reflood-thermohydraulics are analysed in detail. A conservative hot-channel calculation shows maximum temperatures of about 920 0 C. Finally the influence of conservative assumptions is described and the necessity of experiments pointed out. (orig.)

  2. Experiment data report for semiscale MOD-1 tests S-03-A, S-03-B, S-03-C, and S-03-D (reflood heat transfer tests)

    International Nuclear Information System (INIS)

    1976-05-01

    Recorded test data are presented for Tests S-03-A, S-03-B, S-03-C, and S-03-D of the Semiscale Mod-1 reflood heat transfer series (Test Series 3). The tests conducted in this series are separate effects core reflood tests performed to determine the reflood heat transfer characteristics of the 5.5 foot Mod-1 rod bundle. Tests S-03-A through S-03-D were forced-feed reflood tests in which the reflood rate was held constant during each test. The tests were conducted to investigate the effects on system response resulting from variations in operating conditions of pressure, temperature, core power, reflood coolant, subcooling, and peak heater rod thermocouple temperature at reflood initiation. Test S-03-A was conducted from an initial system temperature of about 230 0 F at a pressure of 20 psia. Tests S-03-B through S-03-D were conducted from an initial system temperature of about 290 0 F at a pressure of 60 psia. In all four tests, reflood coolant was injected directly into the core barrel by means of a specially designed core inlet manifold. The electrically heated core was used in the pressure vessel to simulate the effects of a nuclear core during reflood. All four tests were conducted with a flat radial power profile. During reflood, core power was reduced from the initial level according to the American Nuclear Society (ANS) decay heat curve plus 20 percent for pressurized water reactor (PWR) core decay heat. The cold leg broken loop piping was open to the pressure suppression system (PSS). A separate steam supply system connected to the PSS was controlled to maintain constant pressure during the tests

  3. Transferring generic SARA/OSHA training to US Department of Energy facilities

    International Nuclear Information System (INIS)

    White, A.; McKinley, T.

    1989-01-01

    The Technical Resources and Training Section staff at Oak Ridge National Laboratory have developed three extensive training programs for hazardous waste treatment, storage, and disposal facility workers a required by SARA/OSHA, 29 CFR 1910.120. The ORNL program is widely recognized as one of the best in the DOE system. ORNL and ORAU, who manages the Training Resources and Data Exchange (TRADE) network for DOE, entered into as cooperative relationship to respond to the many requests from DOE contractors for copies of the ORNL training materials. This discussion will describe the ORNL program and the process of turning it into a series of generic tools which can be used by additional DOE facilities to meet the training requirements established by SARA/OSHA, 20 CFR 1910.120. The speakers will describe how the materials are being used by DOE facilities as well as plans for additional resources to be developed through TRADE. 5 refs

  4. SarA is a negative regulator of Staphylococcus epidermidis biofilm formation

    DEFF Research Database (Denmark)

    Martin, Christer; Heinze, C.; Busch, M.

    2012-01-01

    Biofilm formation is essential for Staphylococcus epidermidis pathogenicity in implant-associated infections. Nonetheless, large proportions of invasive S. epidermidis isolates fail to show accumulative biofilm growth in vitro. We here tested the hypothesis that this apparent paradox is related...... virulence. Genetic analysis revealed that inactivation of sarA induced biofilm formation via over-expression of the giant 1 MDa extracellular matrix binding protein (Embp), serving as an intercellular adhesin. In addition to Embp, increased extracellular DNA (eDNA) release significantly contributed...... to biofilm formation in mutant 1585ΔsarA. Increased eDNA amounts indirectly resulted from up-regulation of metalloprotease SepA, leading to boosted processing of major autolysin AtlE, in turn inducing augmented autolysis and release of chromosomal DNA. Hence, this study identifies sarA as a negative...

  5. NCBI nr-aa BLAST: CBRC-SARA-01-0756 [SEVENS

    Lifescience Database Archive (English)

    Full Text Available CBRC-SARA-01-0756 gb|AAW70053.1| MRGX2 [Homo sapiens] gb|AAW70054.1| MRGX2 [Homo sapiens...] gb|AAW70055.1| MRGX2 [Homo sapiens] gb|AAW70070.1| MRGX2 [Homo sapiens] gb|AAW70083.1| MRGX2 [Homo sapiens] AAW70053.1 1e-66 52% ...

  6. NCBI nr-aa BLAST: CBRC-SARA-01-1400 [SEVENS

    Lifescience Database Archive (English)

    Full Text Available CBRC-SARA-01-1400 gb|AAW70053.1| MRGX2 [Homo sapiens] gb|AAW70054.1| MRGX2 [Homo sapiens...] gb|AAW70055.1| MRGX2 [Homo sapiens] gb|AAW70070.1| MRGX2 [Homo sapiens] gb|AAW70083.1| MRGX2 [Homo sapiens] AAW70053.1 4e-34 52% ...

  7. NCBI nr-aa BLAST: CBRC-SARA-01-1746 [SEVENS

    Lifescience Database Archive (English)

    Full Text Available CBRC-SARA-01-1746 ref|NP_653200.2| non-imprinted in Prader-Willi/Angelman syndrome ...1 [Homo sapiens] sp|Q7RTP0|NIPA1_HUMAN Non-imprinted in Prader-Willi/Angelman syndrome region protein 1 tpg|...DAA01477.1| TPA_exp: non-imprinted in Prader-Willi/Angelman syndrome 1 [Homo sapiens] NP_653200.2 1e-113 81% ...

  8. Reading, Laterality, and the Brain: Early Contributions on Reading Disabilities by Sara S. Sparrow

    OpenAIRE

    Fletcher, Jack M.; Morris, Robin D.

    2014-01-01

    Although best known for work with children and adults with intellectual disabilities and autism spectrum disorders, training in speech pathology and a doctorate in clinical psychology and neuropsychology was the foundation for Sara Sparrow’s long-term interest in reading disabilities. Her first papers were on dyslexia and laterality, and the maturational lag theory of developmental dyslexia proposed with Paul Satz, her mentor. The research program that emerged from this work had a wide impact...

  9. NCBI nr-aa BLAST: CBRC-SARA-01-1488 [SEVENS

    Lifescience Database Archive (English)

    Full Text Available CBRC-SARA-01-1488 ref|YP_001474562.1| DNA internalization-related competence protei...n ComEC/Rec2 [Shewanella sediminis HAW-EB3] gb|ABV37434.1| DNA internalization-related competence protein ComEC/Rec2 [Shewanella sediminis HAW-EB3] YP_001474562.1 1.7 33% ...

  10. Identification of Differentially Expressed Proteins in Liver in Response to Subacute Ruminal Acidosis (SARA Induced by High-concentrate Diet

    Directory of Open Access Journals (Sweden)

    X. Y. Jiang

    2014-08-01

    Full Text Available The aim of this study was to evaluate protein expression patterns of liver in response to subacute ruminal acidosis (SARA induced by high-concentrate diet. Sixteen healthy mid-lactating goats were randomly divided into 2 groups and fed either a high-forage (HF diet or a high-concentrate (HC diet. The HC diet was expected to induce SARA. After ensuring the occurrence of SARA, liver samples were collected. Proteome analysis with differential in gel electrophoresis technology revealed that, 15 proteins were significantly modulated in liver in a comparison between HF and HC-fed goats. These proteins were found mainly associated with metabolism and energy transfer after identified by matrix-assisted laser desorption ionization/time of flight. The results indicated that glucose, lipid and protein catabolism could be enhanced when SARA occurred. It prompted that glucose, lipid and amine acid in the liver mainly participated in oxidation and energy supply when SARA occurred, which possibly consumed more precursors involved in milk protein and milk fat synthesis. These results suggest new candidate proteins that may contribute to a better understanding of the mechanisms that mediate liver adaptation to SARA.

  11. Effect of Uncertainty Parameters in Blowdown and Reflood Models for OPR1000 LBLOCA Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Huh, Byung Gil; Jin, Chang Yong; Seul, Kwangwon; Hwang, Taesuk [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2014-05-15

    KINS(Korea Institute of Nuclear Safety) has also performed the audit calculation with the KINS Realistic Evaluation Methodology(KINS-REM) to confirm the validity of licensee's calculation. In the BEPU method, it is very important to quantify the code and model uncertainty. It is referred in the following requirement: BE calculations in Regulatory Guide 1.157 - 'the code and models used are acceptable and applicable to the specific facility over the intended operating range and must quantify the uncertainty in the specific application'. In general, the uncertainty of model/code should be obtained through the data comparison with relevant integral- and separate-effect tests at different scales. However, it is not easy to determine these kinds of uncertainty because of the difficulty for evaluating accurately various experiments. Therefore, the expert judgment has been used in many cases even with the limitation that the uncertainty range of important parameters can be wide and inaccurate. In the KINS-REM, six heat transfer parameters in the blowdown phase have been used to consider the uncertainty of models. Recently, MARS-KS code was modified to consider the uncertainty of the five heat transfer parameters in the reflood phase. Accordingly, it is required that the uncertainty range for parameters of reflood models is determined and the effect of these ranges is evaluated. In this study, the large break LOCA (LBLOCA) analysis for OPR1000 was performed to identify the effect of uncertainty parameters in blowdown and reflood models.

  12. SARAS 2 Constraints on Global 21 cm Signals from the Epoch of Reionization

    Science.gov (United States)

    Singh, Saurabh; Subrahmanyan, Ravi; Udaya Shankar, N.; Sathyanarayana Rao, Mayuri; Fialkov, Anastasia; Cohen, Aviad; Barkana, Rennan; Girish, B. S.; Raghunathan, A.; Somashekar, R.; Srivani, K. S.

    2018-05-01

    Spectral distortions in the cosmic microwave background over the 40–200 MHz band are imprinted by neutral hydrogen in the intergalactic medium prior to the end of reionization. This signal, produced in the redshift range z = 6–34 at the rest-frame wavelength of 21 cm, has not been detected yet; and a poor understanding of high-redshift astrophysics results in a large uncertainty in the expected spectrum. The SARAS 2 radiometer was purposely designed to detect the sky-averaged 21 cm signal. The instrument, deployed at the Timbaktu Collective (Southern India) in 2017 April–June, collected 63 hr of science data, which were examined for the presence of the cosmological 21 cm signal. In our previous work, the first-light data from the SARAS 2 radiometer were analyzed with Bayesian likelihood-ratio tests using 264 plausible astrophysical scenarios. In this paper we reexamine the data using an improved analysis based on the frequentist approach and forward-modeling. We show that SARAS 2 data reject 20 models, out of which 15 are rejected at a significance >5σ. All the rejected models share the scenario of inefficient heating of the primordial gas by the first population of X-ray sources, along with rapid reionization. Joint Astronomy Program, Indian Institute of Science, Bangalore 560012, India.

  13. The Remote Observatories of the Southeastern Association for Research in Astronomy (SARA)

    Science.gov (United States)

    Keel, William C.; Oswalt, Terry; Mack, Peter; Henson, Gary; Hillwig, Todd; Batcheldor, Daniel; Berrington, Robert; De Pree, Chris; Hartmann, Dieter; Leake, Martha; Licandro, Javier; Murphy, Brian; Webb, James; Wood, Matt A.

    2017-01-01

    We describe the remote facilities operated by the Southeastern Association for Research in Astronomy (SARA) , a consortium of colleges and universities in the US partnered with Lowell Observatory, the Chilean National Telescope Allocation Committee, and the Instituto de Astrofísica de Canarias. SARA observatories comprise a 0.96 m telescope at Kitt Peak, Arizona; one of 0.6 m aperture on Cerro Tololo, Chile; and the 1 m Jacobus Kapteyn Telescope at the Roque de los Muchachos, La Palma, Spain. All are operated using standard VNC or Radmin protocols communicating with on-site PCs. Remote operation offers considerable flexibility in scheduling, allowing long-term observational cadences difficult to achieve with classical observing at remote facilities, as well as obvious travel savings. Multiple observers at different locations can share a telescope for training, educational use, or collaborative research programs. Each telescope has a CCD system for optical imaging, using thermoelectric cooling to avoid the need for frequent local service, and a second CCD for offset guiding. The Arizona and Chile telescopes also have fiber-fed echelle spectrographs. Switching between imaging and spectroscopy is very rapid, so a night can easily accommodate mixed observing modes. We present some sample observational programs. For the benefit of other groups organizing similar consortia, we describe the operating structure and principles of SARA, as well as some lessons learned from almost 20 years of remote operations.

  14. System Analysis and Risk Assessment System (SARA), Version 4.0

    International Nuclear Information System (INIS)

    Russell, K.D.; Sattison, M.B.; Skinner, N.L.; Stewart, H.D.; Wood, S.T.

    1992-02-01

    This NUREG is the reference manual for the System Analysis and Risk Assessment (SARA) System Version 4.0, a microcomputer-based system used to analyze the safety issues of a family [i.e., a power plant, a manufacturing facility, any facility on which a probabilistic risk assessment (PRA) might be performed]. The SARA data base contains PRA data for the dominant accident sequences of a family and descriptive information about the family including event trees, fault trees, and system model diagrams. The number of facility data bases that can be accessed is limited only by the amount of disk storage available. To simulate changes to family systems, SARA users change the failure rates of initiating and basic events and/or modify the structure of the cut sets that make up the event trees, fault trees, and systems. The user then evaluates the effects of these changes through the recalculation of the resultant accident sequence probabilities and importance measures. The results are displayed in tables and graphs

  15. Contribution to the modelling of flows and heat transfers during the reflooding phase of a PWR core

    International Nuclear Information System (INIS)

    Colas, D.

    1984-01-01

    This thesis contributes to modelise thermohydraulic phenomena occuring in a pressurized water nuclear reactor core during the reflood phase of a LOCA. The reference accident and phenomena occuring during reflooding are described as well as flow regime and heat transfer proposed models. With these models, we developed a code to compute fluid conditions and fuel rods temperatures in a reactor core chanel. In order to test this code, results of computation are compared with experiments (FLECHT Skewed Tests) and a conclusion is drawn [fr

  16. Flow and heat transfer thermohydraulic modelisation during the reflooding phase of a P.W.R.'s core

    International Nuclear Information System (INIS)

    Raymond, Patrick

    1978-04-01

    Some generalities about L.O.C.A. are first recalled. The French experimental studies about Emergency Core Cooling System are briefly described. The different heat transfer mechanisms to take into account, according to the flow pattern in the dry zone, and the correlations or methods to calculate them, are defined. Then the Thermohydraulic code computer: FLIRA, which describe the reflooding phase, and a modelisation taking into account the different flow patterns are setted. A first interpretation of ERSEC experiments with a tubular test section shows that it is possible, with this modelisation and some classical heat transfer correlations, to describe the reflooding phase. [fr

  17. Analysis of the core reflooding of a PWR reactor under a loss-of-coolant postulated accident

    International Nuclear Information System (INIS)

    Austregesilo Filho, H.

    1978-12-01

    The main purpose of this work is to analyse the termohydraulic behaviour of emergency cooling water, during reflooding of a PWR core submitted to a postulated loss-of-coolant accident, with the scope of giving the boundary conditions needed to verify fuel element and containment integrity. The analytical model presented was applied to the simulation of Angra I core reflooding phase, after a double-ended break between pressure vessel and discharge of one of the main coolant pumps. For this accident, with a discharge coefficient of C sub(D) = 0.4, the highest peak cladding temperature is expected. (author) [pt

  18. Verification of thermal-hydraulic computer codes against standard problems for WWER reflooding

    International Nuclear Information System (INIS)

    Alexander D Efanov; Vladimir N Vinogradov; Victor V Sergeev; Oleg A Sudnitsyn

    2005-01-01

    Full text of publication follows: The computational assessment of reactor core components behavior under accident conditions is impossible without knowledge of the thermal-hydraulic processes occurring in this case. The adequacy of the results obtained using the computer codes to the real processes is verified by carrying out a number of standard problems. In 2000-2003, the fulfillment of three Russian standard problems on WWER core reflooding was arranged using the experiments on full-height electrically heated WWER 37-rod bundle model cooldown in regimes of bottom (SP-1), top (SP-2) and combined (SP-3) reflooding. The representatives from the eight MINATOM's organizations took part in this work, in the course of which the 'blind' and posttest calculations were performed using various versions of the RELAP5, ATHLET, CATHARE, COBRA-TF, TRAP, KORSAR computer codes. The paper presents a brief description of the test facility, test section, test scenarios and conditions as well as the basic results of computational analysis of the experiments. The analysis of the test data revealed a significantly non-one-dimensional nature of cooldown and rewetting of heater rods heated up to a high temperature in a model bundle. This was most pronounced at top and combined reflooding. The verification of the model reflooding computer codes showed that most of computer codes fairly predict the peak rod temperature and the time of bundle cooldown. The exception is provided by the results of calculations with the ATHLET and CATHARE codes. The nature and rate of rewetting front advance in the lower half of the bundle are fairly predicted practically by all computer codes. The disagreement between the calculations and experimental results for the upper half of the bundle is caused by the difficulties of computational simulation of multidimensional effects by 1-D computer codes. In this regard, a quasi-two-dimensional computer code COBRA-TF offers certain advantages. Overall, the closest

  19. Measurement of two-phase flow at the core upper plenum interface under simulated reflood conditions

    International Nuclear Information System (INIS)

    Thomas, D.G.; Combs, S.K.; Bagwell, M.E.

    1980-01-01

    Objectives of the Instrument Development Loop program were to simulate flows at the core/upper plenum interface during the reflood phase of a LOCA and to develop instruments for measuring mass-flows at this interface. A tie plate drag body was developed and tested successfully, and the data obtained were shown to be equivalent to pressure drops. The tie-plate drag body gave useful measurements in pure downflow, and the drag/turbine combination correlates with mass flow for high upflow

  20. BWR Refill-Reflood Program, Task 4.7 - model development: TRAC-BWR component models

    International Nuclear Information System (INIS)

    Cheung, Y.K.; Parameswaran, V.; Shaug, J.C.

    1983-09-01

    TRAC (Transient Reactor Analysis Code) is a computer code for best-estimate analysis for the thermal hydraulic conditions in a reactor system. The development and assessment of the BWR component models developed under the Refill/Reflood Program that are necessary to structure a BWR-version of TRAC are described in this report. These component models are the jet pump, steam separator, steam dryer, two-phase level tracking model, and upper-plenum mixing model. These models have been implemented into TRAC-B02. Also a single-channel option has been developed for individual fuel-channel analysis following a system-response calculation

  1. BERTHA: a programme for the thermal/hydraulic analysis of reflooding experiments

    International Nuclear Information System (INIS)

    Pearson, K.G.; Cooper, C.A.

    1985-04-01

    In the event of a large break loss-of coolant accident in a PWR the normal cooling would be restored by reflooding the dry overheated reactor core from below. A model, BERTHA, of heat transfer in this dry region is presented. It includes a film boiling and dispersed flow region and explicitly represents the effect of spacer grids. In parallel channel mode it can calculate the effect of partial flow blockage. Predictions of the model are compared with experimental data and show good agreement in both blocked and unblocked configurations. (U.K.)

  2. LDA measurement of droplet behavior across tie plate during dispersed flow portion of loca reflood

    International Nuclear Information System (INIS)

    Lee, S.L.; Srinivasan, J.; Cho, S.K.

    1980-01-01

    The flow of an air-water droplet dispersion in a simulated 3-D test section in the reflood portion of LOCA was studied. For this purpose, a new scheme of Laser-Doppler Anemometry for the simultaneous measurement of size and velocity of large-size [0.5 mm-6 mm] droplets was developed and utilized. It was observed that the size distribution of the reentrained droplets depends mainly on the flow regimes and is essentially independent of that of the incoming dispersion below the tie plate. 8 refs

  3. Reflooding Experimental On Beta Test Loop : The Characterisation And Preliminary Experiment

    International Nuclear Information System (INIS)

    Khairul, H.; Antariksawan, Anhar R.; Sumamo, Edy; Kiswanta; Giarno; Joko, P.; H, Ismu

    2001-01-01

    The characterisation and preliminary experiment of reflooding had been conducted. The characteristics of main system and component had been identified completely. From these characteristics the experiment condition was set up : heated rod voltage was 20 volt, frequency,of pump was 19 Hz, flow rate was 1 m3/h. The first of experiment did not show the phenomena of rewetting. Possibly because the heated rod temperature was too low. For the second experiment, the voltage of heated rod was increased to 22 Volt and the flow rate was decreased. The result was that the nucleation boiling on the surfaced of heated rod, was observed during the water re flooded the test section

  4. Reflooding phase of the LOCA - state of the art II. Rewetting and liquid entrainment

    International Nuclear Information System (INIS)

    Elias, E.; Yadigaroglu, G.

    1977-01-01

    Understanding the mechanisms by which hot fuel rods quench and the physics of liquid droplet entrainment is important for the analysis of the reflooding phase of the LOCA. Published models of the rewetting process include simple one-dimensional solutions. The basic physical assumptions of these models and the numerical values assigned to the various parameters, as well as empirical rewetting correlations are discussed. The various mechanisms for liquid droplet entrainment and analytical formulations of the critical gas velocity and of the droplet diameter at the onset of entrainment are reviewed

  5. Evaluation report on CCTF core-I reflood test C1-5 (Run 14)

    International Nuclear Information System (INIS)

    Murao, Yoshio; Akimoto, Hajime; Sudoh, Takashi; Okubo, Tsutomu

    1983-02-01

    A study of a cylindrical core test facility (CCTF) test was performed for modeling the system behavior during the reflood phase of a PWR-LOCA and the following conclusions were obtained: 1) With the exception of some points, the observed phenomena are similar to a model derived from an evaluation model for a PWR safety evaluation. 2) The different points are the water accumulation in the upper plenum, the ECC bypass in the downcomer, the reduction of the effective downcomer head and the pressure drop at the broken cold leg nozzle and in the interconnected pipes. (author)

  6. Evaluation report on CCTF core-I reflood test C1-19 (RUN 38)

    International Nuclear Information System (INIS)

    Murao, Yoshio; Fujiki, Kazuo; Akimoto, Hajime

    1983-02-01

    A test named the Evaluation Model (EM) test was performed, whose test conditions were simulated the reflood phase predicted with the safety evaluation analysis. The test results were compared with the blindfold results predicted by Evaluation Model (EM) codes. The main conclusions are as follows: (1) The core heat transfer model built in the EM codes gives conservative results. (2) The system models in the present EM codes are found to be well balanced integrally over the system. (3) Conservative items and items to be improved are pointed out. The downcomer slow water accumulation observed in the lower flow rate test was not appeared in the EM test. (author)

  7. Analysis of the reflood experiment by RELAP5/MOD2 code

    International Nuclear Information System (INIS)

    Prosek, A.; Stritar, A.

    1990-01-01

    The analysis of the reflood experiment on the test rig Achilles has been performed. The analysis has been done by the RELAP5/MOD2 code after the results of the experiment had been released. The experiment has been analyze in several other laboratories around the world. Our results are comparable to other analyses and are in the range of RELAP5/MOD2 capabilities. Two analyses have been done: the core only and the complete system. Computed clad temperatures in the first case are higher than measured, in the second case they are somewhat lower. (author)

  8. Reactivity of Athabasca residue and of its SARA fractions during residue hydroconversion

    Energy Technology Data Exchange (ETDEWEB)

    Verstraete, J.; Danial-Fortain, P.; Gauthier, T.; Merdrignac, I. [IFP-Lyon, Vermaison (France); Budzinski, H. [Bordeaux Univ. (France). ISM-LPTC, UMR CNRS

    2009-07-01

    Residue conversion processes are becoming increasingly important because of the declining market for residual fuel oil and a greater demand for middle distillates. Ebullated-bed hydroconversion is a commercially proven technology for converting heavy feedstocks with high amounts of impurities. The process enables the conversion of atmospheric or vacuum residues at temperatures up to 440 degrees C, and at liquid hourly space velocity (LHSV) conditions in the range of 0.15 to 0.5 per hour. A 540 degrees C conversion of up to 80 weight per cent can be achieved under these conditions. This paper reported on a research study conducted at IFP Lyon in which the residue hydroconversion in a large-scale ebullated bed bench unit was investigated to determine the impact of operating conditions and feed properties on yield and product qualities. Hydrogen was added to the feed in the bench units to keep a high hydrogen partial pressure and favour the catalytic hydroconversion reactions. In a typical test, the reactor was fed with 50 g of feedstock and 0.45 g of crushed equilibrium industrial NiMo catalyst, pressurized hydrogen and quickly heated at the reaction temperature. This paper also discussed the conversion of Athabasca bitumen residue in the large-scale pilot plant and also in the small scale batch reactor. The effect of operating temperature and space velocity was examined. The reactivity of the saturates, aromatics, resins and asphaltenes (SARA) fractions of the bitumen was studied separately in order to better understand the conversion mechanisms and reactivities. The Athabasca bitumen feed and SARA fractions were also analyzed in terms of standard petroleum analysis, SARA fractionation, elemental analysis, size exclusion chromatography (SEC) and 13C NMR. Hydroconversion experiments were conducted in the batch unit at different reaction temperatures and reaction times. A comparison of small-scale batch results with those obtained with the continuous large-scale bench

  9. A model for dispersed flow heat transfer in rod bundles during reflood

    International Nuclear Information System (INIS)

    Wong, S.

    1980-01-01

    The present model calculates the heat transfer characteristics of the non-equilibrium dispersed droplet flow regime above the quench front during reflood by solving simultaneously the wall-to-vapor interactions, wall-to-droplet interactions and vapor-to-droplet interactions by an iterative numerical method. The unique feature in the present study is various heat transfer mechanisms are combined in an overall energy balance equation, and the convective heat transfer to vapor is obtained by calculating the vapor temperature distributions at the heated walls. The reactor rod bundle geometry, axial variations of vapor temperature and flow properties, radiative heat transfers, and enhancement of heat transfer due to turbulence are considered carefully, so that the present model could be used to predict PWR (Pressurized Water Reactor) reflood heat transfers, and hence the fuel cladding wall temperature transients. In order to achieve closure of the problem formulations, the droplet size and its motion are determined from the FLECHT (Full Length Emergency Cooling Heat Transfer Program) low flooding rate series consine axial power shape test data. The model is then verified by comparing the heat transfer predictions with FLECHT low flooding rate series skewed axial power shape test data. Comparisons of predictions with data show satisfactory agreements

  10. Reflooding Experiment on BETA Test Loop: The Effects of Inlet Temperature on the Rewetting Velocity

    International Nuclear Information System (INIS)

    Khairul H; Anhar R Antariksawan; Edy Sumarno; Kiswanta; Giarno; Joko P; Ismu Handoyo

    2003-01-01

    Loss of Coolant Accident (LOCA) on Nuclear Reactor Plant is an important topic because this condition is a severe accident that can be postulated. The phenomenon of LOCA on Pressurized Water Reactor (PWR) can be divided in three stages, e.g.: blowdown, refill and reflood. In the view of Emergency Coolant System evaluation, the reflood is the most important stage. In this stage, an injection of emergency water coolant must be done in a way that the core can be flooded and the overheating can be avoid. The experiment of rewetting on BETA Test Loop had been conducted. The experiment using one heated rod of the test section to study effects of inlet temperature on the wetting velocity. Results of the series of experiments on 2,5 lt/min flow rate and variable of temperature : 28 o C, 38 o C, 50 o C, 58 o C it was noticed that for 58 o C inlet temperature of test section and 572 o C rod temperature the rewetting phenomenon has been observed. The time of refill was 32.81 sec and time of rewetting was 42.87 sec. (author)

  11. COBRA/TRAC analysis of two-dimensional thermal-hydraulic behavior in SCTF reflood tests

    International Nuclear Information System (INIS)

    Iwamura, Takamichi; Ohnuki, Akira; Sobajima, Makoto; Adachi, Hiromichi

    1987-01-01

    The effects of radial power distribution and non-uniform upper plenum water accumulation on thermal-hydraulic behavior in the core were observed in the reflood tests with Slab Core Test Facility (SCTF). In order to examine the predictability of these two effects by a multi-dimensional analysis code, the COBRA/TRAC calculations were made. The calculated results indicated that the heat transfer enhancement in high power bundles above quench front was caused by high vapor flow rate in those bundles due to the radial power distribution. On the other hand, the heat transfer degradation in the peripheral bundles under the condition of non-uniform upper plenum water accumulation was caused by the lower flow rates of vapor and entrained liquid above the quench front in those bundles by the reason that vapor concentrated in the center bundles due to the cross flow induced by the horizontal pressure gradient in the core. The above-mentioned two-dimensional heat transfer behaviors calculated with the COBRA/TRAC code is similar to those observed in SCTF tests and therefore those calculations are useful to investigate the mechanism of the two-dimensional effects in SCTF reflood tests. (author)

  12. NEPTUN/5052, PWR LOCA Cooling Heat Transfer Tests for Loft, Reflood Test

    International Nuclear Information System (INIS)

    Richner, M.; Analytis, G.Th.; Aksan, S.N.

    1993-01-01

    1 - Description of test facility: NEPTUN is designed to perform PWR LOCA simulation experiments, which provide the full length emergency cooling heat transfer tests for LOFT. Therefore the NEPTUN heater bundle with 33 electrical heater elements and 4 guide tubes simulates a section of the LOFT nuclear core. The main test loop also contains measuring systems for the carry-over rate and for the steam expelled, and a back-pressure control system. A water loop brings the water to the initial reflooding conditions. In addition, auxiliary systems maintain normal operating conditions. 2 - Description of test: Test 5052 is one of a series of 40 reflood tests performed in NEPTUN. Before the start of the test, the flooding water in its circuit is brought to the following conditions: pressure = 4.1 bar; velocity = 2.5 cm/sec; subcooling temperature = 78 C; single rod power = 2.45 kW; maximal initial cladding temperature = 867 C. 3 - Status: CSNI1013/01, 21-Jul-1993 Arrived at NEADB

  13. Experimental results of the effective water head in downcomer during reflood phase of a PWR LOCA

    International Nuclear Information System (INIS)

    Sudo, Yukio; Murao, Yoshio; Akimoto, Hajime

    1980-08-01

    The results and analysis of an experiment for the effective water head in downcomer with 50mm gap size are described. The main objective of the experiment was to clarify the effect of gap size on reflooding in a PWR LOCA. The effective water head in downcomer is the driving force for feeding emergency coolant into the core during reflood phase of a PWR LOCA. Discussions presented here follow those of a previous report in which experimental results and analysis were described for the case of 200mm gap size. Experimental Conditions were: Initial Wall Temperature = 200 -- 300 0 C, Back Pressure = 1 atm., Coolant Temperature = 71 -- 100 0 C, Extraction Water Velocity = 0 -- 2 cm/s, Gap Size = 50 mm. The effective water head history obtained in the experiment was compared with those predicted with Sudo's void fraction correlation. In the prediction, heat input to coolant was calculated from the response of measured wall temperature with heat condition analysis. The experimental results and analysis reveals that: (1) The effects of the gap size and initial wall temperature are evident, (2) The effect of extraction water velocity is negligible, and (3) The predicted history of effective water head is in good agreement with the experimental results except during the transient period in which the effective water head is descreasing. (author)

  14. Cold leg injection reflood test results in the SCTF Core-I under constant system pressure

    International Nuclear Information System (INIS)

    Adachi, Hiromichi; Iwamura, Takamichi; Sobajima, Makoto; Osakabe, Masahiro; Ohnuki, Akira; Abe, Yutaka; Murao, Yoshio.

    1990-08-01

    The Slab Core Test Facility (SCTF) was constructed to investigate two-dimensional thermal-hydrodynamics in the core and the interaction in fluid behavior between the core and the upper plenum during the last part of blowdown, refill and reflood phases of a postulated loss-of-coolant accident (LOCA) of a pressurized water reactor (PWR). The present report describes the analytical results on the system behavior observed in the SCTF Core-I cold leg injection tests, S1-14 (Run 520), S1-15 (521), S1-16 (522), S1-17 (523), S1-20 (530), S1-21 (531), S1-23 (536) and S1-24 (537), performed under constant system pressure condition during transient. Major discussion items are: (1) steam binding, (2) U-tube oscillations, (3) bypass of ECC water (4) core cooling behavior, (5) effect of vent valve and (6) other parameter effects. These results give us very useful information and suggestion on reflood behavior. (author)

  15. Development of a thermal-hydraulic code for reflood analysis in a PWR experimental loop

    International Nuclear Information System (INIS)

    Alves, Sabrina P.; Mesquita, Amir Z.; Rezende, Hugo C.; Palma, Daniel A.P.

    2017-01-01

    A process of fundamental importance in the event of Loss of Coolant Accident (LOCA) in Pressurized Water nuclear Reactors (PWR) is the reflood of the core or rewetting of nuclear fuels. The Nuclear Technology Development Center (CDTN) has been developing since the 70’s programs to allow Brazil to become independent in the field of reactor safety analysis. To that end, in the 80’s was designed, assembled and commissioned one Rewetting Test Facility (ITR in Portuguese). This facility aims to investigate the phenomena involved in the thermal hydraulic reflood phase of a Loss of Coolant Accident in a PWR nuclear reactor. This work aim is the analysis of physical and mathematical models governing the rewetting phenomenon, and the development a thermo-hydraulic simulation code of a representative experimental circuit of the PWR reactors core cooling channels. It was possible to elaborate and develop a code called REWET. The results obtained with REWET were compared with the experimental results of the ITR, and with the results of the Hydroflut code, that was the old program previously used. An analysis was made of the evolution of the wall temperature of the test section as well as the evolution of the front for two typical tests using the two codes calculation, and experimental results. The result simulated by REWET code for the rewetting time also came closer to the experimental results more than those calculated by Hydroflut code. (author)

  16. Effect of heat transfer in the fog region during core reflooding

    International Nuclear Information System (INIS)

    Rouai, N. M.; El-sawy, H. M.

    1993-01-01

    Core reflooding following a loss of coolant accident (LOCA) in a pressurized water reactor (PWR) received considerable attention during the past thirty years. In this paper a one dimensional model is used to study the effect of the heat transfer in the fog region ahead of the wet front reflooding rate of a cylindrical fuel element following a LOCA in a PWR. The heat conduction equation in the cladding is solved in coordinate system moving with the wet front under a variety of condition to investigate the effects of such parameters as the initial cladding surface temperature, the decay heat generation rate in the fuel and the mode of heat transfer prevailing. The cladding surface is divided into three axial regions according to the mechanism of heat transfer, namely, a boiling region behind the wet front, a fog region ahead of the wet front and a dry region further downstream of the wet front. The effect of changing the heat transfer coefficient in the fog region on the rewetting rate and on the fog length is investigated. The results of this simple model show that increasing the heat transfer in the fog region increases the rewetting velocity and consequently decreases the fog length. The results are in general agreement with a more accurate two-dimensional model and experimental data. (author)

  17. Development of a thermal-hydraulic code for reflood analysis in a PWR experimental loop

    Energy Technology Data Exchange (ETDEWEB)

    Alves, Sabrina P.; Mesquita, Amir Z.; Rezende, Hugo C., E-mail: sabrinapral@gmail.com, E-mail: amir@cdtn.brm, E-mail: hcr@cdtn.br, E-mail: hcr@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil); Palma, Daniel A.P., E-mail: dapalma@cnen.gov.br [Comissão Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil)

    2017-07-01

    A process of fundamental importance in the event of Loss of Coolant Accident (LOCA) in Pressurized Water nuclear Reactors (PWR) is the reflood of the core or rewetting of nuclear fuels. The Nuclear Technology Development Center (CDTN) has been developing since the 70’s programs to allow Brazil to become independent in the field of reactor safety analysis. To that end, in the 80’s was designed, assembled and commissioned one Rewetting Test Facility (ITR in Portuguese). This facility aims to investigate the phenomena involved in the thermal hydraulic reflood phase of a Loss of Coolant Accident in a PWR nuclear reactor. This work aim is the analysis of physical and mathematical models governing the rewetting phenomenon, and the development a thermo-hydraulic simulation code of a representative experimental circuit of the PWR reactors core cooling channels. It was possible to elaborate and develop a code called REWET. The results obtained with REWET were compared with the experimental results of the ITR, and with the results of the Hydroflut code, that was the old program previously used. An analysis was made of the evolution of the wall temperature of the test section as well as the evolution of the front for two typical tests using the two codes calculation, and experimental results. The result simulated by REWET code for the rewetting time also came closer to the experimental results more than those calculated by Hydroflut code. (author)

  18. Upper plenum dump during reflood in PWR loss-of-coolant accident

    International Nuclear Information System (INIS)

    Sudo, Yukio; Griffith, Peter.

    1981-01-01

    Upper plenum dump during reflood in a large break loww-of-coolant accident of PWR is studied with the emergency core coolant injection into the upper plenum in addition to the cold leg. Transient experiments were carried out by injecting water into the upper plenum and the simple analysis based on a one-dimensional model was done using the drift flux model in order to investigate the conditions under which water dump through the core occurs during reflood. The most significant result is an upper plenum dump occurs when the pressure (hydrostatic head) in the upper plenum is greater than that in the lower plenum. Under those circumstances the flow regime isco-current down flow in which the upper plenum is rapidly emptied. On the other hand, when the upper plenum pressure (hydrostatic head) is less than the lower plenum pressure (hydrostatic head), the co-current down flow is not realized but a counter-current flow occurs. With subcooled water injection to the upper plenum, co-current down flow is realized even when the upper plenum hydrostatic head is less than the lower plenum hydrostatic head. The importance of this effect varies according to the magnetude of water subcooling. (author)

  19. Development of an ion guide coupled to an on-line isotope separation system on Sara. Identification and study of isospin exotic nuclei at Isolde and Sara

    International Nuclear Information System (INIS)

    Bouldjedri, A.

    1992-06-01

    This work is concerned with the study of exotic nuclei located on both sides of the stability-line and known as neutron rich and neutron deficient respectively. For the former, produced by alpha particle-induced fission, an on-line isotope separation with an ion guide (IGISOL) has been developed and submitted to several off-line and on-line optimization tests showing capacity to spectroscopic studies. In the case of neutron deficient nuclei near the magicity Z=82, 182 Tl(3s) has been identified and its decaying modes and those of 183 Tl ground state, studied, using the on-line separator ISOLDE. On the other hand, the β decay of 172,175 Ir produced in 32 S induced reaction is studied using a helium jet system on the SARA accelerator. Existence of isomers is derived from half-lives measurements

  20. RELAP5 model to simulate the thermal-hydraulic effects of grid spacers and cladding rupture during reflood

    Energy Technology Data Exchange (ETDEWEB)

    Nithianandan, C.K.; Klingenfus, J.A.; Reilly, S.S. [B& W Nuclear Technologies, Lynchburg, VA (United States)

    1995-09-01

    Droplet breakup at spacer grids and a cladding swelled and ruptured locations plays an important role in the cooling of nuclear fuel rods during the reflooding period of a loss-of-coolant accident (LOCA) in a pressurized water reactor (PWR). During the reflood phase, a spacer grid affects the thermal-hydraulic system behavior through increased turbulence, droplet breakup due to impact on grid straps, grid rewetting, and liquid holdup due to grid form losses. Recently, models to simulate spacer grid effects and blockage and rupture effects on system thermal hydraulics were added to the B&W Nuclear Technologies (BWNT) version of the RELAP5/MOD2 computer code. Several FLECHT-SEASET forced reflood tests, CCTF Tests C1-19 and C2-6, SCTF Test S3-15, and G2 Test 561 were simulated using RELAP5/MOD2-B&W to verify the applicability of the model at the cladding swelled and rupture locations. The results demonstrate the importance of modeling the thermal-hydraulic effects due to grids, and clad swelling and rupture to correctly predict the clad temperature response during the reflood phase of large break LOCA. The RELAP5 models and the test results are described in this paper.

  1. Reflooding and boil-off experiments in a VVER-440 like rod bundle and analyses with the CATHARE code

    International Nuclear Information System (INIS)

    Korteniemi, V.; Haapalehto, T.; Puustinen, M.

    1995-01-01

    Several experiments were performed with the VEERA facility to simulate reflooding and boil-off phenomena in a VVER-440 like rod bundle. The objective of these experiments was to get experience of a full-scale bundle behavior and to create a database for verification of VVER type core models used with modern thermal-hydraulic codes. The VEERA facility used in the experiments is a scaled-down model of the Russian VVER-440 type pressurized water reactors used in Loviisa, Finland. The test section of the facility consists of one full-scale copy of a VVER-440 reactor rod bundle with 126 full-length electrically heated rod simulators. Bottom and top-down reflooding, different modes of emergency core cooling (ECC) injection and the effect of heating power on the heat-up of the rods was studied. In this paper the results of calculations simulating two reflood and one boil-off experiment with the French CATHARE2 thermal-hydraulic code are also presented. Especially the performance of the recently implemented top-down reflood model of the code was studied

  2. Reflooding and boil-off experiments in a VVER-440 like rod bundle and analyses with the CATHARE code

    Energy Technology Data Exchange (ETDEWEB)

    Korteniemi, V.; Haapalehto, T. [Lappeenranta Univ. of Technology (Finland); Puustinen, M. [VTT Energy, Lappeenranta (Finland)

    1995-09-01

    Several experiments were performed with the VEERA facility to simulate reflooding and boil-off phenomena in a VVER-440 like rod bundle. The objective of these experiments was to get experience of a full-scale bundle behavior and to create a database for verification of VVER type core models used with modern thermal-hydraulic codes. The VEERA facility used in the experiments is a scaled-down model of the Russian VVER-440 type pressurized water reactors used in Loviisa, Finland. The test section of the facility consists of one full-scale copy of a VVER-440 reactor rod bundle with 126 full-length electrically heated rod simulators. Bottom and top-down reflooding, different modes of emergency core cooling (ECC) injection and the effect of heating power on the heat-up of the rods was studied. In this paper the results of calculations simulating two reflood and one boil-off experiment with the French CATHARE2 thermal-hydraulic code are also presented. Especially the performance of the recently implemented top-down reflood model of the code was studied.

  3. REFLA-1D/MODE3: a computer code for reflood thermo-hydrodynamic analysis during PWR-LOCA

    International Nuclear Information System (INIS)

    Murao, Yoshio; Okubo, Tsutomu; Sugimoto, Jun; Iguchi, Tadashi; Sudoh, Takashi.

    1985-02-01

    This manual describes the REFLA-1D/MODE3 reflood system analysis code. This code can solve the core thermo-hydrodynamics under forced flooding conditions and gravity feed conditions in a system similar to FLECHT-SET Phase A. This manual describes the REFLA-1D/MODE3 models and provides application information required to utilize the code. (author)

  4. Effect of upper plenum water accumuration on reflooding phenomena under forced-feed flooding in SCTF Core-I tests

    International Nuclear Information System (INIS)

    Sudo, Yukio; Sobajima, Makoto; Iwamura, Takamichi; Osakabe, Masahiro; Ohnuki, Akira; Abe, Yutaka; Adachi, Hiromichi

    1983-07-01

    Large Scale Reflood Test Program has been performed under contract with the Atomic Energy Bureau of Science and Technology Agency of Japan since 1976. The Slab Core Test Program is a part of the Large Scale Reflood Test Program along with the Cylindrical Core Test Program. Major purpose of the Slab Core Test Program is to investigate two-dimensional, thermo-hydrodynamic behavior in the core and the effect of fluid communication between the core and the upper plenum on the reflood phenomena in a postulated loss-of-coolant accident of a PWR. A significant upper plenum water accumulation was observed in the Base Case Test Sl-01 which was carried out under forced-feed flooding condition. To investigate the effects of upper plenum water accumulation on reflooding phenomena, accumulated water is extracted out of the upper plenum in Test Sl-03 by full opening of valves for extraction lines located just above the upper core support plate. This report presents this effect of upper plenum water accumulation on reflooding phenomena through the comparison of Tests Sl-01 and Sl-03. In spite of full opening of valves for upper plenum water extraction in Test Sl-03, a little water accumulation was observed which is of the same magnitude as in Test Sl-01 for about 200 s after the beginning of reflood. From 200 s after the beginning of reflood, however, the upper plenum water accumulation is much less in Test Sl-03 than in Test Sl-01, showing the following effects of upper plenum water accumulation. In Test Sl-03, (1) the two-dimensionality of horizontal fluid distribution is much less both above and in the core, (2) water carryover through hot leg and water accumulation in the core are less, (3) quench time is rather delayed in the upper part of the core by less water fall back from the upper plenum, and (4) difference in the core thermal behavior and core heat transfer are not significant in the middle and lower part of the core. (author)

  5. Safety verification for the ECCS driven by the electrically 4 trains during LBLOCA reflood phase using ATLAS

    International Nuclear Information System (INIS)

    Park, Yusun; Park, Hyun-sik; Kang, Kyoung-ho; Choi, Nam-hyun; Min, Kyoung-ho; Choi, Ki-yong

    2014-01-01

    Highlights: • Safety improvement by adopting 4 train emergency core cooling system was validated experimentally. • General thermal hydraulic behaviors of the system during LBLOCA reflood phase were successfully demonstrated. • Key parameters such as the liquid levels, the PCTs, the quenching time, and the ECC bypass ratios were investigated. • Asymmetric effects of the different combination of safety injection were negligible during the reflood period. - Abstract: The APR1400 is equipped with four safety injection pumps driven by two emergency diesel generators. However, the design has been changed so that the four safety injection pumps are driven by 4 emergency diesel generators during the design certification process from the U.S. NRC. Thus, 4 safety injection pumps (SIPs) are completely independent electrically and mechanically and three safety injection pumps are available in a single failure condition. This design change could have a certain effects on the thermal-hydraulic phenomenon occurring in the downcomer region during the late reflood phase of a large break loss of coolant accident (LBLOCA). Thus, in this study, a verification experiment for the reflood phase of a LBLOCA was performed to evaluate the core cooling performance of the 4 train emergency core cooling system (ECCS) with an assumption of a single failure. And the different combinations of three SIPs positions were tested to investigate the asymmetric effects on the reactor core cooling performance. The overall experimental results revealed the typical thermal–hydraulic trends expected to occur during the reflood phase of a large-break LOCA scenario for the APR1400. Experiment with the injection of three SIPs showed a faster core quenching time and lower bypass ratio than that of the case in which two SIPs were injected. The RPV wall temperature distributions showed the similar trend in spite of the different SIP combinations

  6. NCBI nr-aa BLAST: CBRC-SARA-01-0195 [SEVENS

    Lifescience Database Archive (English)

    Full Text Available CBRC-SARA-01-0195 ref|NP_036916.1| cannabinoid receptor 1 (brain) [Rattus norvegicu...s] sp|P20272|CNR1_RAT Cannabinoid receptor 1 (CB1) (CB-R) (Brain-type cannabinoid receptor) emb|CAA39332.1| CB1 cann...abinoid receptor [Rattus norvegicus] gb|AAA99067.1| neuronal cannabinoid receptor gb|EDL98589.1| cann...abinoid receptor 1 (brain) [Rattus norvegicus] prf||1613453A cannabinoid receptor NP_036916.1 0.0 97% ...

  7. Nuclear spectroscopy of exotic nuclei with the SARA/IGISOL facility

    International Nuclear Information System (INIS)

    Beraud, R.; Emsallem, A.; Astier, A.; Duffait, R.; Aerje, J.; Aeystoe, J.; Jauho, P.; Barneoud, D.; Genevey, J.; Gizon, A.

    1995-01-01

    Some recent decay studies of neutron-rich and proton-rich nuclei are presented for nuclear structure investigations far off the valley of stability. The experiments, carried out at SARA, are based either on charged particle-induced fission of 238 U or on HI-induced fusion-evaporation reactions in combination with the IGISOL technique. The basic principle of this latter is recalled together with its advantages and limitations. The spectroscopic results obtained in three different regions of the chart of nuclei are sketched. (authors). 30 refs., 7 figs

  8. NCBI nr-aa BLAST: CBRC-SARA-01-1597 [SEVENS

    Lifescience Database Archive (English)

    Full Text Available CBRC-SARA-01-1597 sp|Q9XT58|ADRB3_SHEEP Beta-3 adrenergic receptor (Beta-3 adrenoce...ptor) (Beta-3 adrenoreceptor) gb|AAG31165.1|AF314202_1 beta 3 adrenergic receptor [Ovis aries] gb|AAG31167.1|AF314204_1 beta 3 adrene...rgic receptor [Ovis aries] gb|ABB71185.1| beta 3 adrenergic reecptor [Ovis aries] Q9XT58 1e-140 75% ...

  9. Sara Wasson and Emily Alder, Gothic Science Fiction 1980-2010

    OpenAIRE

    Beaulé, Sophie

    2014-01-01

    With their collection of essays Gothic Science Fiction 1980-2010, Sara Wasson and Emily Alder illustrate the richness of gothic tropes in contemporary forms, from novels and movies to card games. More than cliché, melodrama, or gore, the “gothick” (to borrow Adam Roberts’s term, xi) allows for the hybridity in contemporary production, especially in science fiction, that the collected articles examine. The book is divided into three parts, “Redefining Genres”, “Biopower and Capital”, and “Gend...

  10. NCBI nr-aa BLAST: CBRC-SARA-01-1750 [SEVENS

    Lifescience Database Archive (English)

    Full Text Available CBRC-SARA-01-1750 gb|ABR53744.1| opsin 1 short-wavelength senstive protein [Daubentonia madagascar...iensis] gb|ABR53745.1| opsin 1 short-wavelength senstive protein [Daubentonia madagascariensi...s] gb|ABR53746.1| opsin 1 short-wavelength senstive protein [Daubentonia madagascariensis] gb|ABR53747.1| op...sin 1 short-wavelength senstive protein [Daubentonia madagascariensis] gb|ABR5374...8.1| opsin 1 short-wavelength senstive protein [Daubentonia madagascariensis] gb|ABR53749.1| opsin 1 short-w

  11. Lepidoptera, Nymphalidae, Heliconiinae, Heliconius sara apseudes (Hübner, 1813: Distribution extension

    Directory of Open Access Journals (Sweden)

    Iserhard, C. A.

    2010-01-01

    Full Text Available This work presents new records and extends the geographic distribution of Heliconius sara apseudes in theAtlantic Forest of the state of Rio Grande do Sul. Five new records were taken along butterfly inventories carried outbetween 2005 and 2010 in distinct phytophysiognomies at Rio Grande do Sul northeast region: Swamp Forest, AtlanticForest stricto sensu and Araucaria Moist Forest. The fact that all registers occurred in well preserved habitats of the AtlanticForest emphasizes the need of conservation of this biome in Rio Grande do Sul.

  12. Computation of 3D thermohydraulics in partially blocked bundles during the reflood phase of a LOCA

    International Nuclear Information System (INIS)

    Cicero, G.M.; Briere, E.; Fornaciari, G.

    1994-06-01

    In Pressurized Water Reactors (PWR), ballooning of the fuel rod claddings may occur during a LOCA, since the fuel rod claddings are heated up, and the system pressure is low. The severe blockages that may result induce cross-flow diversion and three-dimensional effects on thermohydraulics in the core bundle, during the reflood phase. To improve the knowledge of these phenomena and their physical modelling in the code CATHARE, 3D computer codes are needed. In 1990, EDF has started up a development and validation program of the 3D THYC computer code to analyze the thermohydraulics of the flow during the reflood phase, in partially blocked bundles. The main objective is to calculate the temperatures of the rods above the quench front, when they are cooled by superheated steam with saturated droplets. First, this paper introduces the THYC model developed for reflood studies. Secondly, we report the first qualification results on a Flooding Experiments with Blocked Array (FEBA) test. Thirdly, we analyze the model predictions on a large break LOCA transient, in a 900 MW PWR 11x11 core area with a 3x3 central blockage. THYC simulates the transient in the bundle around and above the blockage, until the quench front enters the computational domain. Previously, a 1D CATHARE simulation gives the boundary conditions and, in the reactor core case, the deformation of the blocked fuel rods. The results analysis focused on the time evolution of the clad temperatures in the blocked and in the bypass region. In the FEBA test simulation, the main observations are properly predicted within the blockage. Temperatures are lower in blocked rod sleeves than in unblocked rod claddings since the steam gap reduces the power transmitted by the heater rod to the sleeve. In the core case, the model predicts the opposite result. Within the blockage, ballooned rod temperatures are higher than non-ballooned rod ones. We show by sensitivity studies that these behaviour difference between FEBA rods

  13. PLS models for determination of SARA analysis of Colombian vacuum residues and molecular distillation fractions using MIR-ATR

    Directory of Open Access Journals (Sweden)

    Jorge A. Orrego-Ruiz

    2014-06-01

    Full Text Available In this work, prediction models of Saturates, Aromatics, Resins and Asphaltenes fractions (SARA from thirty-seven vacuum residues of representative Colombian crudes and eighteen fractions of molecular distillation process were obtained. Mid-Infrared (MIR Attenuated Total Reflection (ATR spectroscopy in combination with partial least squares (PLS regression analysis was used to estimate accurately SARA analysis in these kind of samples. Calibration coefficients of prediction models were for saturates, aromatics, resins and asphaltenes fractions, 0.99, 0.96, 0.97 and 0.99, respectively. This methodology permits to control the molecular distillation process since small differences in chemical composition can be detected. Total time elapsed to give the SARA analysis per sample is 10 minutes.

  14. Preliminary analysis of the effect of the grid spacers on the reflood heat transfer

    International Nuclear Information System (INIS)

    Sugimoto, Jun; Murao, Yoshio

    1982-02-01

    The results are described about the preliminary analysis of the effect of the grid spacers on the heat transfer during reflood phase of a PWR LOCA. Experiments at JAERI and other facilities showed substantial heat transfer enhancement near the grid spacers. The heat transfer enhancement decreases with the distance from the grid spacers in the downstream region of the grid spacers. Several mechanisms are discussed about the heat transfer enhancement near the grid spacers. A model of a coalescence of the water droplets downstream the spacers is proposed based on the review of the experimental data. The heat transfer correlation for the saturated film boiling is utilized to quantify the heat transfer augmentation by the grid spacers. (author)

  15. Core-debris quenching-heat-transfer rates under top- and bottom-reflood conditions

    International Nuclear Information System (INIS)

    Ginsberg, T.; Tutu, N.; Klages, J.; Schwarz, C.E.; Sanborn, Y.

    1983-02-01

    This paper presents recent experimental data for the quench-heat-transfer characteristics of superheated packed beds of spheres which were cooled, in separate experiments, by top- and bottom-flooding modes. Experiments were carried out with beds of 3-mm steel spheres of 330-mm height. The initial bed temperature was 810 K. The observed heat-transfer rates are strongly dependent on the mode of water injection. The results suggest that top-flood bed quench heat transfer is limited by the rate at which water can penetrate the bed under two-phase countercurrent-flow conditions. With bottom-reflood the heat-transfer rate is an order-of-magnitude greater than under top-flood conditions and appears to be limited by particle-to-fluid film boiling heat transfer

  16. Results of the QUENCH-12 experiment on reflood of a VVER-type bundle

    International Nuclear Information System (INIS)

    Stuckert, J.; Grosse, M.; Heck, M.; Schanz, G.; Sepold, L.; Stegmaier, U.; Steinbrueck, M.

    2008-09-01

    The QUENCH experiments are to investigate the hydrogen source term resulting from the water injection into an uncovered core of a Light-Water Reactor. The QUENCH test bundle with a total length of approximately 2.5 m usually consists of 21 fuel rod simulators of Western PWR (Pressurized Water Reactor) geometry. The QUENCH-12 test bundle, however, which was set up to investigate the effects of VVER materials and bundle geometry (hexagonal lattice) on core reflood consisted of 31 fuel rod simulators. 18 rods of which were electrically heated using tungsten heaters in the rod center. All claddings, corner rods and grid spacers were made of Zr1%Nb (E110) and the shroud of Zr2.5%Nb (E125). For comparison, the QUENCH-06 test (ISP-45) with Western PWR geometry (square lattice) was chosen as reference. QUENCH-12 conducted at the Forschungszentrum Karlsruhe (FZK, Karlsruhe Research Center) on 27 September, 2006 in the frame of the EC-supported ISTC program 1648.2 was proposed by FZK together with RIAR Dimitrovgrad and IBRAE Moscow (Russia), and supported by pretest calculations performed by PSI (Switzerland) and the Kurchatov Institute Moscow (Russia) together with IRSN Cadarache (France). It had been preceded by a low-temperature (maximum 1073 K) pretest on 25 August, 2006 to characterize the bundle thermal hydraulic performance and to provide data to assess the code models used for pretest calculational support. After a stabilization period at 873 K pre-oxidation took place at ∝1470 K for ∝3400 s to achieve a maximum oxide thickness of about 200 μm. A transient phase followed with a temperature rise to ∝2050 K. Then quenching of the bundle by a water flow of 48 g/s was initiated cooling the bundle to ambient temperature in ∝5 min. Following reflood initiation, a moderate temperature excursion of ∝50 K was observed, over a longer period than in QUENCH-06. The temperatures at elevations between 850 mm and 1050 mm exceeded the melting temperature of β-Zr, i

  17. Results of the QUENCH-12 experiment on reflood of a VVER-type bundle

    Energy Technology Data Exchange (ETDEWEB)

    Stuckert, J.; Grosse, M.; Heck, M.; Schanz, G.; Sepold, L.; Stegmaier, U.; Steinbrueck, M. [Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Inst. fuer Materialforschung, Programm Nukleare Sicherheitsforschung; Goryachev, A.; Ivanova, I. [RIAR (FSUE SSC-RIAR) Dimitrovgrad (Russian Federation)

    2008-09-15

    The QUENCH experiments are to investigate the hydrogen source term resulting from the water injection into an uncovered core of a Light-Water Reactor. The QUENCH test bundle with a total length of approximately 2.5 m usually consists of 21 fuel rod simulators of Western PWR (Pressurized Water Reactor) geometry. The QUENCH-12 test bundle, however, which was set up to investigate the effects of VVER materials and bundle geometry (hexagonal lattice) on core reflood consisted of 31 fuel rod simulators. 18 rods of which were electrically heated using tungsten heaters in the rod center. All claddings, corner rods and grid spacers were made of Zr1%Nb (E110) and the shroud of Zr2.5%Nb (E125). For comparison, the QUENCH-06 test (ISP-45) with Western PWR geometry (square lattice) was chosen as reference. QUENCH-12 conducted at the Forschungszentrum Karlsruhe (FZK, Karlsruhe Research Center) on 27 September, 2006 in the frame of the EC-supported ISTC program 1648.2 was proposed by FZK together with RIAR Dimitrovgrad and IBRAE Moscow (Russia), and supported by pretest calculations performed by PSI (Switzerland) and the Kurchatov Institute Moscow (Russia) together with IRSN Cadarache (France). It had been preceded by a low-temperature (maximum 1073 K) pretest on 25 August, 2006 to characterize the bundle thermal hydraulic performance and to provide data to assess the code models used for pretest calculational support. After a stabilization period at 873 K pre-oxidation took place at {proportional_to}1470 K for {proportional_to}3400 s to achieve a maximum oxide thickness of about 200 {mu}m. A transient phase followed with a temperature rise to {proportional_to}2050 K. Then quenching of the bundle by a water flow of 48 g/s was initiated cooling the bundle to ambient temperature in {proportional_to}5 min. Following reflood initiation, a moderate temperature excursion of {proportional_to}50 K was observed, over a longer period than in QUENCH-06. The temperatures at elevations

  18. Measurement of grid spacer's enhanced droplet cooling under reflood condition in a PWR by LDA

    International Nuclear Information System (INIS)

    Lee, S.L.; Sheen, H.J.; Cho, S.K.; Issapour, I.; Hua, S.Q.

    1984-01-01

    Reported is an experiment designed for the measurements of grid spacer's enhanced droplet cooling under reflood condition at elevated temperatures in a steam environment. The flow channel consists of a simulated 1.60m-long pressurized water reactor (PWR) fuel rod bundle of 2 x 2 electrically heated rods. Embedded thermocouples are used to measure the rod cladding temperature at various axial levels and an unshielded Chromel-Alumel thermocouple sheathed by a small Inconel tube is traversed in the center of the subchannel to measure the temperatures of the water and steam coolant phases at various levels. The droplet dynamics across the grid spacer is directly obtained by a special laser-Doppler anemometry technique for the in situ simultaneous measurement of velocity and size of droplets through two observation windows on the test channel, one immediately before and one immediately after the grid spacer. Some results are presented and analyzed

  19. Reentrainment of droplet from grid spacer in mist flow portion of LOCA reflood of PWR

    International Nuclear Information System (INIS)

    Lee, S.L.; Cho, S.K.; Sheen, H.J.

    1983-01-01

    An investigation is made on the influence of a quenched grid spacer on the greatly enhanced heat transfer from heated fuel rods during the mist flow phase of emergency reflood of loss of coolant accident (LOCA) of a pressurized water reactor (PWR). The situation for the case of a dry grid spacer before its quenching has not been covered in this study. The experimental technique used is a relatively simple optical scheme which combines the reference-mode laser-Doppler anemometry making use of the scattering of a light beam from a droplet. The results reveal that the large droplets in the mist flow, which are intercepted by the grid spacer, are responsible for the creation of a large number of smaller droplets. These small droplets, due to their large surface area to mass ratios, can serve as superb evaporative cooling agents to heat transfer downstream of the grid spacer

  20. Experiment predictions of LOFT reflood behavior using the RELAP4/MOD6 code

    International Nuclear Information System (INIS)

    Lin, J.C.; Kee, E.J.; Grush, W.H.; White, J.R.

    1978-01-01

    The RELAP4/MOD6 computer code was used to predict the thermal-hydraulic transient for Loss-of-Fluid Test (LOFT) Loss-of-Coolant Accident (LOCA) experiments L2-2, L2-3, and L2-4. This analysis will aid in the development and assessment of analytical models used to analyze the LOCA performance of commercial power reactors. Prior to performing experiments in the LOFT facility, the experiments are modeled in counterpart tests performed in the nonnuclear Semiscale MOD 1 facility. A comparison of the analytical results with Semiscale data will verify the analytical capability of the RELAP4 code to predict the thermal-hydraulic behavior of the Semiscale LOFT counterpart tests. The analytical model and the results of analyses for the reflood portion of the LOFT LOCA experiments are described. These results are compared with the data from Semiscale

  1. Analytical model for bottom reflooding heat transfer in light water reactors (the UCFLOOD code)

    International Nuclear Information System (INIS)

    Arrieta, L.; Yadigaroglu, G.

    1978-08-01

    The UCFLOOD code is based on mechanistic models developed to analyze bottom reflooding of a single flow channel and its associated fuel rod, or a tubular test section with internal flow. From the hydrodynamic point of view the flow channel is divided into a single-phase liquid region, a continuous-liquid two-phase region, and a dispersed-liquid region. The void fraction is obtained from drift flux models. For heat transfer calculations, the channel is divided into regions of single-phase-liquid heat transfer, nucleate boiling and forced-convection vaporization, inverted-annular film boiling, and dispersed-flow film boiling. The heat transfer coefficients are functions of the local flow conditions. Good agreement of calculated and experimental results has been obtained. A code user's manual is appended

  2. Reflooding phase of the LOCA in PWRs. Part II: rewetting and liquid entrainment

    International Nuclear Information System (INIS)

    Elias, E.; Yadigaroglu, G.

    1978-01-01

    Surface rewetting and liquid-droplet entrainment play an important role in the analysis of the reflooding phase of the loss-of-coolant accident in pressurized-water reactors. The definitions and the various interpretations given to the rewetting temperature and the rewetting mechanisms of the fuel rods are discussed. Published models of the axial-conduction-controlled rewetting process include one-dimensional solutions in two axial regions, one-dimensional solutions in three axial regions with or without precursory cooling, one- and two-dimensional numerical-difference techniques using temperature-dependent heat-transfer coefficients, and analytical two-dimensional solutions. The basic physical assumptions and the numerical values assigned to the various parameters, as well as empirical rewetting correlations, are discussed. The physical mechanisms for liquid-droplet entrainment and analytical formulations of the critical gas velocity and of the droplet diameter at the onset of entrainment are reviewed

  3. Analytical modeling of heat transfer during the reflooding phase of the LOCA: the UCFLOOD code

    International Nuclear Information System (INIS)

    Yadigaroglu, G.; Arrieta, L.A.

    1980-01-01

    A mechanistic model of bottom-reflooding heat transfer is described. From the hydrodynamic point of view the flow channel is divided into a single-phase liquid region, a continuous-liquid two-phase region, and a dispersed-liquid region. The void fraction is obtained from drift flux models. The onset of liquid entrainment is determined using a criterion based on the instability of the liquid core in the inverted-annular flow regime. For heat transfer calculations, the channel is also divided into a number of regions. The heat transfer coefficients are functions of the local flow conditions. Quench front propagation is treated separately by a model including the effects of axial conduction. Good agreement of calculated and experimental results has been obtained

  4. Investigation of radial power and temperature effects in large-scale reflood experiments

    International Nuclear Information System (INIS)

    Motley, F.

    1983-01-01

    The largest reflood test facility in the world has been designed and constructed by the Japan Atomic Energy Research Institute (JAERI). The experimental test facility, known as the Cylindrical Core Test Facility (CCTF), models a full-height core section and the four primary loops of a Pressurized Water Reactor (PWR). The radial power distribution and temperature distribution were varied during the testing program. The test results indicate that the radial effects, while noticeable, do not appreciably alter the overall quenching behavior of the facility. The Transient Reactor Analysis Code (TRAC) correctly predicted the experimental results of several of the tests. The code results indicate that the core flow pattern adjusts multidimensionally to mitigate the effects of increased power or stored energy

  5. Evaluation report on CCTF CORE-I REFLOOD TEST Cl-1, (Run 010)

    International Nuclear Information System (INIS)

    Sudoh, Takashi; Murao, Yoshio.

    1983-09-01

    This report describes the effects of the loop flow resistance on the thermohydraulic behavior in the primary system during the reflood phase. The investigation is based on the results of the test Cl-1 which was performed with increased loop flow resistance in the Cylindrical Core Test Facility (CCTF) at Japan Atomic Energy Research Institute. The loop flow resistance was about 40% higher in the present test than in the reference test Cl-5. The results of two tests were compared and the following conclusions were obtained: 1) The total loop flow rate and the core flooding rate were reduced by about 20% with the increased loop flow resistance 2) The core heat transfer was also lowered, then, the turnaround and the quench times extended at the locations above the core midplane. 3) The measured maximum temperature in the core was 50 K higher for the present test than for the reference test. (author)

  6. Assessment of TRAC-BF1 1D reflood model with CCTF and SCTF data

    International Nuclear Information System (INIS)

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

    1993-03-01

    Post test calculations for six selected Cylindrical Core Test Facility (CCTF) and Slab Core Test Facility (SCTF) tests were performed to assess the core thermal hydraulic models of the TRAC-BF1 code during the reflood in a PWR LOCA. A special version of the TRAC code was developed at JAERI by implementing the constitutive package of the TRAC-BF1 code into the TRAC-PF1 code for this assessment. The TRAC-BF1 model predicted well the void fraction at either bottom or top part of the core and overpredicted the void fraction at the center part of the core in the CCTF and SCTF tests performed under so-called licensing conditions. The TRAC-BF1 model overpredicted the clad temperatures at the center part of the core. The TRAC-BF1 model predicted a jump of void fraction where the flow pattern transition between the bubbly/slug flow and the annular/dispersed flow regimes occurred. The jump caused the water mass flow rate to be unstable and resulted in the overprediction of the void fraction at the center part of the core. It was also found that the TRAC-BF1 film boiling model underestimated the heat transfer coefficient in the vicinity of the quench front and caused the quench front propagation to be delayed. These assessment results suggest the following areas should be improved in future to apply the TRAC-BF1 code to the reflood in a PWR LOCA: (1) Core hydraulic model where flow pattern transition occurs, (2) Core heat transfer model in the film boiling regime, especially for the dependence on the distance from the quench front. (author)

  7. Effects of upper plenum injection on thermo-hydrodynamic behavior under refill and reflood phases

    International Nuclear Information System (INIS)

    Iwamura, Takamichi; Sobajima, Makoto; Abe, Yutaka; Adachi, Hiromichi; Ohnuki, Akira; Osakabe, Masahiro

    1984-12-01

    In order to investigate the thermo-hydrodynamic behavior in core under simultaneous ECC water injection into the upper plenum and the intact cold leg during the refill and reflood phases of a PWR-LOCA, Tests S1-SH3 and S1-SH4 were performed by using Slab Core Test Facility (SCTF) with the injection of saturated and 67K subcooled water into the upper plenum, respectively, under the same cold leg injection condition. The following major findings were obtained by examining these test results. (1) Although the core was cooled by the fall back water from the upper plenum into the core during the period of high injection rate into the upper plenum, the core was cooled mainly by the bottom flooding after the BOCREC (Bottom of core recovery). (2) The possible fall back flow rate estimated with a CCFL correlation rapidly decreased after the BOCREC because of the increase of steam generation rate in core. (3) Continuous fall back of subcooled water was not observed even under the condition with large upper plenum injection rate of subcooled water and with steam outflow through the lower plenum into the downcomer. The fall back was intermittently limited by the rapid increase of upward steam flow which was generated in the core due to the evaporation of the fall back water. (4) The rising of liquid level in the lower plenum was suppressed by the pressurization in core due to the evaporation of fall back water before the BOCREC and therefore the beginning of bottom reflood was delayed. Some selected data from Tests S1-SH3 and S1-SH4 are also included in this report. (author)

  8. Evaluation report on CCTF Core-II reflood Test C2-15 (Run 75)

    International Nuclear Information System (INIS)

    Okubo, Tsutomu; Iguchi, Tadashi; Akimoto, Hajime; Murao, Yoshio

    1992-01-01

    This report presents an evaluation on the CCTF Core-II Test C2-15 (Run 75). The purpose of the test is to investigate whether the thermo-hydrodynamic behavior is different between the CCTF and the FLECHT-SET reflooding tests. For this purpose, test conditions of the present test were set as close as possible to those of concerned FLECHT-SET 2714B experiment, taking account of differences in facility design. Investigating results of both the tests, the following conclusions are obtained: (1) Some discrepancies were observed in the measured test conditions between the two tests. Out of them, difference in the Acc injection duration was large and affected test results, such as the water accumulation in the downcomer and the core and the core cooling, during the initial period. However, this effect was found to become small with time. (2) Taking account of this difference and the difference in the broken cold leg pressure loss coefficient between the two facilities, the overall reflooding behavior is judged to be similar in the two facilities. (3) The CCTF test results showed the core heat transfer enhancement in the higher power region due to its steep radial power distribution, whereas the FLECHT-SET did not due to its rather flat radial power distribution. This enhancement was observed significantly at 1.83 m but was smaller at the higher elevation. (4) The heat transfer was nearly identical between the two tests and an existing correlation could well predict the heat transfer coefficients of both the tests at the location where the heat transfer enhancement mentioned above (3) were small, during the time period when the effect of the difference in the Acc injection mentioned above (1) were small. (5) Therefore, the core cooling is expected to be almost the same in the CCTF and the FLECHT-SET under the same core boundary conditions and core radial power distribution. (author)

  9. Reflood behavior at low initial clad temperature in Slab Core Test Facility Core-II

    International Nuclear Information System (INIS)

    Akimoto, Hajime; Sobajima, Makoto; Abe, Yutaka; Iwamura, Takamichi; Ohnuki, Akira; Okubo, Tsutomu; Murao, Yoshio; Okabe, Kazuharu; Adachi, Hiromichi.

    1990-07-01

    In order to study the reflood behavior with low initial clad temperature, a reflood test was performed using the Slab Core Test Facility (SCTF) with initial clad temperature of 573 K. The test conditions of the test are identical with those of SCTF base case test S2-SH1 (initial clad temperature 1073 K) except the initial clad temperature. Through the comparison of results from these two tests, the following conclusions were obtained. (1) The low initial clad temperature resulted in the low differential pressures through the primary loops due to smaller steam generation in the core. (2) The low initial clad temperature caused the accumulated mass in the core to be increased and the accumulated mass in the downcomer to be decreased in the period of the lower plenum injection with accumulator (before 50s). In the later period of the cold leg injection with LPCI (after 100s), the water accumulation rates in the core and the downcomer were almost the same between both tests. (3) The low initial clad temperature resulted in the increase of the core inlet mass flow rate in the lower plenum injection period. However, the core inlet mass flow rate was almost the same regardless of the initial clad temperature in the later period of the cold leg injection period. (4) The low initial clad temperature resulted in the low turnaround temperature, high temperature rise and fast bottom quench front propagation. (5) In the region apart from the quench front, low initial clad temperature resulted in the lower heat transfer. In the region near the quench front, almost the same heat transfer coefficient was observed between both tests. (6) No flow oscillation with a long period was observed in the SCTF test with low initial clad temperature of 573 K, while it was remarkable in the Cylindrical Core Test Facility (CCTF) test which was performed with the same initial clad temperature. (J.P.N.)

  10. Inhibition of transforming growth factor-beta1-induced signaling and epithelial-to-mesenchymal transition by the Smad-binding peptide aptamer Trx-SARA.

    Science.gov (United States)

    Zhao, Bryan M; Hoffmann, F Michael

    2006-09-01

    Overexpression of the inhibitory Smad, Smad7, is used frequently to implicate the Smad pathway in cellular responses to transforming growth factor beta (TGF-beta) signaling; however, Smad7 regulates several other proteins, including Cdc42, p38MAPK, and beta-catenin. We report an alternative approach for more specifically disrupting Smad-dependent signaling using a peptide aptamer, Trx-SARA, which comprises a rigid scaffold, the Escherichia coli thioredoxin A protein (Trx), displaying a constrained 56-amino acid Smad-binding motif from the Smad anchor for receptor activation (SARA) protein. Trx-SARA bound specifically to Smad2 and Smad3 and inhibited both TGF-beta-induced reporter gene expression and epithelial-to-mesenchymal transition in NMuMG murine mammary epithelial cells. In contrast to Smad7, Trx-SARA had no effect on the Smad2 or 3 phosphorylation levels induced by TGF-beta1. Trx-SARA was primarily localized to the nucleus and perturbed the normal cytoplasmic localization of Smad2 and 3 to a nuclear localization in the absence of TGF-beta1, consistent with reduced Smad nuclear export. The key mode of action of Trx-SARA was to reduce the level of Smad2 and Smad3 in complex with Smad4 after TGF-beta1 stimulation, a mechanism of action consistent with the preferential binding of SARA to monomeric Smad protein and Trx-SARA-mediated disruption of active Smad complexes.

  11. Sara John: Ethnisierte Arbeit. Eine feministische Perspektive. Marburg: Tectum Wissenschaftsverlag 2009.

    Directory of Open Access Journals (Sweden)

    Grit Grigoleit

    2011-03-01

    Full Text Available Auch bei steigender Erwerbsbeteiligung von Frauen ist der deutsche Arbeitsmarkt von einer weitverbreitenden Chancenungleichheit gekennzeichnet. Die Lebenswirklichkeiten von Migrant/-innen und ihre Einbindung in die vergeschlechtlichten Prozesse am Arbeitsmarkt wurden bislang nicht systematisch erfasst. An diesem Punkt setzt Sara John an, indem sie theoretische Konzeptionen zur Vergeschlechtlichung und zur Ethnisierung auf dem Arbeitsmarkt zusammenführt. In einem multidisziplinären Ansatz werden die zahlreichen Verschränkungen um das Phänomen ‚ethnisierte Arbeit‘ aufgegriffen, die vor dem Hintergrund der Debatte um Deutschland als Einwanderungsland zunehmend an Bedeutung und Brisanz gewinnen.Although women’s labor force participation is rising, the German job market is characterized by a widespread lack of equal opportunities. Thus far, the everyday realities of migrants and their integration into the gendered processes on the job market have not been collected systematically. This is where Sara John begins her study by combining theoretical conceptions about gendering and ethnicizing on the job market. In a multidisciplinary approach, several entanglements surrounding the phenomenon ‘ethnicized labor’ are taken into account. These entanglements keep gaining importance and topicality against the backdrop of Germany as a country of immigration.

  12. Analysis with SCDAP/RELAP5 of reflooding of an overheated core in Forsmark 3 BWR after loss of electric power

    International Nuclear Information System (INIS)

    Nilsson, Lars.

    1993-01-01

    In foregoing SIK-2.2 project two severe accident sequences for Forsmark 3 comprising loss of electric power (Total Blackout, TB) without recovery actions (e.g. emergency cooling) were analysed with SCDAP/RELAP5. Code version MOD2.5/V3f was applied and a single core channel input model was used. Present analysis was done with the same initiating events as in SIK-2.2, but assuming recovery of auxiliary feed water and/or emergency core cooling systems to take place after heat-up of the core, in compliance with the plans of the SIK-2.3 project. A new test version of the SCDAP/RELAP5 code, version MOD3/V7af, was used here. The geometrical input model was extended from having one, into five parallel core zones, still with ten axial core sub volumes. Calculations were performed for three TB cases, one without cooling recovery, and two with injection of cold water at a rate of 45 kg/s, beginning when the maximum cladding temperature has reached 1522 K. The results show that a considerably more efficient cooling was obtained spraying the water to the top of the core, compared to the case where the cooling water was introduced into the downcomer, leading to bottom reflooding

  13. Probabilistic model fitting for spatio-temporal variability studies of precipitation: the Sara-Brut system - a case study

    International Nuclear Information System (INIS)

    Dorado Delgado, Jennifer; Burbano Criollo, Juan Carlos; Molina Tabares, Jose Manuel; Carvajal Escobar, Yesid; Aristizabal, Hector Fabio

    2006-01-01

    In this study, space and time variability of monthly and annual rainfall was analyzed for the downstream influence zone of a Colombian supply-regulation reservoir, Sara-Brut, located on the Cauca valley department. Monthly precipitation data from 18 gauge stations and for a 29-year record (1975-2003) were used. These data were processed by means of time series completion, consistency analyses and sample statistics computations. Theoretical probabilistic distribution models such as Gumbel, normal, lognormal and wake by, and other empirical distributions such as Weibull and Landwehr were applied in order to fit the historical precipitation data set. The fit standard error (FSE) was used to test the goodness of fit of the theoretical distribution models and to choose the best of this probabilistic function. The wake by approach showed the best goodness of fit in 89% of the total gauges taken into account. Time variability was analyzed by means of wake by estimated values of monthly and annual precipitation associated with return periods of 1,052, 1,25, 2, 10, 20 and 50 years. Precipitation space variability is presents by means of ArcGis v8.3 and using krigging as interpolation method. In general terms the results obtained from this study show significant distribution variability in precipitation over the whole area, and particularity, the formation of dry and humid nucleus over the northeastern strip and microclimates at the southwestern and central zone of the study area were observed, depending on the season of year. The mentioned distribution pattern is likely caused by the influence of pacific wind streams, which come from the Andean western mountain range. It is expected that the results from this work be helpful for future planning and hydrologic project design

  14. A Different Curriculum of Preparation for Work: Commentary on Mike Rose, Sara Goldrick-Rab, Kris Gutierrez and Norton Grubb

    Science.gov (United States)

    Worthen, Helena Harlow

    2012-01-01

    The January 2012 issue of "Mind, Culture, and Activity" published the Invited Presidential Address "Rethinking Remedial Education and the Academic-Vocational Divide," given by Mike Rose at the 2011 meeting of the American Educational Research Association in New Orleans, along with responses and commentary by Sara Goldrick-Rab, Kris Gutierrez, and…

  15. Hemolytic disease of the fetus and newborn caused by an antibody to a low-prevalence antigen, anti-SARA.

    Science.gov (United States)

    Towns, Dale; Hannon, Judith; Hendry, Julia; Barnes, Janet; Goldman, Mindy

    2011-09-01

    The first case describing the SARAH (SARA) antigen occurred in 1990, in an Australian blood donor. Hemolytic disease of the fetus and newborn (HDFN) due to anti-SARA has not been previously described. We report a case of HDFN in a multiparous female. The pregnancy was unremarkable except that she was involved in a seemingly minor motor vehicle accident at 25 weeks' gestation. Routine prenatal antibody screening was negative throughout the pregnancy. She presented at 37 weeks' gestation because of decreased fetal movements. Labor was induced and a 2702-g infant male was delivered. The infant's hemoglobin was 49 g/L and the bilirubin was 153 µmol/L. Blood samples from the parents and infant were referred to Canadian Blood Services National Immunohematology Reference Laboratory and subsequently to the Australian Red Cross Red Cell Reference Service. The father's and infant's red blood cells were confirmed to be SARA positive, and the mother's plasma contained anti-SARA. The infant was successfully treated with a double-volume exchange transfusion. This is the first example of HDFN associated with this antibody. © 2011 American Association of Blood Banks.

  16. Should Community College Be Free? Forum. "Education Next" Talks with Sara Goldrick-Rab and Andrew P. Kelly

    Science.gov (United States)

    Goldrick-Rab, Sara; Kelly, Andrew P.

    2016-01-01

    In this article, "Education Next" talks with Sara Goldrick-Rab and Andrew Kelly. President Obama's proposal for tuition-free community college, seems to have laid down a marker for the Democratic Party. Vermont senator Bernie Sanders is touting his plan for free four-year public college on the primary trail; Massachusetts senator…

  17. NCBI nr-aa BLAST: CBRC-SARA-01-1608 [SEVENS

    Lifescience Database Archive (English)

    Full Text Available CBRC-SARA-01-1608 ref|NP_001832.1| cannabinoid receptor 2 (macrophage) [Homo sapien...s] sp|P34972|CNR2_HUMAN Cannabinoid receptor 2 (CB2) (CB-2) (CX5) emb|CAA52376.1| CB2 (peripheral) cannabino...id receptor [Homo sapiens] emb|CAD22548.1| peripheral cannabinoid receptor CB2 [Homo sapiens] emb|CAD22549.1| peripheral cann...abinoid receptor CB2 [Homo sapiens] gb|AAO92299.1| cannabinoid r...eceptor 2 [Homo sapiens] emb|CAI14799.1| cannabinoid receptor 2 (macrophage) [Homo sapiens] emb|CAJ42137.1| cann

  18. NCBI nr-aa BLAST: CBRC-SARA-01-0948 [SEVENS

    Lifescience Database Archive (English)

    Full Text Available CBRC-SARA-01-0948 ref|NP_473371.1| MAS-related GPR, member X2 [Homo sapiens] sp|Q96...LB1|MRGX2_HUMAN Mas-related G-protein coupled receptor member X2 gb|AAK91805.1| G protein-coupled receptor [Homo sapiens...] dbj|BAB89339.1| putative G-protein coupled receptor [Homo sapiens] dbj|BAC06030.1| seven trans...membrane helix receptor [Homo sapiens] gb|AAH63450.1| MAS-related GPR, member X2 [Homo sapiens...] gb|AAW70056.1| MRGX2 [Homo sapiens] gb|AAW70057.1| MRGX2 [Homo sapiens] gb|AAW70058.1| MRGX2 [Homo sapiens

  19. NCBI nr-aa BLAST: CBRC-SARA-01-1066 [SEVENS

    Lifescience Database Archive (English)

    Full Text Available CBRC-SARA-01-1066 ref|NP_473371.1| MAS-related GPR, member X2 [Homo sapiens] sp|Q96...LB1|MRGX2_HUMAN Mas-related G-protein coupled receptor member X2 gb|AAK91805.1| G protein-coupled receptor [Homo sapiens...] dbj|BAB89339.1| putative G-protein coupled receptor [Homo sapiens] dbj|BAC06030.1| seven trans...membrane helix receptor [Homo sapiens] gb|AAH63450.1| MAS-related GPR, member X2 [Homo sapiens...] gb|AAW70056.1| MRGX2 [Homo sapiens] gb|AAW70057.1| MRGX2 [Homo sapiens] gb|AAW70058.1| MRGX2 [Homo sapiens

  20. NCBI nr-aa BLAST: CBRC-SARA-01-1746 [SEVENS

    Lifescience Database Archive (English)

    Full Text Available CBRC-SARA-01-1746 ref|NP_705806.1| non-imprinted in Prader-Willi/Angelman syndrome ...1 [Mus musculus] sp|Q8BHK1|NIPA1_MOUSE Non-imprinted in Prader-Willi/Angelman syndrome region protein 1 homo...protein product [Mus musculus] gb|AAH55828.1| Non imprinted in Prader-Willi/Angel...man syndrome 1 homolog (human) [Mus musculus] gb|EDL21870.1| non imprinted in Prader-Willi/Angelman syndrome 1 homolog (human) [Mus musculus] NP_705806.1 1e-113 81% ... ...log gb|AAM34534.1| non-imprinted in Prader-Willi/Angelman syndrome 1 [Mus musculus] dbj|BAC32809.1| unnamed

  1. NCBI nr-aa BLAST: CBRC-SARA-01-1942 [SEVENS

    Lifescience Database Archive (English)

    Full Text Available CBRC-SARA-01-1942 ref|NP_000669.1| alpha-1D-adrenergic receptor [Homo sapiens] sp|P...25100|ADA1D_HUMAN Alpha-1D adrenergic receptor (Alpha 1D-adrenoceptor) (Alpha 1D-adrenoreceptor) (Alpha-1A adrenergic... receptor) (Alpha adrenergic receptor 1a) gb|AAB60351.1| adrenergic alpha-1a receptor protein gb|AAB59487.1| alpha 1a/d adre...nergic receptor dbj|BAA06222.1| alpha1A/D adrenergic rec...eptor [Homo sapiens] emb|CAH70478.1| adrenergic, alpha-1D-, receptor [Homo sapiens] emb|CAC00601.2| adrenergic

  2. NCBI nr-aa BLAST: CBRC-SARA-01-1691 [SEVENS

    Lifescience Database Archive (English)

    Full Text Available CBRC-SARA-01-1691 ref|NP_000854.1| 5-hydroxytryptamine (serotonin) receptor 1B [Hom...o sapiens] ref|NP_001009102.1| 5-hydroxytryptamine (serotonin) receptor 1B [Pan troglodytes] sp|P28222|5HT1B...HT-1B) (Serotonin receptor 1B) (5-HT1B) gb|AAA58675.1| serotonin 1Db receptor gb|AAA36029.1| serotonin recep...tor gb|AAA36030.1| 5-hyroxytryptamine 1D receptor dbj|BAA01763.1| serotonin 1B receptor [Homo sapiens] gb|AAA60316.1| serotonin... 1D receptor emb|CAB51537.1| 5-hydroxytryptamine (serotonin) r

  3. Escribiendo el silencio: la contemplación poética de Sara Pujol

    Directory of Open Access Journals (Sweden)

    Gala, Candelas

    2005-06-01

    Full Text Available Reading Sara Pujol Russell's El fuego tiende su aire (1999 and Intacto asombro de la luz del silencio (2001, is entering into a poetic world whose content and form are both innovative and complex. This poetry invites the reader into a state of meditative contemplation that seeks correspondences among different elements in reality as the key to access a superior type of knowledge. Pujol's writing moves in the fringes between voice and silence, art and nature, meaning and nothingness, identity and difference, it seeks to surpass its own verbal texture while only in that texture does it find articulation and only through it does transcendence becones accessible. The focus of the present reading centers on the point where Pujol's language seeks to transcend the disjunction between sign and surrounding, the point where synthesis is fusion about to dissolve.La lectura de El fuego tiende su aire (1999 e Intacto asombro en la luz del silencio (2001 de Sara Pujol Russell, supone la entrada en un discurso poético innovador y complejo tanto en contenido como en forma. Esta poesía invita a una contemplación meditativa que busca las correspondencias entre los diversos elementos de la realidad como clave para acceder a un conocimiento superior. Su escritura se mueve en los bordes entre la voz y el silencio, el arte y la naturaleza, el sentido y el vacío, la identidad y la diferencia, buscando trascender lo que está más allá de su misma urdimbre verbal pero que sólo en ella se configura, y sólo desde ella se puede acceder. En el movimiento de esta escritura por superar la disyunción entre signo y entorno, en esa síntesis a punto de disolverse, es donde se enfoca la lectura en este ensayo.

  4. The Workplace Literacy System Project (WLS). Final Performance Report.

    Science.gov (United States)

    Poulton, Bruce R.

    The Workplace Literacy System Project (WLS) prepared interactive CD-ROM discs containing about 50 hours of instruction and drill in basic skills presented within the context of the textile/apparel manufacturing industry. The project was conducted at a Sara Lee knit products plant in North Carolina. During the project, literacy task analyses were…

  5. Effect of a blockage length on the coolability during reflood in a 2 × 2 rod bundle with a 90% partially blocked region

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Kihwan, E-mail: kihwankim@kaeri.re.kr [Korea Atomic Energy Research Institute, Daeduk-daero 989-111, Yuseong-Gu, Daejeon 34057 (Korea, Republic of); Kim, Byung-Jae, E-mail: byoungjae@kaeri.re.kr [School of Mechanical Engineering, Chungnam National University, 99 Daehak-ro, Yuseoung-Gu, Daejeon 34134 (Korea, Republic of); Choi, Hae-Seob, E-mail: hschoi@kaeri.re.kr [Korea Atomic Energy Research Institute, Daeduk-daero 989-111, Yuseong-Gu, Daejeon 34057 (Korea, Republic of); Moon, Sang-Ki, E-mail: skmoon@kaeri.re.kr [Korea Atomic Energy Research Institute, Daeduk-daero 989-111, Yuseong-Gu, Daejeon 34057 (Korea, Republic of); Song, Chul-Hwa, E-mail: chsong@kaeri.re.kr [Korea Atomic Energy Research Institute, Daeduk-daero 989-111, Yuseong-Gu, Daejeon 34057 (Korea, Republic of)

    2017-02-15

    Highlights: • This test was conducted to understand the effect of blockage length on the coolability. • Reflood tests were conducted with blockage simulators for various reflood rates. • The coolability in the downstream of the blockage region is significantly enhanced. - Abstract: If fuel rods are ballooned or rearranged during the reflood phase of a large break loss-of-coolant accident (LBLOCA) in a pressurized-water reactor (PWR), the transient heat transfer behavior is entirely different with those of the intact fuel rods owing to the deformed blockage region. The coolability in the blocked region depends on a complex two-phase heat transfer with various thermal hydraulic conditions. In addition, the blockage characteristics, such as the blockage ratio, length, shape, and configurations, are also significant factors affecting the coolability. In the present study, reflood experiments were carried out to understand the effect of the blockage length upon the coolability by varying the reflooding rates. The experiments were performed in electrically heated 2 × 2 rod bundles with blockage simulators having the same blockage ratio but different blockage lengths. The characteristics of quenching and heat transfer were evaluated to investigate the influence of the blockage region on the coolability. The droplet behaviors were also observed by measuring the droplets velocity and size near the blockage region. The coolability in the downstream region of the blockage was significantly enhanced, owing to the reduced flow area of the sub-channel, intensification of turbulence, and the entrained droplets in the blockage region.

  6. Evaluation report on CCTF Core-II reflood tests C2-AC1 (run 51) and C2-4 (run 62)

    International Nuclear Information System (INIS)

    Sugimoto, Jun; Iguchi, Tadashi; Murao, Yoshio

    1984-02-01

    A reflood test program has been conducted at Japan Atomic Energy Research Institute (JAERI) using large scale test facilities named Cylindrical Core Test Facility (CCTF) and Slab Core Test Facility (SCTF). The present report describes the effect of the initial clad temperature i.e., the initial stored energy on reflood phenomena observed in CCTF Core-II tests C2-ACl and C2-4. The peak clad temperatures of tests C2-ACl and C2-4 were 863 K and 1069 K, respectively at reflood initiation. With higher initial clad temperature, obtained were lower water accumulation in the core and upper plenum, and higher loop mass flow rate in an early reflood transient due to larger heat release of the stored energy in the core. Core inlet flow conditions were only affected shortly after the reflood initiation, causing the suppressed flooding rate and the larger U-tube flow oscillation between the core and the downcomer. In the core, with higher initial clad temperature, slower quench front propagation and higher turnaround temperature were observed. Responses to a higher initial clad temperature were similar to those observed in CCTF Core-I and FLECHT tests. Thus, the lower temperature rise with higher initial clad temperature was experimentally confirmed. The importance of higher flooding rate at initial period was analytically shown for further decreasing the temperature rise. (author)

  7. Large scale reflood test with cylindrical core test facility (CCTF). Core I. FY 1979 tests

    International Nuclear Information System (INIS)

    Murao, Yoshio; Akimoto, Hajime; Okubo, Tsutomu; Sudoh, Takashi; Hirano, Kenmei

    1982-03-01

    This report presents the results of analysis of the data obtained in the CCTF Core I test series (19 tests) in FY. 1979 as an interim report. The Analysis of the test results showed that: (1) The present safety evaluation model on the reflood phenomena during LOCA conservatively represents the phenomena observed in the tests except for the downcomer thermohydrodynamic behavior. (2) The downcomer liquid level rose slowly and it took long time for the water to reach a terminal level or the spill-over level. It was presume that such a results was due to an overly conservative selection of the ECC flow rate. This presumption will be checked against a future test result for an increased flow rate. The loop-seal-water filling test was unsuccessful due to a premature power shutdown by the core protection circuit. The test will be conducted again. The tests to be performed in the future are summerized. Tests for investigation of the refill phenomena were also proposed. (author)

  8. Post-BEMUSE Reflood Model Input Uncertainty Methods (PREMIUM) Benchmark Phase II: Identification of Influential Parameters

    International Nuclear Information System (INIS)

    Kovtonyuk, A.; Petruzzi, A.; D'Auria, F.

    2015-01-01

    The objective of the Post-BEMUSE Reflood Model Input Uncertainty Methods (PREMIUM) benchmark is to progress on the issue of the quantification of the uncertainty of the physical models in system thermal-hydraulic codes by considering a concrete case: the physical models involved in the prediction of core reflooding. The PREMIUM benchmark consists of five phases. This report presents the results of Phase II dedicated to the identification of the uncertain code parameters associated with physical models used in the simulation of reflooding conditions. This identification is made on the basis of the Test 216 of the FEBA/SEFLEX programme according to the following steps: - identification of influential phenomena; - identification of the associated physical models and parameters, depending on the used code; - quantification of the variation range of identified input parameters through a series of sensitivity calculations. A procedure for the identification of potentially influential code input parameters has been set up in the Specifications of Phase II of PREMIUM benchmark. A set of quantitative criteria has been as well proposed for the identification of influential IP and their respective variation range. Thirteen participating organisations, using 8 different codes (7 system thermal-hydraulic codes and 1 sub-channel module of a system thermal-hydraulic code) submitted Phase II results. The base case calculations show spread in predicted cladding temperatures and quench front propagation that has been characterized. All the participants, except one, predict a too fast quench front progression. Besides, the cladding temperature time trends obtained by almost all the participants show oscillatory behaviour which may have numeric origins. Adopted criteria for identification of influential input parameters differ between the participants: some organisations used the set of criteria proposed in Specifications 'as is', some modified the quantitative thresholds

  9. An analytical study of thermo-hydrodynamic behaviour of the reflood-phase during a LOCA

    International Nuclear Information System (INIS)

    Murao, Y.

    1977-12-01

    The objectives of this study are - the check of the quench model proposed by the author and T. Sudoh, - the establishment of the thermo-hydrodynamics downstream from the quench front, and - the stabilization of the numerical calculations. In order to study these therms, the new version of the reflood analysis code 'REFLA-1D' was developed. The quench modes were classified into the following three types: 1) Liquid column type (rewetting by subcooled water), 2) Dryout type (annular flow type, rewetting by saturated water), and 3) Rewetting type (entire surface temperature higher than rewetting temperature). For the thermo-hydrodynamic model downstream from the quench front, the flow pattern was divided into the five regimes: 1) Subcooled film boiling regime, 2) Transition flow regime, 3) Dispersed flow regime, 4) Superheated steam flow regime, and 5) Rewetted regime. To stabilze the numerical calculation and shorten the computing time, the Lagrangian form of the energy equation of gase phase and dispersed flow region was used instead of the Eulerian form. Considerably close agreement between three PWR-FLECHT tests and the calculated results for the critical Weber number Wec=1.0 was obtained for fuel clad surface temperature and quench time except in earlier stage before turnaround, but poor agreement for the heat transfer characteristics in the transition flow region defined between the quench front and the dispersed flow region. The calculation was relatively stable and the computing time is about the same as a real time for a IBM 370-158 computer. (orig.) [de

  10. Reflood Heat Transfer in SiC and Graphene Oxide Coated Tube

    International Nuclear Information System (INIS)

    Kim, Kyung Mo; Lee, Seung Won; Bang, In Cheol

    2013-01-01

    The reflood tests have been performed flowing water into bare tube and nanoparticles coated tube at constant flow rate (3 cm/s). The quenching curves have been obtained at atmospheric pressure. Finally, Scanning Electron Microscopy (SEM) images are acquired and contact angles are measured in order to observe the surface structures and wettability effect on cooling performance. The quenching time decreases and quenching velocity increases as the coating time of nanoparticles on the tube increases, because the nanoparticles deposited on the tube destabilize and rupture the vapor film early in the effect of increased Leidenfrost point temperature. The SiC nanoparticles coated tubes have better quenching performance than GO nanoparticles coated tubes. The SEM images and contact angle observations proved the enhanced wettability and rough surface due to deposition of SiC nanoparticles. And the wettability of GO nanoparticles coated tubes shows the increase at 600 s coating. But, the wettability decreases on GO nanoparticles tube coated for 900 s despite the enhanced quenching performance. Thus, the porous structure affects to the better cooling performance in case of GO nanoparticles coated tubes

  11. Evaluation report on CCTF Core-II reflood test C2-9 (Run 68)

    International Nuclear Information System (INIS)

    Akimoto, Hajime; Iguchi, Tadashi; Okubo, Tsutomu; Murao, Yoshio; Okabe, Kazuharu; Sugimoto, Jun.

    1987-02-01

    In order to study the LPCI flow rate effect on the core cooling and system behavior, a test was performed with the LPCI flow rate of 0.025 m 3 /s, which corresponds to the flow rate in case of no pump failure in a PWR system. Through the comparisons of test results with those from the reference test with the LPCI flow rate of 0.011 m 3 /s, the following conclusions were obtained: (1) The higher LPCI flow rate resulted in the worse core-cooling in these two tests. The test results show that the lower LPCI flow rate is not necessarily a conservative assumption for the evaluation of the core cooling during the reflood phase of a PWR LOCA. (2) The worse core-cooling in the high LPCI flow rate test is attributed to the lower core-pressure than in the reference test. It is found that the lower core-pressure results from the lower pressure drop through the broken cold leg. (3) It is expected that the current evaluation model(EM) code is still conservative because it usually predicts the low pressure drop through the broken cold leg. (4) The flow oscillation in the cold leg was not significant even in the high LPCI flow rate test before the whole core quench. (author)

  12. Experiment of the downcomer effective water head during a reflood phase of PWR LOCA

    International Nuclear Information System (INIS)

    Sudo, Yukio; Murao, Yoshio

    1978-12-01

    The results and analysis are described of a downcomer effective water head experiment. Downcomer effective water head is the driving force to feed an emergency coolant to the core during a reflood phase of PWR LOCA. The test rig has dimensions of the full-scale height and gap. Experimental conditions are: downcomer wall temperature = 250 0 -- 300 0 C, back pressure = 1 atm, coolant temperature = 98 0 -- 100 0 C, extraction water velocity = 0 -- 2 cm/s, and gap size = 200 mm. The effective water head histories obtained by experiment were compared with those predicted from the heat release from the downcomer walls. The heat release was calculated from the temperature histories indicated by thermocouples instrumented in and on the walls during experiment. The following were revealed: (1) The relation of heat flux and superheat (q vs ΔT sub(s)) obtained in the experiment is much different from that in pool boiling. (2) The predicted effective water head is in good agreement with the experimental one after 120 sec from the initiation of coolant injection. (3) The effect of extraction water velocity is negligible. (4) The effect of initial wall temperatures is evident. (author)

  13. Effects of fuel relocation on reflood in a partially-blocked rod bundle

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Byoung Jae [School of Mechanical Engineering, Chungnam National University, 99 Daehak-ro, Yuseong-gu, Daejeon 34134 (Korea, Republic of); Kim, Jongrok; Kim, Kihwan; Bae, Sung Won [Thermal-Hydraulic Safety Research Division, Korea Atomic Energy Research Division, 111 Daedeok-daero, Yuseong-gu, Daejeon 34057 (Korea, Republic of); Moon, Sang-Ki, E-mail: skmoon@kaeri.re.kr [Thermal-Hydraulic Safety Research Division, Korea Atomic Energy Research Division, 111 Daedeok-daero, Yuseong-gu, Daejeon 34057 (Korea, Republic of)

    2017-02-15

    Ballooning of the fuel rods has been an important issue, since it can influence the coolability of the rod bundle in a large-break loss-of-coolant accident (LBLOCA). Numerous past studies have investigated the effect of blockage geometry on the heat transfer in a partially blocked rod bundle. However, they did not consider the occurrence of fuel relocation and the corresponding effect on two-phase heat transfer. Some fragmented fuel particles located above the ballooned region may drop into the enlarged volume of the balloon. Accordingly, the fuel relocation brings in a local power increase in the ballooned region. The present study’s objective is to investigate the effect of the fuel relocation on the reflood under a LBLOCA condition. Toward this end, experiments were performed in a 5 × 5 partially-blocked rod bundle. Two power profiles were tested: one is a typical cosine shape and the other is the modified shape considering the effect of the fuel relocation. For a typical power shape, the peak temperature in the ballooned rods was lower than that in the intact rods. On the other hand, for the modified power shape, the peak temperature in the ballooned rods was higher than that in the intact rods. Numerical simulations were also performed using the MARS code. The tendencies of the peak clad temperatures were well predicted.

  14. Direct ECC bypass phenomena in the MIDAS test facility during LBLOCA reflood phase

    International Nuclear Information System (INIS)

    Yun, B. J.; Kweon, T. S.; Ah, D. J.; Ju, I. C.; Song, C. H.; Park, J. K.

    2001-01-01

    This paper describes the experimental results of ECC Direct Bypass Phenomena in the downcomer during the late reflood phase of LBLOCA of the reactor that adopts Direct Vessel Injection as a ECC system. The experiments have been performed in MIDAS test facility using superheated steam and water. The test condition was determined, based on the preliminary analysis of TRAC code, from modified linear scaling method of 1/4.93 length scale. To measure the direct bypass fraction according to the nozzle location, separate effect tests have been performed in case of DVI-4(farthest from broken cold leg) injection, DVI-2(closest to broken cold leg) injection, and DVI-2 and 4 injection, respectively. Also the test was carried out varying the steam flow rate greatly to investigate the effect of steam flow rate on the direct bypass fraction of ECC water. Test results show that the direct bypass fraction of ECC water depends significantly on the injected steam mass flow rate. DVI-4 tests show that the direct bypass fraction increases drastically as the steam flow rate increases. However, in DVI-2 test most of the injected ECC water penetrates into lower downcomer. The direct bypass characteristic in each of DVI-2 and DVI-4 tests is reflected into the direct bypass characteristic curve of DVI-2 and 4 test. The steam condensation reaches to the theoretically allowable maximum value

  15. FLECHT-SEASET 21-rod bundle flow blockage heat transfer during reflood

    International Nuclear Information System (INIS)

    Loftus, M.; Hochreiter, L.; Lee, N.

    1983-01-01

    The effect of various flow blockage shapes and distributions during a PWR reflood was investigated using six 21-rod bundles with full length, internally heated, cosine power-shaped electrical rods. The flow blockage shapes, simulating the fuel rod clad ballooning, were made of thin-wall stainless steel tubes hydroformed into a short, concentric shape and along, nonconcentric shape. The blockage sleeves were distributed both coplanar, with all sleeves located at the same elevation, and non-coplanar. The initial and boundary conditions were varied to include parametric effects of pressure, inlet water temperature, and primarily, flooding rate. The initial mid-plane rod temperature was 871 0 C (1600 0 F) in all tests. Rod and vapor temperature measurements were made throughout the rod bundle with emphasis on the blockage region. The rod heat transfer downstream of the blockage was found to be greater for rods in a blocked bundle than for similar rods in an unblocked bundle. The heat transfer improvement decreases both with time after flood initiation and as the distance increased downstream of the blockage. The improvement in the heat transfer is attributed primarily to the breakup of the water droplets entrained in the steam flow. The smaller droplets subsequently evaporate and desuperheat the steam, which then improves the heat transfer between the rods and the steam in and downstream of the blockage zone

  16. Sensitivity study with respect to direction of ADI method during re-flooding in AHWR

    Energy Technology Data Exchange (ETDEWEB)

    Kumar, M.; Mukhopadhyay, D. [Bhabha Atomic Research Centre, Mumbai (India). Reactor Safety Div.; Ghosh, A.K. [Bhabha Atomic Research Centre, Mumbai (India). Raja Ramanna Fellow; Kumar, R. [Indian Institute of Technology, Roorkee (India)

    2015-05-15

    The Advanced Heavy water Reactor (AHWR) is a natural circulation vertical pressure tube type boiling light water cooled and heavy water moderated reactor. As the AHWR fuel bundle quenching under accident condition is designed primarily with radial jets at several axial locations, bottom re-flooding still remain open as another option. Radial direction injection of emergency core cooling leads to rewetting of AHWR fuel cluster in circumferential direction. A 3D fuel pin model has been developed by using Finite Difference Method (FDM) of transient heat conduction equation. Alternating Direction Implicit technique of Finite Difference Method (FDM) has been used for discretisation of numerical equation in different time step at different direction. Sensitivity numerical study with respect to direction of ADI method has been carried out to optimize the time step during the transient as well as steady state and is found that it is insensitivity with direction of solution. Further, to assess influence of circumferential rewetting vis-a-vis axial rewetting. Both the analyses are carried out with same fluid temperature and heat transfer coefficients as boundary conditions. It has been found from the analyses that for radial jet, the circumferential conduction is significant and overall the fuel temperature falls in the quench plane with the initiation of quenching event. The paper discusses the sensitivity study with respect to direction of ADI solution and comparison of numerical results for circumferential and axial rewetting for single pin.

  17. Intravenous immunoglobulin in the management of a rare cause of hemolytic disease of the newborn: Anti-SARA antibodies.

    Science.gov (United States)

    Venkataraman, Rohini; Yusuf, Kamran

    2017-01-01

    Hemolytic disease of newborn (HDN) is a condition that develops in a fetus, when the IgG molecules produced by the mother pass through the placenta and attack the fetal red blood cells. HDN can occur due to Rh and ABO incompatibilities between the mother and the fetus as well as due to other allo-immune antibodies belonging to Kell (K and k), Duffy (Fya), Kidd (Jka and Jkb), and MNS (M, N, S, and s) systems. Role of intravenous immunoglobulin in management of HDN is not clear.SARA red blood cell antigen, first discovered in 1990 is a low frequency antigen. We report, a multiparous female whose pregnancy was complicated by HDN due to anti-SARA antibodies requiring both exchange transfusion and intravenous immunoglobulin. The response was sustained after intravenous immunoglobulin (IVIG) rather than after exchange transfusion.

  18. Experimental and calculation results of the integral reflood test QUENCH-14 with M5 (registered) cladding tubes

    International Nuclear Information System (INIS)

    Stuckert, J.; Birchley, J.; Grosse, M.; Jaeckel, B.; Steinbrueck, M.

    2010-01-01

    The QUENCH-14 experiment investigated the effect of M5 (registered) cladding material on bundle oxidation and core reflood, in comparison with tests QUENCH-06 (ISP-45) that used standard Zircaloy-4 and QUENCH-12 that used VVER E110-claddings. The PWR bundle configuration of QUENCH-14 with a single unheated rod, 20 heated rods, and four corner rods was otherwise identical to QUENCH-06. The test was conducted in principle with the same protocol as QUENCH-06, so that the effects of the change of cladding material could be observed more easily. Pre-test calculations were performed by the Paul Scherrer Institut (Switzerland) using the SCDAPSIM, SCDAP/RELAP5 and MELCOR codes. Follow-on post-test analyses were performed using SCDAP/RELAP5 and MELCOR as part of an ongoing programme of model validation and code assessment. Alternative oxidation correlations were used to examine the possible influence of the M5 (registered) cladding material on hydrogen generation, in comparison with Zircaloy-4. The experiment started with a pre-oxidation phase in steam, lasting ∼3000 s at ∼1500 K peak bundle temperature. After a further temperature increase to maximum bundle temperature of 2073 K the bundle was flooded with 2 g/s/rod water from the bottom. The peak temperature of ∼2300 K was measured on the bundle shroud, shortly after quench initiation. The electrical power was reduced to average value of 2 W/cm during the reflood phase to simulate effective decay heat level. Complete bundle cooling was reached in 300 s after reflood initiation. The development of the oxide layer growth during the test was essentially defined by measurements performed on the three Zircaloy-4 corner rods withdrawn successively from the bundle. The withdrawal of Zircaloy-4 and E110 corner rods after the test allowed a comparison of the different alloys in one test. One heated rod with M5 cladding was withdrawn after the test for a detailed analysis of oxidation degree and measurement of absorbed

  19. Saras Cranes in Palwal District in Southern Haryana are Asking for Immediate Attention for Their Last Rescue Effort

    Directory of Open Access Journals (Sweden)

    Tirshem Kumar Kaushik

    2015-05-01

    Full Text Available Saras Cranes Grus antigone are endangered birds of open wetlands with highly worrying depletion trends being witnessed related with disappearance of marshy and shallow perennial, expansive wetlands throughout northern India. Alongside, massive hunting in 18th, 19th and 20th centuries and even today is another serious cause for their worrisome deterioration. Also, destruction of nests, eggs, fledglings and adults by aboriginals indeliberately or deliberately is causing these cranes to perish sooner than latter, completely. Now, Saras Cranes are found in limited number and domain as four populations in the entire world including India, China, Burma, South East Asia and northern Australia. The population of Indian Saras Crane is pitiably restricted to Etawa and Mainpuri districts of Uttar Pradesh. Stray birds of this species are restricted to Kanha National Park in Madhya Pradesh and in some parts of Gujarat and Assam. It is interesting to note that few pairs have been seen in Faridabad and Palwal districts in southern Haryana, India. These need to be protected and conserved.

  20. Changes in Microbiota in Rumen Digesta and Feces Due to a Grain-Based Subacute Ruminal Acidosis (SARA) Challenge

    DEFF Research Database (Denmark)

    Plaizier, Jan C.; Li, Shucong; Danscher, Anne Mette

    2017-01-01

    The effects of a grain-based subacute ruminal acidosis (SARA) challenge on bacteria in the rumen and feces of lactating dairy cows were determined. Six lactating, rumen-cannulated Danish Holstein cows were used in a cross-over study with two periods. Periods included two cows on a control diet...... and two cows on a SARA challenge. The control diet was a total mixed ration containing 45.5% dry matter (DM), 43.8% DM neutral detergent fiber, and 19.6% DM starch. The SARA challenge was conducted by gradually substituting the control diet with pellets containing 50% wheat and 50% barley over 3 days...... to reach a diet containing 55.6% DM, 31.3% DM neutral detergent fiber, and 31.8% DM starch, which was fed for four more days. Rumen fluid samples were collected at day 7 and 10 of experimental periods. Feces samples were collected on days 8 and 10 of these periods. Extracted DNA from the rumen and feces...

  1. The Sun-Duffey mass effluents calculation model applied to bottom reflooding tests of a single tube performed at the CDTN

    International Nuclear Information System (INIS)

    Ladeira, L.C.D.; Rezende, H.C.

    1993-01-01

    A simple generalized model, developed by K.H. Sun and R.B. Duffey, is applied in this work to calculate the ratio of mass effluents during bottom reflooding of a single tube carried out at the CDTN/CNEN. The results of the benchmark experiments indicate that the accuracy on mass effluence ratio prediction can be within 15% by using the Sun-Duffey model. The reasonable agreement obtained between experimental data and model predictions suggest that it could be used for analysis of single tube reflood tests, in similar conditions. (author)

  2. Entrainment of droplets during the reflood phase of a LOCA and the influence of the channel geometry

    International Nuclear Information System (INIS)

    van der Molen, S.B.; Galjee, F.W.B.M.

    1979-01-01

    This paper describes the different reflood phenomena and the most relevant appearing two phase flow patterns such as the inverted annular, the annular and dispersed flow regimes and the transition between the different regimes. From high speed films it is clear that the onset of entrainment in case of the liquid column type quench mode occurs simultaneously with the transition of churn flow to a dispersed flow whereas in case of the dryout type quench mode with an annular flow at the quench front, the onset of entrainment is caused by the interaction of the vapor flow on the liquid film flow. 14 refs

  3. Assessment of TRAC-PD2 reflood core thermo-hydraulic model by CCTF Test C1-16

    International Nuclear Information System (INIS)

    Sugimoto, Jun

    1982-11-01

    The TRAC-PD2 reflood core thermo-hydraulic model was assessed by CCTF Test C1-16. The measured data were utilized as core boundary conditions in the TRAC calculations. The results indicate that the core inlet liquid temperature and the core heater rod temperatures are in reasonable agreement with data, but the pressure distribution in the core and water pool formation in the upper plenum are not in good agreement. The parametric effects of the droplet critical Weber number, the material properties of the heater rod, the noding of the upper plenum, and the minimum stable film boiling temperature are also discussed. (author)

  4. Drop size measurements and entrainment in APR1400 during LBLOCA reflood phase

    International Nuclear Information System (INIS)

    Lee, Eo Hwak

    2010-02-01

    A study has been performed to investigate droplet size in the nuclear reactor of APR1400 during LBLOCA reflood phase and to develop droplet entrainment and deposition models for SPACE (Safety and Performance CodE) which is a safety analysis tool for PWR being developed in Korea. A freezing technique for measuring the size of droplets was developed to obtain the droplet size distribution in horizontal annular flow in a pipe with a 37.1 mm diameter. Droplets are frozen by using an extremely low temperature nitrogen gas with liquid film extraction. They are then photographed with a microscope and a CCD camera and measured by means of an image process. The results are compared with various experimental data. The droplet sizes measured by the freezing technique are comparable with those measured by other methods at a high superficial air velocity (of 50 m/s). However, because of the film extraction problem, the droplet sizes measured at a low superficial air velocity of less than 40 m/s are higher than those measured by other methods. A present method suggested for predicting the Sauter mean diameter is based on the maximum droplet size correlation for the experimental data, with and without liquid film extraction. The average droplet size is remarkably smaller downstream of the liquid film extractor because large droplets from the liquid film are excluded. In order to understand and to predict a heat transfer between superheated steam and droplets properly during reflood phase of LBLOCA, it is very important to measure broken droplet sizes by spacer grids. A study, therefore, has been performed to investigate droplet size in rod bundles with spacer grids and to develop a spacer grid droplet breakup model for safety analysis codes. Experiments were conducted with liquid droplets (SMD of 300∼700 μm) and various spacer grids at superficial air velocity of 10 m/s and 20 m/s based on FLECHT SEASET. The test channel and the grids were heated to 150 .deg. C to prevent

  5. Drop size measurements and entrainment in APR1400 during LBLOCA reflood phase

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Eo Hwak

    2010-02-15

    A study has been performed to investigate droplet size in the nuclear reactor of APR1400 during LBLOCA reflood phase and to develop droplet entrainment and deposition models for SPACE (Safety and Performance CodE) which is a safety analysis tool for PWR being developed in Korea. A freezing technique for measuring the size of droplets was developed to obtain the droplet size distribution in horizontal annular flow in a pipe with a 37.1 mm diameter. Droplets are frozen by using an extremely low temperature nitrogen gas with liquid film extraction. They are then photographed with a microscope and a CCD camera and measured by means of an image process. The results are compared with various experimental data. The droplet sizes measured by the freezing technique are comparable with those measured by other methods at a high superficial air velocity (of 50 m/s). However, because of the film extraction problem, the droplet sizes measured at a low superficial air velocity of less than 40 m/s are higher than those measured by other methods. A present method suggested for predicting the Sauter mean diameter is based on the maximum droplet size correlation for the experimental data, with and without liquid film extraction. The average droplet size is remarkably smaller downstream of the liquid film extractor because large droplets from the liquid film are excluded. In order to understand and to predict a heat transfer between superheated steam and droplets properly during reflood phase of LBLOCA, it is very important to measure broken droplet sizes by spacer grids. A study, therefore, has been performed to investigate droplet size in rod bundles with spacer grids and to develop a spacer grid droplet breakup model for safety analysis codes. Experiments were conducted with liquid droplets (SMD of 300∼700 μm) and various spacer grids at superficial air velocity of 10 m/s and 20 m/s based on FLECHT SEASET. The test channel and the grids were heated to 150 .deg. C to prevent

  6. TRADE instructional materials for SARA/OSHA training. Volume 2, Managers and supervisors training

    Energy Technology Data Exchange (ETDEWEB)

    1989-03-01

    This document provides instructional materials for an eight-hour training course for managers and supervisors of hazardous waste sites. It is one of three volumes of course materials TRADE is preparing to help DOE contractor training staff comply with 29 CFR 1910.120, the Occupational Health and Safety Administration (OSHA) rule that implements Title I of the Superfund Amendments and Reauthorization Act (SARA) of 1986. OSHA`s final rule for hazardous waste operators was published in the Federal Register of March 6, 1989 (54 FR 9294). Combined with the materials in Volumes I and III and with appropriate site-specific information, these materials will help DOE contractors to meet the requirements of 1910.120 (e) that ``on-site management and supervisors directly responsible for, or who supervise employees engaged in, hazardous waste operations`` receive the same initial training as that of the employees they supervise and at least eight additional hours of specialized training in managing hazardous waste operations.

  7. Nuclear spectroscopy of exotic nuclei with the Sara/Igisol facility

    International Nuclear Information System (INIS)

    Beraud, R.; Emsallem, A.; Astier, A.; Duffait, R.; Le Coz, Y.; Redon, N.; Barneoud, D.; Genevey, J.; Gizon, A.

    1994-11-01

    The authors review their recent studies on alpha and beta decay of exotic nuclei performed with the on-line mass separator at the Igisol/Sara facility in Grenoble. The experiments using charged particle induced fission have given new information on production cross section and properties of n-rich nuclei with A=110-130 whereas by means of heavy ion induced fusion evaporation reactions the authors have investigated two regions close to the proton drip line around A=180 and A=130. This paper gives first a brief description of the Igisol technique and shows its application in case of two different production modes: charged particle-induced fission and heavy ion -induced fusion-evaporation reactions. The systematic study of the low-lying levels in n-rich Ru isotopes has allowed to show an axial symmetry breaking, whereas complementary investigations are necessary to clarify the case of 180 Tl decay. A number of new spectroscopic data such as new isotopes identification have been gained in the region of light rare earth nuclei. (N.T.)

  8. Instructional materials for SARA/OSHA training. Volume 1, General site working training

    Energy Technology Data Exchange (ETDEWEB)

    Copenhaver, E.D.; White, D.A.; Wells, S.M. [Oak Ridge National Lab., TN (United States)

    1988-04-01

    This proposed 24 hour ORNL SARA/OSHA training curriculum emphasizes health and safety concerns in hazardous waste operations as well as methods of worker protection. Consistent with guidelines for hazardous waste site activities developed jointly by National Institute for Occupational Safety and Health, Occupational Safety and Health Administration, US Coast Guard, and the Envirorunental Protection Agency, the program material will address Basic Training for General Site Workers to include: ORNL Site Safety Documentation, Safe Work Practices, Nature of Anticipated Hazards, Handling Emergencies and Self-Rescue, Employee Rights and Responsibilities, Demonstration of Use, Care, and Limitations of Personal Protective, Clothing and Equipment, and Demonstration of Monitoring Equipment and Sampling Techniques. The basic training courses includes major fundamentals of industrial hygiene presented to the workers in a format that encourages them to assume responsibility for their own safety and health protection. Basic course development has focused on the special needs of ORNL facilities. Because ORNL generates chemical wastes, radioactive wastes, and mixed wastes, we have added significant modules on radiation protection in general, as well as modules on radiation toxicology and on radiation protective clothing and equipment.

  9. La difesa della donna ebrea: Sara Copio Sullam e Debora Ascarelli

    Directory of Open Access Journals (Sweden)

    Umberto Fortis

    2014-04-01

    Full Text Available Sara Copio Sullam and Debora Ascarelli, the best-known Jewish women poets of the age of the Italian ghetto, have often been studied with a focus on the distinctive features of their writing: the former as a translator of sacred texts, the latter as the author of original verses, sometimes written as a risposta per le rime (reply through rhymes or in defence of her orthodoxy. They share, however, a common theme, which has often been neglected: the defence of the Jewish woman, which is overt in some of Copio’s sonnets and prose, whereas it has not yet been properly pointed out in some of Ascarelli’s verses. This paper aims at bringing this theme to the fore not only in Copio, through a rereading of some passages of her Manifesto, but also in Debora Ascarelli, through an analysis of her few original verses. These hendecasyllables certainly reflect the Petrarchan and classicistic atmosphere of the late 16th century in Rome, but they are far from the mainstream modes of women’s poetry of the age. They allow us, therefore, to highlight, besides the differences, the similarities between the two poetesses; their commitment, in the late 16th and early 17th century, to the intellectual and moral defence of the Jewish woman, in a context of general depreciation of women, but also in the background of the claim to the “nobility and excellence of women”.

  10. Reading Sara Pujol Russell’s Poetry of Contemplation and Connection

    Directory of Open Access Journals (Sweden)

    Anita M. Hart

    2012-06-01

    Full Text Available Sara Pujol Russell’s poetry captures a process of expanding consciousness and personal renewal. Through contemplation and attention to nature, the poet-speaker in her works generates a sense of connection that moves her beyond daily concerns. Pujol’s poetry is both metaphysical and also different in that it resists easy classification and is not representative of mainstream trends. This essay approaches the distinctiveness of Pujol’s work by studying selected poems from her third book of poetry in Spanish, Para decir sí a la carencia, sí a la naranja, al azafrán en el pan (2004 ‘To Say Yes to Lack, Yes to the Orange, to the Saffron in the Bread.’ Incorporating philosopher María Zambrano’s thoughts on contemplation, it shows Pujol’s poet-speaker establishing a connection with nature and spirit, experiencing a heightened consciousness, and searching for expression. The poetic language is characterized by vision, intimacy, enigma, and contradiction. In its subjective, intuitive way, Pujol’s work reveals the poet-speaker’s winding path of discovery and challenges the reader to look closely inside and outside in engaging life’s mysteries.

  11. SAPHIRE technical reference manual: IRRAS/SARA Version 4.0

    International Nuclear Information System (INIS)

    Russell, K.D.; Atwood, C.L.; Sattison, M.B.; Rasmuson, D.M.

    1993-01-01

    This report provides information on the principles used in the construction and operation of Version 4.0 of the Integrated Reliability and Risk Analysis System (IRRAS) and the System Analysis and Risk Assessment (SARA) system. It summarizes the fundamental mathematical concepts of sets and logic, fault trees, and probability. The report then describes the algorithms that these programs use to construct a fault tree and to obtain the minimal cut sets. It gives the formulas used to obtain the probability of the top event from the minimal cut sets, and the formulas for probabilities that are appropriate under various assumptions concerning repairability and mission time. It defines the measures of basic event importance that these programs can calculate. The report gives an overview of uncertainty analysis using simple Monte Carlo sampling or Latin Hypercube sampling, and states the algorithms used by these programs to generate random basic event probabilities from various distributions. Further references are given, and a detailed example of the reduction and quantification of a simple fault tree is provided in an appendix

  12. Evaluation report on CCTF core-II reflood test C2 - 8 (Run 67)

    International Nuclear Information System (INIS)

    Akimoto, Hajime; Iguchi, Tadashi; Okubo, Tsutomu; Murao, Yoshio; Okabe, Kazuharu; Sugimoto, Jun.

    1987-01-01

    In order to study the system pressure effect of the core cooling and flow behavior during the reflood phase of a PWR LOCA, a test was performed with CCTF under the system pressure pf 0.15 MPa as a counterpart test of the CCTF test C2-1 (system pressure 0.42 MPa) and the CCTF test C2-4 (system pressure 0.20 MPa). Through the comparisons of results from these three tests, the following conclusions were obtained: (1) The higher system pressure resulted in the lower temperature rise, the shorter turnaround time and the shorter quench time as observed in the CCTF Core-I system pressure effect tests. (2) The higher system pressure resulted in higher core water head, higher upper plenum water head, higher mass flow rate through the primary loops. On the other hand, the higher system pressure resulted in lower downcomer water head and lower pressure drop through the primary loops and the broken cold leg. These system pressure effects on the flow behavior in the primary system are almost the same as observed in the system pressure effect tests in the CCTF Core-I test series. (3) Before the mixture level in the upper plenum reached the level of the hot leg nozzle, the loop flow resistance coefficient of the intact loops was nearly constant regardless of the system pressure. After the mixture level reached the level of the hot leg nozzle, the loop flow resistance coefficient was increased due to the water accumulation in the hot leg piping and the inlet plenum of the steam generator in these tests. (J.P.N.)

  13. Evaluation report on CCTF core-II reflood test C2-6 (Run 64)

    International Nuclear Information System (INIS)

    Akimoto, Hajime; Iguchi, Tadashi; Sugimoto, Jun; Okubo, Tsutomu; Murao, Yoshio; Okabe, Kazuharu.

    1985-03-01

    In order to evaluate the effect of the radial power profile on the system behavior and the core thermal hydraulic behavior during the reflood phase of a PWR LOCA, a test was performed using the Cylindrical Core Test Facility(CCTF) with the flat radial power profile. The test was conducted with the same total core power as that of the steep radial power test C2-5(Run 63). Through the comparisons of the results from these two tests, the following conclusions were obtained: (1) The radial power profile in the core has weak effect on the thermal hydraulic behavior in the primary system except the core. (2) Almost the same differential pressure was observed at various elevations in the periphery of the core regardless of different radial power profile. The result suggests that the core differential pressure is determined mainly by the total power and the total stored energy rather than by the local power and the local stored energy. (3) The test results support the single channel core model with the average power rod used in the reactor safety analysis codes such as REFLA-1DS, WREM for the evaluation of the overall system behavior. (4) In the steep radial power test, the heat transfer coefficient in the central(high power) region was higher than that in the peripheral(low power) region. The tendency was not explained by the estimation with the heat transfer correlation developed by Murao and Sugimoto assuming that the void fraction was uniform in a horizontal cross section. It is necessary to study more the dependency of core heat transfer on the radial power profile in the wide core. (author)

  14. Evaluation report on CCTF CORE-I REFLOOD TEST Cl-4 (Run 13) and Cl-15 (Run 24)

    International Nuclear Information System (INIS)

    Sudoh, Takashi; Murao, Yoshio.

    1983-08-01

    The tests Cl-4 and Cl-15 were performed with the Cylindrical Core Test Facility (CCTF) to investigate the effects of the depressurization process to simulate the refill phase, and the effects of the nitrogen to be injected after the end of the accumulator injection on the thermo-hydraulic behavior in the core and primary loop system during refill and reflood phases. In these tests, after the lower plenum was filled to 0.9m level with saturated water at 0.6 MPa, the accumulator water was injected into three intact cold legs in the depressurization period from 0.6 MPa to 0.2 MPa. The water in the lower plenum voided during the depressurization and the significant steam condensation occurred in or near the intact cold legs. The condensation caused high steam flow rate in the intact loops and the lower plenum flashing resulted in suppressed core water accumulation. The slightly lower core heat transfer coefficient due to the less core water caused the higher turnaround temperature and the longer quench time than those of the normal reflood test without the depressurization process. The nitrogen injection followed the accumulator injection was allowed in the test Cl-15. However, significant effects of the nitrogen injection was not observed. (author)

  15. Evaluation report on CCTF Core-II reflood test second shakedown test, C2-SH2 (Run 54)

    International Nuclear Information System (INIS)

    Iguchi, Tadashi; Sugimoto, Jun; Akimoto, Hajime; Okubo, Tsutomu; Murao, Yoshio

    1985-03-01

    A low power test (the initial averaged linear power density = 1.18 kW/m) and the base case test (1.4 kW/m) were performed with the Cylindrical Core Test Facility (CCTF) at Japan Atomic Energy Research Institute, in order to study the effect of the power on the reflood phenomena. The former linear power density corresponds nearly to the scaled linear power density based on the current safety evaluation criterio. During the early period of the reflood ( 200s) the heat transfer coefficient became higher and resultantly the quench front advanced faster in the low power test. The core flooding rate was nearly identical between both tests, independently of the different power. The insensitiveness of the power to the core flooding rate was also observed in FLECHT-SET performed in the USA. A significatn large differential pressure oscillation at ECC ports was experienced in the low power test, and it may be important for the long term core cooling although it has not been taken note on the previous studies. (author)

  16. Measuring the socio-economic impacts of agroforestry projects in the Philippines

    Science.gov (United States)

    Evan Mercer; Belita Vega; Hermie Francisco; Robin Maille

    1994-01-01

    Conventional wisdom suggests that agroforestry projects can provide both ecological and economic benefits. Most agroforestry project evaluations, however, have failed to adequately assess the soci0-economic impacts. For example, a review of 108 agroforestry project impact evaluations by Sara Scherr of IFPRJ reported that only 8% assessed economic costs or benefits, 5%...

  17. Study of top reflooding in case of severe accident and in particular oxidation of Uranium, Zirconium, Oxygen melts; Etude du renoyage par le haut en cas d'accident grave et en particulier oxydation des melanges (U,Zr,O)

    Energy Technology Data Exchange (ETDEWEB)

    Brunet-Thibault, E

    2006-12-15

    In 1979, the Three Mile Island (TMI) accident occurred in United States and accelerated research activities in the field of severe accidents. Severe accident management procedures imply massive water injections to flood the core. The work of this thesis bent principally over this reflooding. The first part of the study concerns the core oxidation enhancement during the reflooding phase which leads to a rough increase of the concentration of burnable hydrogen in the containment. This is why the study carried on the analysis of the contribution of the oxidation of U-Zr-O mixtures, towards the total production of hydrogen during reflooding. In the second part, the study concerns top flooding modelling i.e.: with injection of water in the hot legs. Here, we attempted to define bases and realize a model allowing to describe this type of reflooding. These models were validated on the simulation of the parameter with MAAP4 code. (author)

  18. Women Empowerment in the Realms of Institutionalized Religion and Patriarchy: El Saadawi’s Firdaus and Yezierska’s Sara as Examples

    Directory of Open Access Journals (Sweden)

    Abdullah K. Shehabat

    2016-09-01

    Full Text Available This paper explains how the two protagonists, Firdaus and Sara, successfully paved their own ways in search of self-liberation despite the authoritarian patriarchy and institutionalized religions that plagued them. El Saadawi's Woman at Point Zero and Yezierska’s Bread Givers represent the fruitful struggle these protagonists experienced as they come to forge an identity and be themselves. The paper argues that the protagonists manage to free themselves, establish their own spiritual homes at their own homes and assert the potentials of their femininity despite their endings. Empowered by the powers of reading, strong will and meticulous work, the protagonists were able to realize their own material independence and achieve their lifelong ambitions. However, through Firdaus' and Sara's journeys of breaking their silence, they were subject to different patterns of self-annihilation. While Firdaus was sentenced to death for killing a pimp, Sara embraced living under the hegemony of an authoritarian husband.

  19. Systems Analysis Programs for Hands-on Integrated Reliability Evaluations (SAPHIRE), Version 5.0. Volume 5, Systems Analysis and Risk Assessment (SARA) tutorial manual

    International Nuclear Information System (INIS)

    Sattison, M.B.; Russell, K.D.; Skinner, N.L.

    1994-07-01

    The Systems Analysis Programs for Hands-on Integrated Reliability Evaluations (SAPHIRE) refers to a set of several microcomputer programs that were developed to create and analyze probabilistic risk assessments (PRAs) primarily for nuclear power plants. This volume is the tutorial manual for the Systems Analysis and Risk Assessment (SARA) System Version 5.0, a microcomputer-based system used to analyze the safety issues of a open-quotes familyclose quotes [i.e., a power plant, a manufacturing facility, any facility on which a probabilistic risk assessment (PRA) might be performed]. A series of lessons is provided that guides the user through some basic steps common to most analyses performed with SARA. The example problems presented in the lessons build on one another, and in combination, lead the user through all aspects of SARA sensitivity analysis capabilities

  20. SARA South Observations and Analysis of the Solar Type, Totally Eclipsing, Over Contact Binary, PY Aquarii

    Science.gov (United States)

    Chamberlain, Heather; Samec, Ronald G.; Caton, Daniel Bruce; Van Hamme, Walter

    2018-01-01

    PY Aqr (GSC 05191-00853) is a solar Type (T ~ 5750K) eclipsing binary. It was observed in July to October, 2017 at Cerro Tololo in remote mode with the 0.6-m SARA South reflector. Two times of minimum light were calculated from our present observations, a primary and a secondary eclipse:HJD Min I = 2457951.7762±0.0006 HJD Min II = 2458019.5295±00.0003. Both weighted as 1.0.In addition, four timings were determined from online data given in IBVS 5600 and five observations at minima were determined from archived All Sky Automated Survey Data:HJD Min I = 2452908.3165, 2452912.33612 HJD Min II = 2452877.5621, 2452913.34465. All weighted as 0.5.ASAS Observations at minima: 2452094.688, 2453478.882, 2453266.576, 2452093.685 and 54729.600. Each weighted as 0.10The following linear and quadratic ephemerides were determined from all available times of minimum light:JD Hel Min I=2452951.7443±0.0008d + 0.402093441±0.000000099 X E {1} JD Hel Min I=2452951.7439±0.0007d + 0.4020912±0.0000007 X E +0.00000000018 ± 0.00000000006 X E2 {2}A BVRI Bessell filtered simultaneous Wilson-Devinney Program (W-D) solution reveals that the system has a mass ratio of ~0.34 and a component temperature difference of only ~40 K. One low luminosity (Tfact ~ 0.94, ~66 degree radius) large cool region of spots was iterated on the primary component in the WD Synthetic Light Curve computations. It appears in the Southern Hemisphere (colatitude 155 degrees). The Roche Lobe fill-out of the binary is ~17%. The inclination is ~86 degrees. An eclipse duration of ~10 minutes was determined for the primary eclipse and the light curve solution. Additional and more detailed information is given in this report.

  1. DETERMINACIÓN DE LAS FRACCIONES SARA DE ASFALTOS COLOMBIANOS ENVEJECIDOS AL MEDIO AMBIENTE EMPLEANDO CROMATOGRAFÍA LÍQUIDA EN COLUMNA DETERMINAÇÃO DAS FRAÇÕES SARA DE ASFALTOS COLOMBIANOS ENVELHECIDOS AO MÉDIO AMBIENTE EMPREGANDO CROMATOGRAFIA LÍQUIDA EM COLUNA DETERMINATION OF SARA FRACTIONS OF ENVIRONMENTALLY AGED COLOMBIAN ASPHALTS USING LIQUID CHROMATOGRAPHY COLUMN

    Directory of Open Access Journals (Sweden)

    Fredy Alberto Reyes

    2012-06-01

    Full Text Available En este artículo presentamos un método basado en cromatografía líquida en columna para cuantificar la composición química de los cementos asfálticos fabricados en Colombia, sometidos al medio ambiente, mediante la determinación de las fracciones SARA. El método fue aplicado sobre películas de asfalto 60/70 y 80/100 para determinar los cambios en la composición química del material luego de ser expuesto durante 12 meses a las condiciones de intemperie de la ciudad de Bogotá; los ensayos de SARA fueron efectuados para el asfalto original a 1, 3, 6, 9 y 12 meses respectivamente. Los fraccionamientos SARA evidenciaron que el envejecimiento produjo una disminución de la fracción de aromáticos y un incremento en la de asfaltenos respecto al asfalto no envejecido. La disminución de los compuestos aromáticos y de resinas pudo ser responsable del endurecimiento observado en los asfaltos, que presentaron una consistencia dura y quebradiza, lo que está de acuerdo con la obtención de índices coloidales elevados. El método empleado permitió establecer correlaciones entre la composición química del asfalto y sus propiedades mecánicas.Neste artigo apresentamos um método baseado em cromatografia líquida em coluna para quantificar a composição química dos cimentos asfálticos fabricados em Colômbia, submetidos ao médio ambiente, mediante a determinação das frações SARA. O método foi aplicado sobre películas de asfalto 60/70 e 80/100 para determinar as mudanças na composição química do material depois de ser exposto durante 12 meses às condições de intempérie da cidade de Bogotá; os ensaios de SARA foram efetuados para o asfalto original a 1, 3, 6, 9 e 12 meses respectivamente. Os fraccionamentos SARA evidenciaram que o envelhecimento produziu uma diminuição da fração de aromáticos e um incremento na de asfaltenos com respeito ao asfalto não envelhecido. A diminuição dos compostos aromáticos e de resinas p

  2. Modeling of quench front progression and heat transfer by radiation during reflooding of a tubular test section

    International Nuclear Information System (INIS)

    Clement, P.; Deruaz, R.

    1976-01-01

    Heat transfer modeling is presented in the scope of emergency core cooling. The rewetting of a hot dry wall during reflooding is a conduction-controlled phenomenon described by a model of heat-transfer coefficient. Upstream of the quench front, a two-dimensional approach involving both axial and transverse (or radial) heat conduction is discussed in view of thick walls, high quench front velocities and nucleate boiling. Downstream of the quench-front, high wall temperatures are reached so that a thermal radiation model is required to separate the different mechanisms of heat transfer. An attempt is made to consider radiation between walls, water droplets and vapor, with scattering emission and absorption of the two phases

  3. Evaluation report on CCTF core-I reflood tests Cl-17(Run 36) and Cl-20(Run 39)

    International Nuclear Information System (INIS)

    Murao, Yoshio; Iguchi, Tadashi

    1983-02-01

    In the safety analysis of the reflood phase of a PWR LOCA, the core thermo-hydrodynamic behavior is analyzed as a phenomena in a single channel core. In other words, the core thermo-hydrodynamic behavior is treated one-dimensionally. In order to confirm the validity of the one-dimensional treatment, tests named Asymmetric power test Cl-17(Run 36) and Asymmetric temperature test Cl-20(Run 39) were performed, whose test conditions were similar to the base case test Cl-5(Run 14) (the reference test for the parametric effect tests) except for the power distribution and the initial temperature distribution in core, respectively. First the results of the base case test were investigated. And the results of Asymmetric power test and Asymmetric temperature test were compared with the results of the base case test. The main conclusions are as follows: (1) The water accumulation was observed along the whole core even above quench front almost simultaneously just after reflood initiation and almost terminated within 20 to 30 seconds. The flow pattern was recognized as a slug flow. (2) In the lower two-thirds of the core, bottom quench was observed and the core water accumulation was one-dimensional even under the thermally asymmetric conditions. (3) In the upper portion of the core, the multi-dimensional effect was observed, i.e. the top quench occurred locally. (4) The water accumulation behavior or void fraction in the lower two-thirds of the core, i.e. our concerning region for the peak clad temperature analysis, and the core behavior for system analysis can be one-dimensionally analyzed with a representing single channel core. (author)

  4. PKL/K9, Refill and Reflood Experiment in a Simulated PWR Primary System (PKL)

    International Nuclear Information System (INIS)

    1981-01-01

    reflood process within a pressure vessel considering the influence of the simulated primary loops of a pressurized water reactor (PWR). As to the number of rods and the cross-sections of vessel and components the PKL test-facility is scaled down to 1:134 of a typical West Germany PWR. The elevations and locations have been designed in order to reproduce substantially the original extension. Compared to other cold leg injection tests in the same facility (K5. 3a, K5. 4a) test K9 differs in a uniform radial power profile in the core, an increased temperature of injected Emergency Core Cooling (ECC) water (feed water, from 35 to 53 deg. C), an injection mass flow rate highly reduced to 1:3, and a history of it corresponding to that of a typical US-PWR, on the average somewhat higher maximum initial temperatures in the bundle, and a smaller bundle heating power during the initial phase

  5. REFLA-1D/MODE 1: a computer program for reflood thermo-hydrodynamic analysis during PWR-LOCA user's manual

    International Nuclear Information System (INIS)

    Murao, Yoshio; Sugimoto, Jun; Okubo, Tsutomu

    1981-01-01

    This manual describes the REFLA-1D/MODE 1 reflood system analysis code. This code can solve the core thermo-hydrodynamics under forced flooding conditions and gravity feed conditions in a system similar to FLECHT-SET phase A. This manual describes the REFLA-1D/MODE 1 models and provides application information required to utilize REFLA-1D/MODE 1. (author)

  6. Reflooding phenomena of German PWR estimated from CCTF [Cylindrical Core Test Facility], SCTF [Slab Core Test Facility] and UPTF [Upper Plenum Test Facility] results

    International Nuclear Information System (INIS)

    Murao, Y.; Iguchi, T.; Sugimoto, J.

    1988-09-01

    The reflooding behavior in a PWR with a combined injection type ECCS was studied by comparing the test results from Cylindrical Core Test Facility (CCTF), Slab Core Test Facility (SCTF) and Upper Plenum Test Facility (UPTF). Core thermal-hydraulics is discussed mainly based on SCTF test data. In addition, the water accumulation behavior in hot legs and the break-through characteristics at tie plate are discussed

  7. Construct Validity and Reliability of the SARA Gait and Posture Sub-scale in Early Onset Ataxia

    Directory of Open Access Journals (Sweden)

    Tjitske F. Lawerman

    2017-12-01

    Full Text Available Aim: In children, gait and posture assessment provides a crucial marker for the early characterization, surveillance and treatment evaluation of early onset ataxia (EOA. For reliable data entry of studies targeting at gait and posture improvement, uniform quantitative biomarkers are necessary. Until now, the pediatric test construct of gait and posture scores of the Scale for Assessment and Rating of Ataxia sub-scale (SARA is still unclear. In the present study, we aimed to validate the construct validity and reliability of the pediatric (SARAGAIT/POSTURE sub-scale.Methods: We included 28 EOA patients [15.5 (6–34 years; median (range]. For inter-observer reliability, we determined the ICC on EOA SARAGAIT/POSTURE sub-scores by three independent pediatric neurologists. For convergent validity, we associated SARAGAIT/POSTURE sub-scores with: (1 Ataxic gait Severity Measurement by Klockgether (ASMK; dynamic balance, (2 Pediatric Balance Scale (PBS; static balance, (3 Gross Motor Function Classification Scale -extended and revised version (GMFCS-E&R, (4 SARA-kinetic scores (SARAKINETIC; kinetic function of the upper and lower limbs, (5 Archimedes Spiral (AS; kinetic function of the upper limbs, and (6 total SARA scores (SARATOTAL; i.e., summed SARAGAIT/POSTURE, SARAKINETIC, and SARASPEECH sub-scores. For discriminant validity, we investigated whether EOA co-morbidity factors (myopathy and myoclonus could influence SARAGAIT/POSTURE sub-scores.Results: The inter-observer agreement (ICC on EOA SARAGAIT/POSTURE sub-scores was high (0.97. SARAGAIT/POSTURE was strongly correlated with the other ataxia and functional scales [ASMK (rs = -0.819; p < 0.001; PBS (rs = -0.943; p < 0.001; GMFCS-E&R (rs = -0.862; p < 0.001; SARAKINETIC (rs = 0.726; p < 0.001; AS (rs = 0.609; p = 0.002; and SARATOTAL (rs = 0.935; p < 0.001]. Comorbid myopathy influenced SARAGAIT/POSTURE scores by concurrent muscle weakness, whereas comorbid myoclonus predominantly influenced

  8. sarA negatively regulates Staphylococcus epidermidis biofilm formation by modulating expression of 1 MDa extracellular matrix binding protein and autolysis‐dependent release of eDNA

    DEFF Research Database (Denmark)

    Christner, Martin; Heinze, Constanze; Busch, Michael

    2012-01-01

    to biofilm formation in mutant 1585ΔsarA. Increased eDNA amounts indirectly resulted from upregulation of metalloprotease SepA, leading to boosted processing of autolysin AtlE, in turn inducing augmented autolysis and release of eDNA. Hence, this study identifies sarA as a negative regulator of Embp‐ and e...

  9. Pushing and Pulling Sara: A Case Study of the Contrasting Influences of High School and University Experiences on Engineering Agency, Identity, and Participation

    Science.gov (United States)

    Godwin, Allison; Potvin, Geoff

    2017-01-01

    This manuscript reports a longitudinal case study of how one woman, Sara, who had previously considered dropping out of high school, authored strong mathematics and science identities and purposefully exhibited agency through her experiences in high school science. These experiences empowered her to choose an engineering major in college; however,…

  10. Staphylococcus aureus Quorum Regulator SarA Targeted Compound, 2-[(Methylaminomethyl]phenol Inhibits Biofilm and Down-Regulates Virulence Genes

    Directory of Open Access Journals (Sweden)

    P. Balamurugan

    2017-07-01

    Full Text Available Staphylococcus aureus is a widely acknowledged Gram-positive pathogen for forming biofilm and virulence gene expressions by quorum sensing (QS, a cell to cell communication process. The quorum regulator SarA of S. aureus up-regulates the expression of many virulence factors including biofilm formation to mediate pathogenesis and evasion of the host immune system in the late phases of growth. Thus, inhibiting the production or blocking SarA protein might influence the down-regulation of biofilm and virulence factors. In this context, here we have synthesized 2-[(Methylaminomethyl]phenol, which was specifically targeted toward the quorum regulator SarA through in silico approach in our previous study. The molecule has been evaluated in vitro to validate its antibiofilm activity against clinical S. aureus strains. In addition, antivirulence properties of the inhibitor were confirmed with the observation of a significant reduction in the expression of representative virulence genes like fnbA, hla and hld that are governed under S. aureus QS. Interestingly, the SarA targeted inhibitor showed negligible antimicrobial activity and markedly reduced the minimum inhibitory concentration of conventional antibiotics when used in combination making it a more attractive lead for further clinical tests.

  11. Investigation of typicality of non-nuclear rod and fuel-clad gap effect during reflood phase, and development of a FEM thermal transient analysis code HETFEM

    International Nuclear Information System (INIS)

    Sudoh, Takashi

    1981-06-01

    The objective of this study are: 1) Evaluate the capability of the electrical heater for simulating the fuel rod during the reflood phase, and 2) To investigate the effect of the clad-fuel gap in the fuel rod on the clad thermal response during the reflood phase. A computer code HETFEM which is the two dimensional transient thermal conductivity analysis code utilized a finite element method is developed for analysing thermal responses of heater and fuel rod. The two kinds of electrical heaters and a fuel rod are calculated with simple boundary conditions. 1) direct heater (former JAERI reflood test heater), 2) indirect heater (FLECHT test heater), 3) fuel rod (15 x 15 type in Westinghouse PWR). The comparison of the clad temperature responses shows the quench time is influenced by the thermal diffusivity and gap conductance. In the conclusion, the ELECHT heater shows atypicality in the clad temperature response and heat releasing rate. But the direct heater responses are similar to those of the fuel rod. For the gap effect on the fuel rod behavior, the lower gap conductance causes sooner quench and less heat releasing rate. This calculation is not considered the precursory cooling which is affected by heat releasing rate at near and below the quench front. Therefore two dimensional calculation with heat transfer related to the local fluid conditions will be needed. (author)

  12. The acquisition and supervision system of S.A.R.A.'s (Accelerator system Rhone-Alpes) parameters

    International Nuclear Information System (INIS)

    Iazzourene, F.

    1982-01-01

    The acquisition and supervision system of SARA's (Systeme Accelerateur Rhone-Alpes) parameters is built up. The basic hardware consists of: - A PDP 11/10 computer with a 64 K bytes memory capacity. The system and load device is a floppy disk of 28 megabytes capacity. - A CAMAC crate including a data logger with 224 input channels, a terminal driver (JTY21) and three modules designed for reading out a few digital data, for instance polarities of power supplies. The software provides three distinct programs: AKITS, which uses 3 commands, detects and signals functioning defects in the CAMAC modules used. AKIDO which uses 11 commands, is the acquisition and organization program of the accelerator's functioning parameters. AKISUR is the supervision program of the functioning parameter's stability, within a fixed gap, during the accelerator running [fr

  13. Memoria de la guerra civil española. Entre el sol y la tormenta de Sara Berenguer

    Directory of Open Access Journals (Sweden)

    Helena López

    2013-07-01

    Full Text Available En este artículo pretendo analizar dos cuestiones en relación con las memorias de guerra de la militante anarquista Sara Berenguer. En primer lugar, quiero atender a las estrategias discursivas (clase, género, sexualidad de construcción de la subjetividad en este texto. Además, me interesa indagar cómo estos discursos se interseccionan con la posición espacio-temporal (tiempo de la memoria y tiempo-espacio del exilio del sujeto autobiográfico. Mi objetivo principal es proponer una problematización de los conceptos de “memoria colectiva” y de “experiencia femenina” y reivindicar, por lo tanto, la relevancia tanto teórica como política de análisis críticos basados en narrativas personales.

  14. Os suínos da raça Bísara – oportunidades e desafios

    OpenAIRE

    Carvalho, Marieta

    2015-01-01

    A procura mundial de produtos de origem animal aumentará cerca de 70% em 2050. Estima-se que mil milhões de pobres dependam dos animais para a sua alimentação e criação de riqueza1. A carne de porco é um dos alimentos mais consumidos mundialmente, representando em 2012: 43,3% em todo o mundo2, 45,9% na União Europeia1 e 39,8 % em Portugal da carne total consumida3. Este trabalho tem como objetivo, fazer uma caracterização atual da suinicultura, com base nos suínos da raça Bísara, enumer...

  15. Assessment of current safety evaluation analysis on reflood behavior during PWR-LOCA by using CCTF data

    International Nuclear Information System (INIS)

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

    1987-01-01

    This paper describes an assessment result on conservatism of current safety analysis concerning reflood behavior during a LOCA in a PWR by using the experimental data with cylindrical core test facility (CCTF) performed at Japan Atomic Energy Research Institute (JAERI). WREM code is selected for a representative of current safety analyses. The predicted peak clad temperature with the WREM code was higher than the data, and it was confirmed that the WREM code had the overall conservatism against CCTF data. The WREM code predicted the reasonable core boundary conditions and it was found that the conservatism of the code came mainly from the calculations on the incore thermal hydraulics and clad temperature. In addition, it was found that the conservatism of the WREM code against the CCTF data could be attributed to the neglection of horizontal fluid mixing between subchannels, the neglection of the heat transfer enhancement due to the radial core power profile, and the usage of the heat transfer correlations conservative against CCTF data. (author)

  16. Two-dimensional thermal-hydraulic behavior in core in SCTF Core-II forced feed reflood tests

    International Nuclear Information System (INIS)

    Iwamura, Takamichi; Sobajima, Makoto; Okubo, Tsutomu; Ohnuki, Akira; Abe, Yutaka; Adachi, Hiromichi

    1987-01-01

    Major purpose of the Slab Core Test Program is to investigate the two-dimensional thermal-hydraulic behavior in the core during the reflood phase of a PWR-LOCA. It was revealed in the previous Slab Core Test Facility (SCTF) Core-II test results that the heat transfer was enhanced in the higher power bundles and degraded in the lower power bundles in the non-uniform radial power profile tests. In order to separately evaluate the effect of the radial power (Q) distribution itself and the effect of the radial temperature (T) distribution, four tests were performed with steep Q and T, flat Q and T, steep Q and flat T, and flat Q and steep T. Based on the test results, it was concluded that the radial temperature distribution which accompanied the radial power distribution was the dominant factor of the two-dimensional thermal-hydraulic behavior in the core during the initial period. Selected data from these four tests are also presented in this report. Some data from Test S2-12 (steep Q, T) were compared with TRAC post-test calculations performed by the Los Alamos National Laboratory. (author)

  17. Feminism and Faith: Exploring Christian Spaces in the Writing of Sara Maitland and Michèle Roberts

    Directory of Open Access Journals (Sweden)

    Arina LUNGU-CIRSTEA

    2011-03-01

    Full Text Available En 1983, les féministes britanniques Sara Maitland et Jo Garcia ont publié Walking on the Water (London : Virago, une collection d’essais, de récits, de poèmes et de photos produits par des femmes sur le thème de la spiritualité. Les contributrices ont été en particulier invitées à explorer la relation entre leur identité féministe et leurs croyances religieuses. Le ton de ces contributions varie fortement, allant de l’envie passionnée de concilier les objectifs du féminisme avec le christianisme à un rejet total de l’Eglise comme institution patriarcale suprême. Cet article met en dialogue des récits diamétralement opposés du rapport entre christianisme et féminisme en s’intéressante plus particulièrement à deux des contributrices, Sara Maitland (1950 - et Michèle Roberts (1949 - . Ces deux écrivaines, qui se sont activement impliquées dans les mouvements féministes des années 1970, ont toutes deux lutté pour se réconcilier avec leur héritage chrétien. Néanmoins, alors que Maitland tente essentiellement de revisiter le christianisme en y incorporant les points essentiels d’une idéologie féministe, Roberts sent le besoin impérieux de se défaire de son identité religieuse afin de devenir indépendante ; en effet, dans son autobiographie Paper Houses (2007 elle décrit son éducation catholique comme “autoritaire et misogyne” (16. Cet article explore les façons dont l’identité spirituelle se construit dans le jeu complexe des interactions entre féminisme et foi. Il se propose, dans une perspective comparatiste, d’analyser d’une part le recueil de nouvelles de Sara Maitland intitulé A Book of Spells, et d’autre part, le roman acclamé de Michèle Roberts, Daughters of the House. Dans ces écrits, Maitland et Roberts ont un objectif commun qui est de renégocier la place des femmes dans l’histoire chrétienne dont elles reconnaissent – il est vrai à partir de perspectives diff

  18. The technical status of the supersara project at its termination

    International Nuclear Information System (INIS)

    Markovina, A.; Randles, J.

    1987-01-01

    On March 10th 1983 the Council of Ministers of the European Community adopted the decision to abandon the SuperSARA project. In the frame of this decision, the Management of the SuperSARA project formulated the guidelines to close the project, which included the preparation of the present final report. This report presents the final status of the project, which means that it reflects the situation in March 1983, with a few updates introduced shortly afterwards in conformity with the safety requirements which were being revised at that time. The aim of this report is to give a general description of activities which were carried on to implement the experimental programme and to illustrate some important achievements reached in specific areas. In addition, it is also intended to provide the access key to the documentation which was produced in the past years, so as to make the most significant technical material easily available for any possible future use

  19. The LP-FP-2 severe fuel damage scenario and discussion of the relative influence of the transient and reflood phases in affecting the final condition of the bundle

    International Nuclear Information System (INIS)

    Modro, S.M.; Carboneau, M.L.

    1990-01-01

    The purpose of this paper is to review the evidence from the OECD LP-FP-2 experiment that a high temperature excursion occurred within the center fuel module (CFM) during the reflood portion of the test, was caused by rapid metal-water reaction. It is shown that this reflood scenario explains many perplexing observations from the experiment, in particular, the small amount of fission products and hydrogen transported to the blowdown suppression tank (BST) as compared with the larger quantities trapped within the primary coolant system (PCS). The timing and destruction of the CFM upper tie plate, as well as the transport of fuel debris to the top of this plate, are also explained. In general, all measurements, observations, and analyses of the LP-FP-2 data indicate that most of the CFM damage occurred during a relatively short period of time coincident with the reflood portion of the experiment. 4 refs., 6 figs

  20. Impact of the Regulators SigB, Rot, SarA and sarS on the Toxic Shock Tst Promoter and TSST-1 Expression in Staphylococcus aureus.

    Directory of Open Access Journals (Sweden)

    Diego O Andrey

    Full Text Available Staphylococcus aureus is an important pathogen manifesting virulence through diverse disease forms, ranging from acute skin infections to life-threatening bacteremia or systemic toxic shock syndromes. In the latter case, the prototypical superantigen is TSST-1 (Toxic Shock Syndrome Toxin 1, encoded by tst(H, and carried on a mobile genetic element that is not present in all S. aureus strains. Transcriptional regulation of tst is only partially understood. In this study, we dissected the role of sarA, sarS (sarH1, RNAIII, rot, and the alternative stress sigma factor sigB (σB. By examining tst promoter regulation predominantly in the context of its native sequence within the SaPI1 pathogenicity island of strain RN4282, we discovered that σB emerged as a particularly important tst regulator. We did not detect a consensus σB site within the tst promoter, and thus the effect of σB is likely indirect. We found that σB strongly repressed the expression of the toxin via at least two distinct regulatory pathways dependent upon sarA and agr. Furthermore rot, a member of SarA family, was shown to repress tst expression when overexpressed, although its deletion had no consistent measurable effect. We could not find any detectable effect of sarS, either by deletion or overexpression, suggesting that this regulator plays a minimal role in TSST-1 expression except when combined with disruption of sarA. Collectively, our results extend our understanding of complex multifactorial regulation of tst, revealing several layers of negative regulation. In addition to environmental stimuli thought to impact TSST-1 production, these findings support a model whereby sporadic mutation in a few key negative regulators can profoundly affect and enhance TSST-1 expression.

  1. Women Empowerment in the Realms of Institutionalized Religion and Patriarchy: El Saadawi’s Firdaus and Yezierska’s Sara as Examples

    OpenAIRE

    Abdullah K. Shehabat

    2016-01-01

    This paper explains how the two protagonists, Firdaus and Sara, successfully paved their own ways in search of self-liberation despite the authoritarian patriarchy and institutionalized religions that plagued them. El Saadawi's Woman at Point Zero and Yezierska’s Bread Givers represent the fruitful struggle these protagonists experienced as they come to forge an identity and be themselves. The paper argues that the protagonists manage to free themselves, establish their own spiritual homes at...

  2. UPTF/TEST10B/RUN081, Steam/Water Flow Phenomena Reflood PWR Cold Leg Break LOCA

    International Nuclear Information System (INIS)

    1998-01-01

    1 - Description of test facility: The Upper Plenum Test Facility (UPTF) is a geometrical full-scale simulation of the primary system of the four-loop 1300 MWe Siemens/KWU pressurized water reactor (PWR) at Grafenrheinfeld. The test vessel, upper plenum and its internals, downcomer, primary loops, pressurizer and surge line are replicas of the reference plant. The core, coolant pumps, steam generators and containment of a PWR are replaced by simulators which simulate the boundary and initial conditions during end-of-blowdown, refill and reflood phase following a loss-of-coolant accident (LOCA) with a hot or cold leg break. The break size and location can be simulated in the broken loop. The emergency core coolant (ECC) injection systems at the UPTF are designed to simulate the various ECC injection modes, such as hot leg, upper plenum, cold leg, downcomer or combined hot and cold leg injection of different ECC systems of German and US/Japan PWRs. Moreover, eight vent valves are mounted in the core barrel above the hot leg nozzle elevation for simulation of ABB and B and W PWRs. The UPTF primary system is divided into the investigation and simulation areas. The investigation areas, which are the exact replicas of a GPWR, consist of the upper plenum with internals, hot legs, cold legs and downcomer. The realistic thermal-hydraulic behavior in the investigation areas is assured by appropriate initial and boundary conditions of the area interface. The boundary conditions are realized by above mentioned simulators, the setup and the operation of which are based on small-scale data and mathematical models. The simulation areas include core simulator, steam generator simulators, pump simulators and containment simulator. The steam production and entrainment in a real core during a LOCA are simulated by steam and water injection through the core simulator. 2 - Description of test: Investigation of steam/water flow phenomena at the upper tie plate and in the upper plenum and

  3. Instability in newly-established wetlands? Trajectories of floristic change in the re-flooded Hula peatland, northern Israel

    Directory of Open Access Journals (Sweden)

    D. Kaplan

    2012-01-01

    Full Text Available Drainage of the 6,000 ha Hula Lake and peatland in northern Israel in the late 1950s caused the loss of a very diverse and rare ecosystem and an important phytogeographic meeting zone for Holarctic and Palaeotropical species. Draining the Hula peatland was only partially successful in creating a large fertile area for cultivation, and in 1994 this led the authorities to re-flood 100 ha of the valley—the Agamon (Agmon—with the aim of rehabilitating the diverse wetland landscape, promoting ecotourism and creating a clear-water body that would contribute to the purification of Lake Kinneret. The vegetation of the restored wetland was monitored for ten years (1997–2006, recording the establishment and abundance of vascular plant species. More than 20 emergent, submerged and riparian species became established. Like a number of other shallow-water wetlands, the Agmon is characterised by considerable ecological fluctuations. This has been expressed in prominent floristic changes in the Agamon since it was created. An increased abundance of Ceratophyllum demersum and Najas minor and a decline in Potamogeton spp., Najas delilei and filamentous algae have been observed. A long-term decline in water level and sediment accumulation has brought about a significant rise in the incidence of Phragmites australis, Typha domingensis and Ludwigia stolonifera in the south-eastern area. A GIS analysis of changes in species dominance shows fluctuations over the years, with only a partial trend of succession towards a P. australis, T. domingensis and L. stolonifera community.

  4. Evaluation report on CCTF Core-I reflood tests Cl-2 (Run 11) and Cl-3 (Run 12)

    International Nuclear Information System (INIS)

    Akimoto, Hajime; Murao, Yoshio

    1983-06-01

    In order to clarify the effect of the initial superheat of the downcomer wall on the system and the core cooling behaviors during the reflood phase of a PWR-LOCA, two tests were performed with the Cylindrical Core Test Facility (CCTF). One is the superheated wall test (test Cl-2) with the initial superheat of 79K, as in the actual PWR, and the other is the saturated wall test (test Cl-3) without any initial superheat. Through the comparisons of the test results from these two tests, the following conclusions were obtained. (1) The initial superheat of the downcomer wall resulted in the lower downcomer water head as observed in our separate-effect tests for the downcomer water head. (2) The superheat also caused the core inlet subcooling to be decreased, and led to the lower core water head. (3) The mass flow rate through the intact loop was reduced only by 4% by the initial superheat of the downcomer wall because the core water head was reduced as well as the downcomer water head. Whereas the mass flow rate through the broken loop was increased because of the increased pressure drop through the broken cold leg. (4) The difference of the core inlet mass flow rate was small between the superheated and the saturated wall tests. It can be considered that small difference of the core inlet mass flow rate results from the compensation of the decreased mass flow rate through the intact loops by the increased mass flow rate through the broken loop. (5) The main discrepancies of the core cooling and the carry-over behaviors between two CCTF tests, were consistent with those observed in the parametric tests for the core inlet subcooling of the FLECHT LOW FLOODING TEST series. (author)

  5. Numerical studies of the heat-up-phase of Super-Sara 'severe fuel damage'. Boildown tests

    International Nuclear Information System (INIS)

    Eifler, W.; Shepherd, I.M.

    1983-01-01

    Calculations to investigate the heat-up phase of the Super-Sara 'severe fuel damage' test matrix have been performed using a simple computer code which models a typical pin. In particular the effect of the exothermic zirconium water reaction on the transient is considered. It is shown that it is possible to achieve the desired objectives of all the tests by a test procedure involving a constant power level a simple flow history. This flow history consists of an initial inlet flow, that has the water saturated at outlet. It is then linearly decreased in a time of the order of 200 seconds to a steady lower value. The clad temperature ramp rate is defined by the power and the peak clad temperature by the ratio of the power of the final steady inlet flow rate. If the final inlet flow rate for a particular power is below a certain critical value then the clad will reach melting temperature. The sensitivity of the results are discussed and a sample calculation is made for each test in the matrix

  6. Land-use evaluation for sustainable construction in a protected area: A case of Sara mountain national park.

    Science.gov (United States)

    Ristić, Vladica; Maksin, Marija; Nenković-Riznić, Marina; Basarić, Jelena

    2018-01-15

    The process of making decisions on sustainable development and construction begins in spatial and urban planning when defining the suitability of using land for sustainable construction in a protected area (PA) and its immediate and regional surroundings. The aim of this research is to propose and assess a model for evaluating land-use suitability for sustainable construction in a PA and its surroundings. The methodological approach of Multi-Criteria Decision Analysis was used in the formation of this model and adapted for the research; it was combined with the adapted Analytical hierarchy process and the Delphi process, and supported by a geographical information system (GIS) within the framework of ESRI ArcGIS software - Spatial analyst. The model is applied to the case study of Sara mountain National Park in Kosovo. The result of the model is a "map of integrated assessment of land-use suitability for sustainable construction in a PA for the natural factor". Copyright © 2017 Elsevier Ltd. All rights reserved.

  7. Full-scale model development of the WWER-440 reactor fuel rod bundle for core temperature regime study under reflooding conditions

    International Nuclear Information System (INIS)

    Bezrukov, Yu.A.; Logvinov, S.A.; Levchuk, S.V.; Nakladnov, V.D.; Onshin, V.P.; Sokolov, A.S.

    1982-01-01

    Consideration is given to the issues of a full scale WWER-440 fuel rod bundle imitation. An imitator contains a molybdenum heating rod inclosed in stainless steel shell. The shell diameter is 9 mm, the heated length is 2500 mm, the total len.o.th is 2855 mm. 125 fuel rod imitators are set in the bundle mock-up. The experiments were run on a test facility imitating the WWER-440 reactor primary loop, providing the conditions of the loop breaking. The mock-up thermal hydraulics has been studied during the refloodino. stage. The mock-up was heated up to predetermined initial temperature at a low power level with saturated steam cooling. Then the steam input was stopped, the power level rarapidly rised up to a given value and the cooling water injected. Simultaneously with water injection all the measured parameters monitoring was started. Both at the top spraying and combined cooling temperature oscillations in the upper and middle parts of the mock-up were observed. At the bottom reflooding the mock-up cooling down took more time, thereat temperature inthe upper part first slowly rised during reflooding then decreased and then dropped abruptly at thefront coming up [ru

  8. Assessment of MARS for downcomer multi-dimensional thermal hydraulics during LBLOCA reflood using KAERI air-water direct vessel injection tests

    Energy Technology Data Exchange (ETDEWEB)

    Won-Jae, Lee; Kwi-Seok, Ha; Chul-Hwa, Song [Korea Atomic Energy Research Inst., Daejeon (Korea, Republic of)

    2001-07-01

    The MARS code has been assessed for the downcomer multi-dimensional thermal hydraulics during a large break loss-of-coolant accident (LBLOCA) reflood of Korean Next Generation Reactor (KNGR) that adopted an upper direct vessel injection (DVI) design. Direct DVI bypass and downcomer level sweep-out tests carried out at 1/50-scale air-water DVI test facility are simulated to examine the capability of MARS. Test conditions are selected such that they represent typical reflood conditions of KNGR, that is, DVI injection velocities of 1.0 {approx} 1.6 m/sec and air injection velocities of 18.0 {approx} 35.0 m/sec, for single and double DVI configurations. MARS calculation is first adjusted to the experimental DVI film distribution that largely affects air-water interaction in a scaled-down downcomer, then, the code is assessed for the selected test matrix. With some improvements of MARS thermal-hydraulic (T/H) models, it has been demonstrated that the MARS code is capable of simulating the direct DVI bypass and downcomer level sweep-out as well as the multi-dimensional thermal hydraulics in downcomer, where condensation effect is excluded. (authors)

  9. Multi-dimensional Mixing Behavior of Steam-Water Flow in a Downcomer Annulus during LBLOCA Reflood Phase with a DVI Injection Mode

    International Nuclear Information System (INIS)

    Kwon, T.S.; Yun, B.J.; Euh, D.J.; Chu, I.C.; Song, C.H.

    2002-01-01

    Multi-dimensional thermal-hydraulic behavior in the downcomer annulus of a pressurized water reactor vessel with a Direct Vessel Injection (DVI) mode is presented based on the experimental observation in the MIDAS (Multi-dimensional Investigation in Downcomer Annulus Simulation) steam-water test facility. From the steady-state test results to simulate the late reflood phase of a Large Break Loss-of-Coolant Accidents(LBLOCA), isothermal lines show the multidimensional phenomena of a phasic interaction between steam and water in the downcomer annulus very well. MIDAS is a steam-water separate effect test facility, which is 1/4.93 linearly scaled-down of 1400 MWe PWR type of a nuclear reactor, focused on understanding multi-dimensional thermalhydraulic phenomena in downcomer annulus with various types of safety injection during the refill or reflood phase of a LBLOCA. The initial and the boundary conditions are scaled from the pre-test analysis based on the preliminary calculation using the TRAC code. The superheated steam with a superheating degree of 80 K at a given downcomer pressure of 180 kPa is injected equally through three intact cold legs into the downcomer. (authors)

  10. Evaluation report on CCTF Core-I reflood tests C1-5 (Run 14), C1-7 (Run 16) and C1-14 (Run 23)

    International Nuclear Information System (INIS)

    Sugimoto, Jun; Muurao, Yoshio

    1983-02-01

    The present report describes the effects of the initial clad temperature on the reflood phenomena observed in the Cylindrical Core Test Facility (CCTF) at Japan Atomic Energy Research Institute. The evaluation is based on the data of tests C1-5, C1-7 and C1-14 of the CCTF-Core I test series. Nominal initial peak clad temperatures in these tests are 600 0 C, 700 0 C and 800 0 C, respectively. With the higher initial clad temperature, the higher loop mass flow rate and the lower water accumulation in the core and the upper plenum were obtained in an early reflood transient. However, the core inlet flow conditions, which is sensitive to the core cooling, were not much affected by the higher initial clad temperature. The slower quench front propagation was observed with the higher initial clad temperature. However, the heat transfer coefficient was almost identical with each other before the turnaround time, which resulted in the lower temperature rise with the highest initial clad temperature. This qualitatively agreed with the results of the forced feed FLECHT experiment. (author)

  11. Projectables

    DEFF Research Database (Denmark)

    Rasmussen, Troels A.; Merritt, Timothy R.

    2017-01-01

    CNC cutting machines have become essential tools for designers and architects enabling rapid prototyping, model-building and production of high quality components. Designers often cut from new materials, discarding the irregularly shaped remains. We introduce ProjecTables, a visual augmented...... reality system for interactive packing of model parts onto sheet materials. ProjecTables enables designers to (re)use scrap materials for CNC cutting that would have been previously thrown away, at the same time supporting aesthetic choices related to wood grain, avoiding surface blemishes, and other...... relevant material properties. We conducted evaluations of ProjecTables with design students from Aarhus School of Architecture, demonstrating that participants could quickly and easily place and orient model parts reducing material waste. Contextual interviews and ideation sessions led to a deeper...

  12. Evaluation of reflooding effects on an overheated boiling water reactor core in a small steam-line break accident using MAAP, MELCOR, and SCDAP/RELAP5 computer codes

    International Nuclear Information System (INIS)

    Lindholm, I.; Pekkarinen, E.; Sjoevall, H.

    1995-01-01

    Selected core reflooding situations were investigated in the case of a Finnish boiling water reactor with three severe accident analysis computer codes (MAAP, MELCOR, and SCDAP/RELAP5). The unmitigated base case accident scenario was a 10% steam-line break without water makeup to the reactor pressure vessel initially. The pumping of water to the core was started with the auxiliary feed water system when the maximum fuel cladding temperature reached 1,500 K. The auxiliary feedwater system pumps water (temperature 303 K) through the core spray spargers (core spray) on the top of the core and through feedwater nozzles to the downcomer (downcomer injection). The scope of the study was restricted to cases where the overheated core was still geometrically intact at the start of the reflooding. The following different core reflooding situations were investigated: (1) auxiliary feedwater injection to core spray (45 kg/s); (2) auxiliary feedwater injection to downcomer (45 kg/s); (3) auxiliary feedwater injection to downcomer (45 kg/s) and to core spray (45 kg/s); (4) no reflooding of the core. All the three codes predicted debris formation after the water addition, and in all MAAP and MELCOR reflooding results the core was quenched. The major difference between the code predictions was in the amount of H 2 produced, though the trends in H 2 production were similar. Additional steam production during the quenching process accelerated the oxidation in the unquenched parts of the core. This result is in accordance with several experimental observations

  13. The comparison of naturally weathered oil and artificially photo-degraded oil at the molecular level by a combination of SARA fractionation and FT-ICR MS

    International Nuclear Information System (INIS)

    Islam, Ananna; Cho, Yunju; Yim, Un Hyuk; Shim, Won Joon; Kim, Young Hwan; Kim, Sunghwan

    2013-01-01

    Highlights: • Weathered oils from the Hebei Spirit oil spill and photo degraded oils are compared. • We investigate changes of polar species at the molecular level by 15T FT-ICR MS. • Significant reduction of sulfur class compounds in saturates fraction is observed. • The relative abundance of protonated compounds (presumably basic nitrogen compounds) increase after degradation. • Changes of polar compounds occurred by natural and photo degradation are similar. -- Abstract: Two sets of oil samples, one obtained from different weathering stages of the M/V Hebei Spirit oil spill site and the other prepared by an in vitro photo-degradation experiment, were analyzed and compared at the molecular level by atmospheric pressure photo-ionization coupled with Fourier transform ion cyclotron resonance mass spectrometry (FT-ICR MS). For a more detailed comparison at the molecular level, the oil samples were separated into saturate, aromatic, resin, and asphaltene (SARA) fractions before MS analysis. Gravimetric analysis of the SARA fractions revealed a decreased weight percentage of the aromatic fraction and an increased resin fraction in both sets of samples. Molecular-level investigations of the SARA fractions showed a significant reduction in the S 1 class in the saturate fraction and increase of S 1 O 1 class compounds with high DBE values in resin fraction. Levels of N 1 and N 1 O 1 class compounds resulting in protonated ions (presumably basic nitrogen compounds) increased after degradation compared to compounds generating molecular ions (presumably non-basic nitrogen compounds). This study revealed changes occurring in heteroatom polar species of crude oils such as sulfur and nitrogen containing compounds that have not been easily detected with conventional GC based techniques

  14. SARAS 2: a spectral radiometer for probing cosmic dawn and the epoch of reionization through detection of the global 21-cm signal

    Science.gov (United States)

    Singh, Saurabh; Subrahmanyan, Ravi; Shankar, N. Udaya; Rao, Mayuri Sathyanarayana; Girish, B. S.; Raghunathan, A.; Somashekar, R.; Srivani, K. S.

    2018-04-01

    The global 21-cm signal from Cosmic Dawn (CD) and the Epoch of Reionization (EoR), at redshifts z ˜ 6-30, probes the nature of first sources of radiation as well as physics of the Inter-Galactic Medium (IGM). Given that the signal is predicted to be extremely weak, of wide fractional bandwidth, and lies in a frequency range that is dominated by Galactic and Extragalactic foregrounds as well as Radio Frequency Interference, detection of the signal is a daunting task. Critical to the experiment is the manner in which the sky signal is represented through the instrument. It is of utmost importance to design a system whose spectral bandpass and additive spurious signals can be well calibrated and any calibration residual does not mimic the signal. Shaped Antenna measurement of the background RAdio Spectrum (SARAS) is an ongoing experiment that aims to detect the global 21-cm signal. Here we present the design philosophy of the SARAS 2 system and discuss its performance and limitations based on laboratory and field measurements. Laboratory tests with the antenna replaced with a variety of terminations, including a network model for the antenna impedance, show that the gain calibration and modeling of internal additive signals leave no residuals with Fourier amplitudes exceeding 2 mK, or residual Gaussians of 25 MHz width with amplitudes exceeding 2 mK. Thus, even accounting for reflection and radiation efficiency losses in the antenna, the SARAS 2 system is capable of detection of complex 21-cm profiles at the level predicted by currently favoured models for thermal baryon evolution.

  15. A dinâmica dos mercados associados ao suínos de raça Bísara na Terra Fria Transmonta

    OpenAIRE

    Carvalho, Marieta

    2014-01-01

    A procura mundial de produtos de origem animal aumentará cerca de 70% em 2050, com especial relevância para a de origem do porco (FAO, 2014). Este trabalho visa estudar: · A dinâmica dos mercados associados aos suínos da raça Bísara: animais, carne e fumeiro de Vinhais. · Os circuitos de comercialização, os preços ao criador de suínos de animais vivos, da carne e fumeiro de Vinhais. A metodologia utilizada baseou-se na análise descritiva, referente aos de 2013 e 2014, dos ...

  16. Study of top reflooding in case of severe accident and in particular oxidation of Uranium, Zirconium, Oxygen melts; Etude du renoyage par le haut en cas d'accident grave et en particulier oxydation des melanges (U,Zr,O)

    Energy Technology Data Exchange (ETDEWEB)

    Brunet-Thibault, E

    2006-12-15

    In 1979, the Three Mile Island (TMI) accident occurred in United States and accelerated research activities in the field of severe accidents. Severe accident management procedures imply massive water injections to flood the core. The work of this thesis bent principally over this reflooding. The first part of the study concerns the core oxidation enhancement during the reflooding phase which leads to a rough increase of the concentration of burnable hydrogen in the containment. This is why the study carried on the analysis of the contribution of the oxidation of U-Zr-O mixtures, towards the total production of hydrogen during reflooding. In the second part, the study concerns top flooding modelling i.e.: with injection of water in the hot legs. Here, we attempted to define bases and realize a model allowing to describe this type of reflooding. These models were validated on the simulation of the parameter with MAAP4 code. (author)

  17. Dispersed flow film boiling: An investigation of the possibility to improve the models implemented in the NRC computer codes for the reflooding phase of the LOCA

    International Nuclear Information System (INIS)

    Andreani, M.; Yadigaroglu, G.; Paul Scherrer Inst.

    1992-08-01

    Dispersed Flow Film Boiling is the heat transfer regime that occurs at high void fractions in a heated channel. The way this heat transfer mode is modelled in the NRC computer codes (RELAP5 and TRAC) and the validity of the assumptions and empirical correlations used is discussed. An extensive review of the theoretical and experimental work related with heat transfer to highly dispersed mixtures reveals the basic deficiencies of these models: the investigation refers mostly to the typical conditions of low rate bottom reflooding, since the simulation of this physical situation by the computer codes has often showed poor results. The alternative models that are available in the literature are reviewed, and their merits and limits are highlighted. The modifications that could improve the physics of the models implemented in the codes are identified

  18. Evaluation and assessment of reflooding models in RELAP5/Mod2.5 and RELAP5/Mod3 codes using Lehigh University and PSI-Neptun bundle experimental data

    Energy Technology Data Exchange (ETDEWEB)

    Sencar, M.; Aksan, N. [Paul Scherrer Institute, Villigen (Switzerland)

    1995-09-01

    An extensive analysis and assessment work on reflooding models of RELAP5/Mod2.5 and, RELAP5/Mod3/v5m5 and RELAP/Mod3/v7j have been performed. Experimental data from LehighUniversityv. and PSI-NEPTUN bundle reflooding experiments have been used for the assessment, since both of these tests cover a broad range of initial conditions. Within the range of these initial conditions, it was tried to identify their separate impacts on the calculated results. A total of six Lehigh University reflooding bundle tests and two PSI-NEPTUN tests with bounding initial conditions are selected for the analysis. Detailed nodalisation studies both for hydraulic and conduction heat transfer were done. On the basis of the results obtained from these cases, a base nodalisation scheme was established. All the other analysis work was performed by using this base nodalisation. RELAP5/Mod2.5 results do not change with renodalisation but RELAP5/Mod3 results are more sensitive to renodalisation. The results of RELAP5/Mod2.5 versions show very large deviations from the used experimental data. These results indicate that some of the phenomenology of the events occurring during the reflooding could not be identified. In the paper, detailed discussions on the main reasons of the deviations from the experimental data will be presented. Since, the results and findings of this study are meant to be a developmental aid, some recommendations have been drawn and some of these have already been implemented at PSI with promising results.

  19. The staphylococcal accessory regulator, SarA, is an RNA-binding protein that modulates the mRNA turnover properties of late-exponential and stationary phase Staphylococcus aureus cells

    Directory of Open Access Journals (Sweden)

    John M Morrison

    2012-03-01

    Full Text Available The modulation of mRNA turnover is gaining recognition as a mechanism by which Staphylococcus aureus regulates gene expression, but the factors that orchestrate alterations in transcript degradation are poorly understood. In that regard, we previously found that 138 mRNA species, including the virulence factors protein A (spa and collagen binding protein (cna, are stabilized in a sarA-dependent manner during exponential phase growth, suggesting that SarA protein may directly or indirectly effect the RNA turnover properties of these transcripts. Herein, we expanded our characterization of the effects of sarA on mRNA turnover during late exponential and stationary phases of growth. Results revealed that the locus affects the RNA degradation properties of cells during both growth phases. Further, using gel mobility shift assays and RIP-ChIP, it was found that SarA protein is capable of binding mRNA species that it stabilizes both in vitro and within bacterial cells. Taken together, these results suggest that SarA post-transcriptionally regulates S. aureus gene expression in a manner that involves binding to and consequently altering the mRNA turnover properties of target transcripts.

  20. Identification of new proton-rich rare earth nuclei by means of the coupled system helium jet-isotope separator of SARA

    International Nuclear Information System (INIS)

    Ollivier, T.

    1986-01-01

    In order to study new exotic nuclei far from stability we built a fast separation system by coupling a helium jet with the medium-current source of the mass separator. First the tests were made in Lyon and then the system used on line with the heavy ion accelerator SARA, in Grenoble. We obtained efficiency greater than 1% for each element and a better chemical independence. This allowed us to perform experiments on rare-earth region near N=82, with fusion-evaporation reactions after an investigation of various ranges of beam energies. The first results allow to identify two new isotopes, 143 Tb (12s) and 138 Eu (12s). The decay schemes obtained are analysed in the frame of existing models [fr

  1. Análise SWOT global da exploração dos suínos da raça Bísara

    OpenAIRE

    Carvalho, Marieta

    2015-01-01

    A procura mundial de produtos de origem animal aumentará cerca de 70% em 2050. Estima-se que mil milhões de pobres dependam dos animais para a sua alimentação e criação de riqueza (FAO, 2014). A raça Bísara, são suínos autóctones portugueses do tronco Celta em risco de extinção. Apesar do seu reduzido efetivo representa para as populações locais um elevado peso económico e social. Este trabalho tem como objetivo, fazer uma caracterização atual da suinicultura, com base nos suínos da ra...

  2. Coloss project

    International Nuclear Information System (INIS)

    2005-01-01

    The COLOSS project was a shared-cost action, co-ordinated by IRSN within the Euratom Research Framework Programme 1998-2002. Started in February 2000, the project lasted three years. The work-programme performed by 19 partners was shaped around complementary activities aimed at improving severe accident codes. Unresolved risk-relevant issues regarding H2 production, melt generation and the source term were studied, through a large number of experiments such as a) dissolution of fresh and high burn-up UO 2 and MOX by molten Zircaloy, b) simultaneous dissolution of UO 2 and ZrO 2 by molten Zircaloy, c) oxidation of U-O-Zr mixtures by steam, d) degradation-oxidation of B 4 C control rods. Significant results have been produced from separate-effects, semi-global and large-scale tests on COLOSS topics. Break-through were achieved on some issues. Nevertheless, more data are needed for consolidation of the modelling on burn-up effects on UO 2 and MOX dissolution and on oxidation of U-O-Zr and B 4 C-metal mixtures. There was experimental evidence that the oxidation of these mixtures can contribute significantly to the large H2 production observed during the reflooding of degraded cores under severe accident conditions. Based on the experimental results obtained on the COLOSS topics, corresponding models were developed and were successfully implemented in several severe accident codes. Upgraded codes were then used for plant calculations to evaluate the consequences of new models on key severe accident sequences occurring in different plants designs involving B 4 C control rods (EPR, BWR, VVER- 1000) as well as in the TMI-2 accident. The large series of plant calculations involved sensitivity studies and code benchmarks. Main severe accident codes in use in the EU for safety studies were used such as ICARE/CATHARE, SCDAP/RELAP5, ASTEC, MELCOR and MAAP4. This activity enabled: a) the assessment of codes to calculate core degradation, b) the identification of main

  3. Core radial power profile effect on system and core cooling behavior during reflood phase of PWR-LOCA with CCTF data

    International Nuclear Information System (INIS)

    Akimoto, Hajime; Iguchi, Tadashi; Murao, Yoshio

    1985-01-01

    In the reactor safety assessment during reflood phase of a PWR-LOCA, it is assumed implicitly that the core thermal hydraulic behavior is evaluated by the one-dimensional model with an average power rod. In order to assess the applicability of the one-dimensional treatment, integral tests were performed with various core radial power profiles using the Cylindrical Core Test Facility (CCTF) whose core includes about 2,000 heater rods. The CCTF results confirm that the core radial power profile has weak effect on the thermal hydraulic behavior in the primary system except core. It is also confirmed that the core differential pressure in the axial direction is predicted by the one-dimensional core model with an average power rod even in the case with a steep radial power profile in the core. Even though the core heat transfer coefficient is dependent on the core radial power profile, it is found that the error of the peak clad surface temperature calculation is less than 15 K using the one-dimensional model in the CCTF tests. The CCTF results support the one-dimensional treatment assumed in the reactor safety assessment. (author)

  4. Application of thermal hydraulic and severe accident code SOCRAT/V3 to bottom water reflood experiment QUENCH-LOCA-0

    International Nuclear Information System (INIS)

    Vasiliev, A.D.; Stuckert, J.

    2013-01-01

    Highlights: ► QLOCA-0 test simulates a design basis LOCA NPP accident with maximum temperature 1300 K. ► Deep understanding of hydraulics and thermal mechanics under accident conditions is necessary. ► We model the test QLOCA-0 with bottom flooding using the Russian code SOCRAT/V3. ► Calculated and experimental data are in a good agreement. ► Experimental procedure is determined to reach a representative LOCA scenario in future tests. -- Abstract: The thermal hydraulic and SFD (severe fuel damage) best estimate computer modeling code SOCRAT/V3 has been used for the calculation of QUENCH-LOCA-0 experiment. The new QUENCH-LOCA bundle tests with different cladding materials will simulate a representative scenario of the LOCA (loss of coolant accident) nuclear power plant accident sequence in which the overheated up to 1300 K reactor core would be reflooded from the bottom by ECCS (emergency core cooling system). The first test QUENCH-LOCA-0 was successfully conducted at the KIT, Karlsruhe, Germany, in July 22, 2010, and was performed as the commissioning test for this series. The rod claddings are identical to that used in PWRs. The bundle was electrically heated in steam from 800 K to 1340 K with the heat-up rate of approximately 2.7 K/s. After cooling in the saturated steam the bottom flooding with water flow rate of about 100 g/s was initiated. The SOCRAT calculated results are in a good agreement with experimental data taking into account additional quenching due to water condensate entrainment at the steam cooling stage. SOCRAT/V3 has been used for estimation of further steps in experimental procedure to reach a representative LOCA scenario in future tests

  5. Valorización del arte en los textos periodísticos de Clarice Lispector y Sara Gallardo (1967-1973

    Directory of Open Access Journals (Sweden)

    Guillermina Feudal

    2017-12-01

    Full Text Available En el contexto regional de democratización en el acceso a los bienes culturales, un aspecto nuclear de la producción periodística de Clarice Lispector y Sara Gallardo revela una sintonía común en el comentario y apropiación de recursos estéticos de las vanguardias “de los sesenta”. La apelación al arte como referencia para evaluar la vida cotidiana constituye una decisión comunicacional que funciona, desde el planteo formal y temático, como eje de las intervenciones críticas que ellas operan en el periodismo. El artículo analiza y compara la fundamentación de las elecciones artísticas de las autoras, así como los universos de discusión en los que desarrollan la contienda estética y debaten sobre los alcances de las nuevas modalidades de interacción cultural.

  6. Evaluation report on CCTF core-I reflood tests Cl-5 (Run 14), Cl-10 (Run 19) and Cl-12 (Run 21)

    International Nuclear Information System (INIS)

    Akimoto, Hajime; Murao, Yoshio

    1983-06-01

    Three tests Cl-5 (Run 14), Cl-10 (Run 19) and Cl-12 (Run 21) were performed using the Cylindrical Core Test Facility to study the effect of the containment pressure on the core cooling and the system behaviors during the reflood phase of a PWR-LOCA. The containment pressures of these tests were 0.15, 0.20 and 0.30 MPa for the tests Cl-10, Cl-5 and Cl-12, respectively. Through the comparison of the test results from these three tests, the following results were obtained. (1) The higher containment pressure gave the higher heat transfer coefficient in the core. This resulted in the lower turnaround temperature, the shorter turnaround time and the shorter quench time at the higher containment pressure. (2) In the higher containment pressure test, the higher core water head, the higher upper plenum water head, the higher downcomer water head in the early period and the lower downcomer water head in the later period were observed than those in the lower containment pressure test. This resulted in the higher pressure drop through the intact loop in the early period of the tests and the lower pressure drop in the later period of the test with the containment pressure. (3) The pressure drop through the broken cold leg pressurized the primary system. The pressure drop through the broken cold leg was decreased with the containment pressure. (4) The core inlet mass flow rate was increased with the containment pressure as observed in the FLECHT-SET phase B1 test. In quantity, however, the effect of the containment pressure on the increase of the core inlet mass flow rate was less in the CCTF than that in the FLECHT-SET. The less sensitivity in the CCTF was attributed mainly to the great pressure drop through the broken cold leg, which was not observed in the FLECHT-SET with big broken cold leg. (5) The system effect of the containment pressure was explained quantitatively. (author)

  7. ASTEC code development, validation and applications for severe accident management within the CESAM European project - 15392

    International Nuclear Information System (INIS)

    Van Dorsselaere, J.P.; Chatelard, P.; Chevalier-Jabet, K.; Nowack, H.; Herranz, L.E.; Pascal, G.; Sanchez-Espinoza, V.H.

    2015-01-01

    ASTEC, jointly developed by IRSN and GRS, is considered as the European reference code since it capitalizes knowledge from the European research on the domain. The CESAM project aims at its enhancement and extension for use in severe accident management (SAM) analysis of the nuclear power plants (NPP) of Generation II-III presently under operation or foreseen in near future in Europe, spent fuel pools included. Within the CESAM project 3 main types of research activities are performed: -) further validation of ASTEC models important for SAM, in particular for the phenomena being of importance in the Fukushima-Daichi accidents, such as reflooding of degraded cores, pool scrubbing, hydrogen combustion, or spent fuel pools behaviour; -) modelling improvements, especially for BWR or based on the feedback of validation tasks; and -) ASTEC applications to severe accident scenarios in European NPPs in order to assess prevention and mitigation measures. An important step will be reached with the next major ASTEC V2.1 version planned to be delivered in the first part of 2015. Its main improvements will concern the possibility to simulate in details the core degradation of BWR and PHWR and a model of reflooding of severely degraded cores. A new user-friendly Graphic User Interface will be available for plant analyses

  8. Sharing AIS Related Anomalies (SARA)

    Science.gov (United States)

    2016-03-01

    78 6.3.7 SQL Versus NoSQL . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 81 6.4 Data Processing...43 6.1 Overview of SQL and NoSQL differences, from [56]. . . . . . . . . . . . . . . . . . 82 A.1 Description of the ship anomaly upload use...constraints must be considered. These requirements, however, can only be defined when lower level implementation decisions, such as SQL versus NoSQL

  9. Notas sobre Feral y las cigüeñas, de Fernando Alonso, y la "Historia del califa cigüeña" (Wilhelm Hauff, Sara Cone Bryant

    Directory of Open Access Journals (Sweden)

    Hans Christian Hagedorn

    2011-01-01

    Full Text Available En el presente estudio se analizan las fuentes de la versión de la "Historia del califa cigüeña", incluida en la narración Feral y las cigüeñas (1971, de Fernando Alonso. Para ello se tienen en cuenta el cuento original del autor postromántico alemán Wilhelm Hauff ("Die Geschichte von Kalif Storch", 1825, y la adaptación de este cuento que Sara Cone Bryant realizó para su libro How to tell stories to children (1905, traducción española: El arte de contar cuentos, 1965.

  10. Research Implementation and Quality Assurance Project Plan: An Evaluation of Hyperspectral Remote Sensing Technologies for the Detection of Fugitive Contamination at Selected Superfund Hazardous Waste Sites

    Science.gov (United States)

    Slonecker, E. Terrence; Fisher, Gary B.

    2009-01-01

    This project is a research collaboration between the U.S. Environmental Protection Agency (EPA) Office of Inspector General (OIG) and the U.S. Geological Survey (USGS) Eastern Geographic Science Center (EGSC), for the purpose of evaluating the utility of hyperspectral remote sensing technology for post-closure monitoring of residual contamination at delisted and closed hazardous waste sites as defined under the Comprehensive Environmental Response Compensation and Liability Act [CERCLA (also known as 'Superfund')] of 1980 and the Superfund Amendments and Reauthorization Act (SARA) of 1986.

  11. Impact of 2D/3D-project on LOCA-licensing analysis and reactor safety of PWRs

    International Nuclear Information System (INIS)

    Winkler, F.; Krebs, W.D.

    1989-01-01

    In the past LOCA-licensing analysis has included large conservatisms to compensate for the lack of detailed two phase flow and full scale experimental data. The 2D/3D-project was established to improve the data base in order to minimize the conservatisms required. The significant results and findings of the full scale Upper Plenum Test Facility (UPTF) and from the electrically heated Slab Core Test Facility (SCTF) were particularly useful for understanding the multidimensional phenomena in the primary system and in the core of a PWR. UPTF results were used to verify the TRAC-PF1 analysis of a PWR with combined ECC-Injection during the reflood phase of a large break-LOCA. Comparison of these results with results from classic licensing calculations quantifies the large safety margin in earlier licensing procedures and in reactor systems. (orig.)

  12. Two-phase flow parameters of a downcomer boiling during a postulated reflood phase of APR1400; Parametres d'ecoulement diphasique dans un ebullition a la cuve en acier pendant un refroidissement d'un APRP de APR1400

    Energy Technology Data Exchange (ETDEWEB)

    Byong-Jo, Yun; Dong-Jin, Euh; Chul-Hwa, Song [Korea Atomic Energy Research Inst. (Korea, Republic of)

    2009-07-01

    Downcomer boiling phenomena is one of the key issues for a postulated large-break LOCA (LBLOCA) in a conventional pressurized water reactor, because it can degrade the hydraulic head of the coolant in the downcomer and consequently affect the reflood flow rate for a core cooling. To investigate the thermal hydraulic behavior in the downcomer region of the APR1400, a test program for a downcomer boiling is being progressed for the reflood phase of a postulated LBLOCA. Test was performed in a one side heated rectangular test channel which was designed by adopting a full-pressure, full-height, and full-size downcomer-gap approach, but with the circumferential length was reduced 47.08-fold. The test consists of two steps: (I) for the global two-phase flow parameters and (II) for the local two-phase flow parameters. The step-I test has already been completed. In the present paper, the experimental results of the step-II test are introduced. (authors)

  13. Coloss project; Le projet Coloss

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    The COLOSS project was a shared-cost action, co-ordinated by IRSN within the Euratom Research Framework Programme 1998-2002. Started in February 2000, the project lasted three years. The work-programme performed by 19 partners was shaped around complementary activities aimed at improving severe accident codes. Unresolved risk-relevant issues regarding H2 production, melt generation and the source term were studied, through a large number of experiments such as a) dissolution of fresh and high burn-up UO{sub 2} and MOX by molten Zircaloy, b) simultaneous dissolution of UO{sub 2} and ZrO{sub 2} by molten Zircaloy, c) oxidation of U-O-Zr mixtures by steam, d) degradation-oxidation of B{sub 4}C control rods. Significant results have been produced from separate-effects, semi-global and large-scale tests on COLOSS topics. Break-through were achieved on some issues. Nevertheless, more data are needed for consolidation of the modelling on burn-up effects on UO{sub 2} and MOX dissolution and on oxidation of U-O-Zr and B{sub 4}C-metal mixtures. There was experimental evidence that the oxidation of these mixtures can contribute significantly to the large H2 production observed during the reflooding of degraded cores under severe accident conditions. Based on the experimental results obtained on the COLOSS topics, corresponding models were developed and were successfully implemented in several severe accident codes. Upgraded codes were then used for plant calculations to evaluate the consequences of new models on key severe accident sequences occurring in different plants designs involving B{sub 4}C control rods (EPR, BWR, VVER- 1000) as well as in the TMI-2 accident. The large series of plant calculations involved sensitivity studies and code benchmarks. Main severe accident codes in use in the EU for safety studies were used such as ICARE/CATHARE, SCDAP/RELAP5, ASTEC, MELCOR and MAAP4. This activity enabled: a) the assessment of codes to calculate core degradation, b) the

  14. Quench/reflood modeling in MELCOR

    International Nuclear Information System (INIS)

    Gauntt, R.O.

    2001-01-01

    The authors describe the reactor accident simulation model MELCOR. It comprises hydrodynamic investigations on reactor core quenching, hydrogen generation in the reactor core vessel, quench front advances. Preliminary comparisons to data are reasonable but need further validation. (uke)

  15. Project Notes

    Science.gov (United States)

    School Science Review, 1978

    1978-01-01

    Presents sixteen project notes developed by pupils of Chipping Norton School and Bristol Grammar School, in the United Kingdom. These Projects include eight biology A-level projects and eight Chemistry A-level projects. (HM)

  16. Define Project

    DEFF Research Database (Denmark)

    Munk-Madsen, Andreas

    2005-01-01

    "Project" is a key concept in IS management. The word is frequently used in textbooks and standards. Yet we seldom find a precise definition of the concept. This paper discusses how to define the concept of a project. The proposed definition covers both heavily formalized projects and informally...... organized, agile projects. Based on the proposed definition popular existing definitions are discussed....

  17. Project Management

    DEFF Research Database (Denmark)

    Project Management Theory Meets Practice contains the proceedings from the 1st Danish Project Management Research Conference (DAPMARC 2015), held in Copenhagen, Denmark, on May 21st, 2015.......Project Management Theory Meets Practice contains the proceedings from the 1st Danish Project Management Research Conference (DAPMARC 2015), held in Copenhagen, Denmark, on May 21st, 2015....

  18. Project Management

    DEFF Research Database (Denmark)

    Pilkington, Alan; Chai, Kah-Hin; Le, Yang

    2015-01-01

    This paper identifies the true coverage of PM theory through a bibliometric analysis of the International Journal of Project Management from 1996-2012. We identify six persistent research themes: project time management, project risk management, programme management, large-scale project management......, project success/failure and practitioner development. These differ from those presented in review and editorial articles in the literature. In addition, topics missing from the PM BOK: knowledge management project-based organization and project portfolio management have become more popular topics...

  19. Project financing

    International Nuclear Information System (INIS)

    Cowan, A.

    1998-01-01

    Project financing was defined ('where a lender to a specific project has recourse only to the cash flow and assets of that project for repayment and security respectively') and its attributes were described. Project financing was said to be particularly well suited to power, pipeline, mining, telecommunications, petro-chemicals, road construction, and oil and gas projects, i.e. large infrastructure projects that are difficult to fund on-balance sheet, where the risk profile of a project does not fit the corporation's risk appetite, or where higher leverage is required. Sources of project financing were identified. The need to analyze and mitigate risks, and being aware that lenders always take a conservative view and gravitate towards the lowest common denominator, were considered the key to success in obtaining project financing funds. TransAlta Corporation's project financing experiences were used to illustrate the potential of this source of financing

  20. Project descriptions

    International Nuclear Information System (INIS)

    Anon.

    1990-01-01

    This part specifies the activities and project tasks of each project broken down according to types of financing, listing the current projects Lw 1 through 3 funded by long-term provisions (budget), the current projects LB 1 and 2, LG 1 through 5, LK1, LM1, and LU 1 through 6 financed from special funds, and the planned projects ZG 1 through 4 and ZU 1, also financed from special funds. (DG) [de

  1. Heat exchanges during the re-flooding of a water reactor core - within the framework of the 'reference accident'; Echanges thermiques lors du renoyage d'un coeur de reacteur a eau - dans le cadre de 'l'accident de reference'

    Energy Technology Data Exchange (ETDEWEB)

    Andreoni, Daniel

    1975-11-28

    After a brief presentation of reported studies made in different countries and regarding the so-called 'reference accident', this research thesis reports the study of reactor re-flooding when the reactor is completely dried and heating elements have reached a temperature between 300 and 900 C, with a constant water flow rate entering the test section, with a constant dissipated electrical power, and by using very simple geometries. After a first part addressing the experimental study, the author reports the development of conduction calculation codes used to compute the flow extracted by the two-phase flow, present the thermal-hydraulic code used to compute local values and to study the correlation of the upstream area exchange coefficient. The author finally reports an analysis of the different existing models and the study of a re-flooding model [French] La presente etude est consacree a l'un des aspects de la surete des reacteurs a eau sous pression, et plus precisement a l'accident tres important qui consiste en une perte de fluide caloporteur (Loss of Coolant Accident - 'LOCA'). Le but de l'etude est de fournir des renseignements necessaires a l'interpretation des experiences effectuees sur des grappes, de donner une correlation de coefficient d'echange dans la zone aval, et de donner aussi un modele de progression du front de trempe pour les analyses de surete. Une etude bibliographique preliminaire nous a permis de faire le point sur les experiences entreprises concernant le refroidissement de secours. Ensuite, les chapitres suivants seront decrits: 1) Le chapitre II, consacre a l'etude experimentale (boucle, sections d'essais, resultats globaux). 2) Le chapitre III ou seront presentes les codes de calcul de conduction, necessaires au calcul du flux extrait par le melange diphasique, le code de thermohydraulique necessaire au calcul des grandeurs locales et l'etude de la correlation du coefficient d'echange de la zone aval. 3) Enfin le chapitre IV ou, apres

  2. Ergenlik Dönemi Okuma Tutumu Ölçeği’nin Türkçe’ye Uyarlanması The Adaptasyon Of Survey Of Adolescent Reading Attitudes (Sara Into Turkish

    Directory of Open Access Journals (Sweden)

    Muhammet BAŞTUĞ

    2013-07-01

    Full Text Available The aim of this study is to adapt the Survey of Adolescent Reading Attitudes SARA to Turkish, which was developed by McKenna, Conradi, Lawrance, Jang, and Meyer (2012, and to test it for validity and reliability. The rationale is that the scale involves one’s attitude towards digital reading. The sample was comprised of 702 sixth,seventh and eighth grade students in Konya- 343 of them being femaleand the remaining 359 being male. The original scale had 18 items infour sub-dimensions, namely academic reading in digital settings (AD,recreational reading in digital settings (RD, academic reading in printsettings (AP and recreational reading in print settings (RP. Theexploratory factor analysis and confirmatory factor analysis revealedthat the four original sub-dimensions were retained when two itemswere omitted. Cronbach’s alpha coefficients were 0.691, 0.802, 0.690,0.660 and 0.623 for the overall scale, RD, RP, AP and AD respectively.The results suggest that the adapted scale is reliable and valid. The 15-item finalized version is appropriate for the Turkish language and use inTurkey. In the development of reading environments and materials,identification of students’ attitudes toward reading in a multidimensionalway is expected to make great contributions to morequalified learning environments. Bu araştırmanın amacı, McKenna, Conradi, Lawrence, Jang ve Meyer (2012 tarafından geliştirilen Ergenlik Dönemi Okuma Tutumu Ölçeği’nin geçerlik ve güvenirliğinin yapılarak Türkçe’ye uyarlanmasıdır. Ölçeğin dijital okumaya karşı tutumu da kapsaması sebebiyle uyarlama çalışmasının uygun olacağı düşünülmüştür. Çalışma grubunu Konya ilinde yer alan ve 6,7 ve 8. Sınıflara devam eden 343’ü kız, 359’u erkek toplam 702 öğrenci oluşturmuştur. Ölçeğin orjinali 18 maddeden ve “Akademik Dijital, Serbest Dijital, Akademik Kağıt ve Serbest Kağıt” olmak üzere 4 alt boyuttan olu

  3. Severe accident management: a summary of the VAHTI and ROIMA projects

    International Nuclear Information System (INIS)

    Sairanen, R.

    1998-01-01

    Two severe accident research projects: 'Severe Accident Management' (VAHTI), 1994-96 and 'Reactor Accidents' Phenomena and Simulation (ROIMA) 1997-98. have been conducted at VTT Energy within the RETU research programme. The main objective was to assist the severe accident management programmes of the Finnish nuclear power plants. The projects had several subtopics. These included thermal hydraulic validation of the APROS code, studies of failure mode of the BWR pressure vessel, investigation of core melt progression within a BWR pressure vessel, containment phenomena, development of a computerised severe accident training tool, and aerosol behaviour experiments. The last topic is summarised by another paper in the seminar. The projects have met the objectives set at the project commencement. Calculation tools have been developed and validated suitable for analyses of questions specific for the Finnish plants. Experimental fission product data have been produced that can be used to validate containment aerosol codes. The tools and results have been utilised in plant assessments. One of the main achievements has been the computer code PASULA for analysis of interactions between core melt and pressure vessel. The code has been applied to pressure vessel penetration analysis. The results have shown the importance of the nozzle construction. Modelling possibilities have recently improved by addition of a creep and porous debris models. Cooling of a degraded BWR core has been systematically studied as joint Nordic projects with a set of severe accident codes. Estimates for coolable conditions have been provided. Recriticality due to reflooding of a damaged core has been evaluated. (orig.)

  4. Project studies

    DEFF Research Database (Denmark)

    Geraldi, Joana; Söderlund, Jonas

    2018-01-01

    Project organising is a growing field of scholarly inquiry and management practice. In recent years, two important developments have influenced this field: (1) the study and practice of projects have extended their level of analysis from mainly focussing on individual projects to focussing on micro......, and of the explanations of project practices they could offer. To discuss avenues for future research on projects and project practice, this paper suggests the notion of project studies to better grasp the status of our field. We combine these two sets of ideas to analyse the status and future options for advancing...... project research: (1) levels of analysis; and (2) type of research. Analysing recent developments within project studies, we observe the emergence of what we refer to as type 3 research, which reconciles the need for theoretical development and engagement with practice. Type 3 research suggests pragmatic...

  5. Virtual projects

    DEFF Research Database (Denmark)

    Svejvig, Per; Commisso, Trine Hald

    2012-01-01

    that the best practice knowledge has not permeated sufficiently to the practice. Furthermore, the appropriate application of information and communication technology (ICT) remains a big challenge, and finally project managers are not sufficiently trained in organizing and conducting virtual projects....... The overall implications for research and practice are to acknowledge virtual project management as very different to traditional project management and to address this difference.......Virtual projects are common with global competition, market development, and not least the financial crisis forcing organizations to reduce their costs drastically. Organizations therefore have to place high importance on ways to carry out virtual projects and consider appropriate practices...

  6. Project financing

    International Nuclear Information System (INIS)

    Alvarez, M.U.

    1990-01-01

    This paper presents the basic concepts and components of the project financing of large industrial facilities. Diagrams of a simple partnership structure and a simple leveraged lease structure are included. Finally, a Hypothetical Project is described with basic issues identified for discussion purposes. The topics of the paper include non-recourse financing, principal advantages and objectives, disadvantages, project financing participants and agreements, feasibility studies, organization of the project company, principal agreements in a project financing, insurance, and an examination of a hypothetical project

  7. Microsoft project

    OpenAIRE

    Markić, Lucija; Mandušić, Dubravka; Grbavac, Vitomir

    2005-01-01

    Microsoft Project je alat čije su prednosti u svakodnevnom radu nezamjenjive. Pomoću Microsoft Projecta omogućeno je upravljanje resursima, stvaranje izvještaja o projektima u vremenu, te analize različitih scenarija. Pojavljuje u tri verzije: Microsoft Project Professional, Microsoft Project Server i Microsoft Project Server Client Access Licenses. Upravo je trend da suvremeni poslovni ljudi zadatke povjeravaju Microsoft Projectu jer on znatno povećava produktivnost rada. Te prednos...

  8. Project ethics

    CERN Document Server

    Jonasson, Haukur Ingi

    2013-01-01

    How relevant is ethics to project management? The book - which aims to demystify the field of ethics for project managers and managers in general - takes both a critical and a practical look at project management in terms of success criteria, and ethical opportunities and risks. The goal is to help the reader to use ethical theory to further identify opportunities and risks within their projects and thereby to advance more directly along the path of mature and sustainable managerial practice.

  9. Project Temporalities

    DEFF Research Database (Denmark)

    Tryggestad, Kjell; Justesen, Lise; Mouritsen, Jan

    2013-01-01

    Purpose – The purpose of this paper is to explore how animals can become stakeholders in interaction with project management technologies and what happens with project temporalities when new and surprising stakeholders become part of a project and a recognized matter of concern to be taken...... into account. Design/methodology/approach – The paper is based on a qualitative case study of a project in the building industry. The authors use actor-network theory (ANT) to analyze the emergence of animal stakeholders, stakes and temporalities. Findings – The study shows how project temporalities can...... multiply in interaction with project management technologies and how conventional linear conceptions of project time may be contested with the emergence of new non-human stakeholders and temporalities. Research limitations/implications – The study draws on ANT to show how animals can become stakeholders...

  10. LEX Project

    DEFF Research Database (Denmark)

    Damkilde, Lars; Larsen, Torben J.; Walbjørn, Jacob

    This document is aimed at helping all parties involved in the LEX project to get a common understanding of words, process, levels and the overall concept.......This document is aimed at helping all parties involved in the LEX project to get a common understanding of words, process, levels and the overall concept....

  11. OMEGA project

    International Nuclear Information System (INIS)

    Shibuya, E.H.

    1989-01-01

    The OMEGA - Observation of Multiple particle production, Exotic Interactions and Gamma-ray Air Shower-project is presented. The project try to associate photosensitive detectors from experiences of hadronic interactions with electronic detectors used by experiences that investigate extensive atmospheric showers. (M.C.K.)

  12. Watchdog Project

    Energy Technology Data Exchange (ETDEWEB)

    Smith, Rhett [Schweitzer Engineering Laboratories, Inc., Pullman, WA (United States); Campbell, Jack [CenterPoint Energy Houston Electric, TX (United States); Hadley, Mark [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2016-12-30

    The Watchdog Project completed 100% of the project Statement of Project Objective (SOPO). The Watchdog project was a very aggressive project looking to accomplish commercialization of technology that had never been commercialized, as a result it took six years to complete not the original three that were planned. No additional federal funds were requested from the original proposal and SEL contributed the additional cost share required to complete the project. The result of the Watchdog Project is the world’s first industrial rated Software Defined Network (SDN) switch commercially available. This technology achieved the SOPOO and DOE Roadmap goals to have strong network access control, improve reliability and network performance, and give the asset owner the ability to minimize attack surface before and during an attack. The Watchdog project is an alliance between CenterPoint Energy Houston Electric, Pacific Northwest National Laboratories (PNNL), and Schweitzer Engineering Laboratories, Inc. (SEL). SEL is the world’s leader in microprocessor-based electronic equipment for protecting electric power systems. PNNL performs basic and applied research to deliver energy, environmental, and national security for our nation. CenterPoint Energy is the third largest publicly traded natural gas delivery company in the U.S and third largest combined electricity and natural gas delivery company. The Watchdog Project efforts were combined with the SDN Project efforts to produce the entire SDN system solution for the critical infrastructure. The Watchdog project addresses Topic Area of Interest 5: Secure Communications, for the DEFOA- 0000359 by protecting the control system local area network itself and the communications coming from and going to the electronic devices on the local network. Local area networks usually are not routed and have little or no filtering capabilities. Combine this with the fact control system protocols are designed with inherent trust the control

  13. Freedom Project

    Directory of Open Access Journals (Sweden)

    Alejandra Suarez

    2014-02-01

    Full Text Available Freedom Project trains prisoners in nonviolent communication and meditation. Two complementary studies of its effects are reported in this article. The first study is correlational; we found decreased recidivism rates among prisoners trained by Freedom Project compared with recidivism rates in Washington state. The second study compared trained prisoners with a matched-pair control group and found improvement in self-reported anger, self-compassion, and certain forms of mindfulness among the trained group. Ratings of role-plays simulating difficult interactions show increased social skills among the group trained by Freedom Project than in the matched controls.

  14. EBFA project

    International Nuclear Information System (INIS)

    Anon.

    1979-01-01

    An engineering project office was established during the fall of 1976 to manage and coordinate all of the activities of the Electron Beam Fusion Project. The goal of the project is to develop the Electron Beam Fusion Accelerator (EBFA) and its supporting systems, and integrate these systems into the new Electron Beam Fusion Facility (EBFF). Supporting systems for EBFA include a control/monitor system, a data acquistion/automatic data processing system, the liquid transfer systems, the insulating gas transfer systems, etc. Engineers and technicians were assigned to the project office to carry out the engineering design, initiate procurement, monitor the fabrication, perform the assembly and to assist the pulsed power research group in the activation of the EBFA

  15. Project Reptile!

    Science.gov (United States)

    Diffily, Deborah

    2001-01-01

    Integrating curriculum is important in helping children make connections within and among areas. Presents a class project for kindergarten children which came out of the students' interests and desire to build a reptile exhibit. (ASK)

  16. Project Soar.

    Science.gov (United States)

    Austin, Marion

    1982-01-01

    Project Soar, a Saturday enrichment program for gifted students (6-14 years old), allows students to work intensively in a single area of interest. Examples are cited of students' work in crewel embroidery, creative writing, and biochemistry. (CL)

  17. EUROFANCOLEN Project

    International Nuclear Information System (INIS)

    Bueren, J. A.

    2014-01-01

    The first follow-up report of European Project EUROFANCOLEN, the purpose of which is to develop a gene therapy clinical trial to resolve bone marrow failure in patients with a genetic disease known as Fanconi anemia (FA), was sent to the European Commission in September. The main objective of project EUROFANCOLEN is to develop a gene therapy trial for patients with Fanconi anemia Type A (FA-A), which affects 80% of the patients with FA in Spain. (Author)

  18. Project Management

    DEFF Research Database (Denmark)

    Kampf, Constance

    2009-01-01

    In this video Associate Professor Constance Kampf talks about the importance project management. Not only as a tool in implementation, but also as a way of thinking, and as something that needs to be considered from idea conception......In this video Associate Professor Constance Kampf talks about the importance project management. Not only as a tool in implementation, but also as a way of thinking, and as something that needs to be considered from idea conception...

  19. Project mobilisation

    International Nuclear Information System (INIS)

    Clark, J.; Limbrick, A.

    1996-01-01

    This paper identifies and reviews the issues to be addressed and the procedures to be followed during the mobilisation of projects using LFG as an energy source. Knowledge of the procedures involved in project mobilisation, their sequence and probable timescales, is essential for efficient project management. It is assumed that the majority of projects will be situated on existing, licensed landfill sites and, in addition to complying with the relevant conditions of the waste management licence and original planning consent, any proposed developments on the site will require a separate planning consent. Experience in the UK indicates that obtaining planning permission rarely constitutes a barrier to the development of schemes for the utilisation of LFG. Even so, an appreciation of the applicable environmental and planning legislation is essential as this will enable the developer to recognise the main concerns of the relevant planning authority at an early stage of the project, resulting in the preparation of an informed and well-structured application for planning permission. For a LFG utilisation scheme on an existing landfill site, the need to carry out an environmental assessment (EA) as part of the application for planning permission will, in vitually all cases, be discretionary. Even if not deemed necessary by the planning authority, an EA is a useful tool at the planning application stage, to identify and address potential problems and to support discussions with bodies such as the Environment Agency, from whom consents or authorisations may be required. Carrying out an EA can thus provide for more cost-effective project development and enhanced environmental protection. Typically, the principal contractual arrangements, such as the purchase of gas or the sale of electricity, will have been established before the project mobilisation phase. However, there are many other contractural arrangements that must be established, and consents and permits that may be

  20. Projective mapping

    DEFF Research Database (Denmark)

    Dehlholm, Christian; Brockhoff, Per B.; Bredie, Wender Laurentius Petrus

    2012-01-01

    by the practical testing environment. As a result of the changes, a reasonable assumption would be to question the consequences caused by the variations in method procedures. Here, the aim is to highlight the proven or hypothetic consequences of variations of Projective Mapping. Presented variations will include...... instructions and influence heavily the product placements and the descriptive vocabulary (Dehlholm et.al., 2012b). The type of assessors performing the method influences results with an extra aspect in Projective Mapping compared to more analytical tests, as the given spontaneous perceptions are much dependent......Projective Mapping (Risvik et.al., 1994) and its Napping (Pagès, 2003) variations have become increasingly popular in the sensory field for rapid collection of spontaneous product perceptions. It has been applied in variations which sometimes are caused by the purpose of the analysis and sometimes...

  1. Isotopes Project

    International Nuclear Information System (INIS)

    Dairiki, J.M.; Browne, E.; Firestone, R.B.; Lederer, C.M.; Shirley, V.S.

    1984-01-01

    The Isotopes Project compiles and evaluates nuclear structure and decay data and disseminates these data to the scientific community. From 1940-1978 the Project had as its main objective the production of the Table of Isotopes. Since publication of the seventh (and last) edition in 1978, the group now coordinates its nuclear data evaluation efforts with those of other data centers via national and international nuclear data networks. The group is currently responsible for the evaluation of mass chains A = 167-194. All evaluated data are entered into the International Evaluated Nuclear Structure Data File (ENSDF) and are published in Nuclear Data Sheets. In addition to the evaluation effort, the Isotopes Project is responsible for production of the Radioactivity Handbook

  2. LLAMA Project

    Science.gov (United States)

    Arnal, E. M.; Abraham, Z.; Giménez de Castro, G.; de Gouveia dal Pino, E. M.; Larrarte, J. J.; Lepine, J.; Morras, R.; Viramonte, J.

    2014-10-01

    The project LLAMA, acronym of Long Latin American Millimetre Array is very briefly described in this paper. This project is a joint scientific and technological undertaking of Argentina and Brazil on the basis of an equal investment share, whose mail goal is both to install and to operate an observing facility capable of exploring the Universe at millimetre and sub/millimetre wavelengths. This facility will be erected in the argentinean province of Salta, in a site located at 4830m above sea level.

  3. Project Avatar

    DEFF Research Database (Denmark)

    Juhlin, Jonas Alastair

    'Project Avatar' tager udgangspunkt i den efterretningsdisciplin, der kaldes Open Source Intelligence og indebærer al den information, som ligger frit tilgængeligt i åbne kilder. Med udbredelsen af sociale medier åbners der op for helt nye typer af informationskilder. Spørgsmålet er; hvor nyttig er...

  4. Project Baltia

    Index Scriptorium Estoniae

    2007-01-01

    Uus arhitektuuriajakiri "Project Baltia" tutvustab Baltimaade, Soome ja Peterburi regiooni arhitektuuri, linnaehitust ja disaini. Ilmub neli korda aastas inglise- ja venekeelsena. Väljaandja: kirjastus Balticum Peterburis koostöös Amsterdami ja Moskva kirjastusega A-Fond. Peatoimetaja Vladimir Frolov

  5. Tedese Project

    Science.gov (United States)

    Buforn, E.; Davila, J. Martin; Bock, G.; Pazos, A.; Udias, A.; Hanka, W.

    The TEDESE (Terremotos y Deformacion Cortical en el Sur de España) project is a joint project of the Universidad Complutense de Madrid (UCM) and Real Instituto y Observatorio de la Armada de San Fernando, Cadiz (ROA) supported by the Spanish Ministerio de Ciencia y Tecnologia with the participation of the GeoforschungZen- trum, Potsdam (GFZ). The aim is to carry out a study of the characteristics of the oc- currence and mechanism of earthquakes together with measurements of crustal struc- ture and deformations in order to obtain an integrated evaluation of seismic risk in southern Spain from. As part of this project a temporal network of 10 broad-band seismological stations, which will complete those already existing in the zone, have been installed in southern Spain and northern Africa for one year beginning in October 2001. The objectives of the project are the study in detail of the focal mechanisms of earthquakes in this area, of structural in crust and upper mantle, of seismic anisotropy in crust and mantle as indicator for tectonic deformation processed and the measure- ments of crustal deformations using techniques with permanent GPS and SLR stations and temporary GPS surveys. From these studies, seismotectonic models and maps will be elaborated and seismic risk in the zone will be evaluated.

  6. Project Boomerang

    Science.gov (United States)

    King, Allen L.

    1975-01-01

    Describes an experimental project on boomerangs designed for an undergraduate course in classical mechanics. The students designed and made their own boomerangs, devised their own procedures, and carried out suitable measurements. Presents some of their data and a simple analysis for the two-bladed boomerang. (Author/MLH)

  7. Project Narrative

    Energy Technology Data Exchange (ETDEWEB)

    Driscoll, Mary C. [St. Bonaventure University, St Bonaventure, NY(United States)

    2012-07-12

    The Project Narrative describes how the funds from the DOE grant were used to purchase equipment for the biology, chemistry, physics and mathematics departments. The Narrative also describes how the equipment is being used. There is also a list of the positive outcomes as a result of having the equipment that was purchased with the DOE grant.

  8. Radiochemistry Project

    International Nuclear Information System (INIS)

    Anon.

    Researches carried out in the 'Radiochemistry Project' of the Agricultural Nuclear Energy Center, Piracicaba, Sao Paulo State, Brazil, are described. Such researches comprise: dosimetry and radiological protection; development of techniques and methods of chemical analysis and radiochemistry. (M.A.) [pt

  9. FLOAT Project

    DEFF Research Database (Denmark)

    Sørensen, Eigil V.; Aarup, Bendt

    The objective of the FLOAT project is to study the reliability of high-performance fibre-reinforced concrete, also known as Compact Reinforced Composite (CRC), for the floats of wave energy converters. In order to reach a commercial breakthrough, wave energy converters need to achieve a lower price...

  10. Hydrology Project

    International Nuclear Information System (INIS)

    Anon.

    Research carried out in the 'Hydrology Project' of the Centro de Energia Nuclear na Agricultura', Piracicaba, Sao Paulo State, Brazil, are described. Such research comprises: Amazon hydrology and Northeast hydrology. Techniques for the measurement of isotope ratios are used. (M.A.) [pt

  11. CHEMVAL project

    International Nuclear Information System (INIS)

    Chandratillake, M.; Falck, W.E.; Read, D.

    1992-01-01

    This report summarises the development history of the CHEMVAL Thermodynamic Database, the criteria employed for data selection and the contents of Version 4.0, issued to participants on the completion of the project. It accompanies a listing of the database constructed using the dBase III + /IV database management package. (Author)

  12. Project COLD.

    Science.gov (United States)

    Kazanjian, Wendy C.

    1982-01-01

    Describes Project COLD (Climate, Ocean, Land, Discovery) a scientific study of the Polar Regions, a collection of 35 modules used within the framework of existing subjects: oceanography, biology, geology, meterology, geography, social science. Includes a partial list of topics and one activity (geodesic dome) from a module. (Author/SK)

  13. Swedish projects

    International Nuclear Information System (INIS)

    Thunell, J.

    1993-01-01

    The main sources of the financing of Swedish research on gas technology are listed in addition to names of organizations which carry out this research. The titles and descriptions of the projects carried out are presented in addition to lists of reports published with information on prices. (AB)

  14. SDN Project

    Energy Technology Data Exchange (ETDEWEB)

    Smith, Rhett [Schweitzer Engineering Laboratories Inc, Pullman, WA (United States)

    2016-12-23

    The SDN Project completed on time and on budget and successfully accomplished 100% of the scope of work outlined in the original Statement of Project Objective (SOPO). The SDN Project formed an alliance between Ameren Corporation, University of Illinois Urbana- Champaign (UIUC), Pacific Northwest National Laboratories (PNNL), and Schweitzer Engineering Laboratories, Inc. (SEL). The objective of the SDN Project is to address Topic Area of Interest 2: Sustain critical energy delivery functions while responding to a cyber-intrusion under Funding Opportunity Announcement DE-FOA-0000797. The goal of the project is to design and commercially release technology that provides a method to sustain critical energy delivery functions during a cyber intrusion and to do this control system operators need the ability to quickly identify and isolate the affected network areas, and re-route critical information and control flows around. The objective of the SDN Project is to develop a Flow Controller that monitors, configures, and maintains the safe, reliable network traffic flows of all the local area networks (LANs) on a control system in the Energy sector. The SDN team identified the core attributes of a control system and produced an SDN flow controller that has the same core attributes enabling networks to be designed, configured and deployed that maximize the whitelisted, deny-bydefault and purpose built networks. This project researched, developed and commercially released technology that: Enables all field networks be to configured and monitored as if they are a single asset to be protected; Enables greatly improved and even precalculated response actions to reliability and cyber events; Supports pre-configured localized response actions tailored to provide resilience against failures and centralized response to cyber-attacks that improve network reliability and availability; Architecturally enables the right subject matter experts, who are usually the information

  15. Projective geometry and projective metrics

    CERN Document Server

    Busemann, Herbert

    2005-01-01

    The basic results and methods of projective and non-Euclidean geometry are indispensable for the geometer, and this book--different in content, methods, and point of view from traditional texts--attempts to emphasize that fact. Results of special theorems are discussed in detail only when they are needed to develop a feeling for the subject or when they illustrate a general method. On the other hand, an unusual amount of space is devoted to the discussion of the fundamental concepts of distance, motion, area, and perpendicularity.Topics include the projective plane, polarities and conic sectio

  16. Projective measure without projective Baire

    DEFF Research Database (Denmark)

    Schrittesser, David; Friedman, Sy David

    We prove that it is consistent (relative to a Mahlo cardinal) that all projective sets of reals are Lebesgue measurable, but there is a ∆13 set without the Baire property. The complexity of the set which provides a counterexample to the Baire property is optimal.......We prove that it is consistent (relative to a Mahlo cardinal) that all projective sets of reals are Lebesgue measurable, but there is a ∆13 set without the Baire property. The complexity of the set which provides a counterexample to the Baire property is optimal....

  17. Project Radon

    International Nuclear Information System (INIS)

    Ekholm, S.

    1988-01-01

    The project started in March 1987. The objective is to perform radon monitoring in 2000 dwellings occupied by people employed by State Power Board and to continue to contribute to the development of radon filters. The project participates in developing methods for radon measurement and decontamination and in adapting the methods to large scale application. About 400 so called radon trace measurements (coarse measurement) and about 10 action measurements (decontamination measurement) have been made so far. Experience shows that methods are fully applicable and that the decontamination measures recommended give perfectly satisfactory results. It is also established that most of the houses with high radon levels have poor ventilation Many of them suffer from moisture and mould problems. The work planned for 1988 and 1989 will in addition to measurements be directed towards improvement of the measuring methods. An activity catalogue will be prepared in cooperation with ventilation enterprises. (O.S.)

  18. PARTNER Project

    CERN Multimedia

    Ballantine, A; Dixon-Altaber, H; Dosanjh, M; Kuchina, L

    2011-01-01

    Hadrontherapy uses particle beams to treat tumours located near critical organs and tumours that respond poorly to conventional radiation therapy. It has become evident that there is an emerging need for reinforcing research in hadrontherapy and it is essential to train professionals in this rapidly developing field. PARTNER is a 4-year Marie Curie Training project funded by the European Commission with 5.6 million Euros aimed at the creation of the next generation of experts. Ten academic institutes and research centres and two leading companies are participating in PARTNER, that is coordinated by CERN, forming a unique multidisciplinary and multinational European network. The project offers research and training opportunities to 25 young biologists, engineers, physicians and physicists and is allowing them to actively develop modern techniques for treating cancer in close collaboration with leading European Institutions. For this purpose PARTNER relies on cutting edge research and technology development, ef...

  19. Swedish projects

    International Nuclear Information System (INIS)

    Thunell, J.

    1992-01-01

    A description is given of research activities, concerning heating systems, which were carried out in Sweden during 1991. The main subject areas dealt with under the gas technology group within the area of heating systems were catalytic combustion, polyethylene materials, and gas applications within the paper and pulp industries. A list is given of the titles of project reports published during 1991 and of those begun during that year. Under the Swedish Centre for Gas Technology (SGC), the main areas of research regarding gas applications were polyethylene materials, industrial applications and the reduction of pollutant emissions. A detailed list is given of research projects which were in progress or proposed by March 1992 under the heating system gas technology research group in Sweden. This list also presents the aims and descriptions of the methods, etc. (AB)

  20. AVE project

    International Nuclear Information System (INIS)

    2004-01-01

    During 1998, ANAV began to optimize Human Resources to cope with the ERE and ANA-ANV integration. Project AVE was intended to achieve an orderly transfer of know-how, skills, attitudes and experiences. The most complex part was renovation of personnel with Operating Licenses. Nearly 140 people had joined the organization by late December 2003. This opportunity was seized to draw up a new Training Manual, and a common Initial Training Plan was designed for the two plants, accounting for the singularities of each one. The plan is divided into 5 modules: Common Training, Specific Training, PEI/CAT, Management, and on-the-job Training. The training environments were defined according to the nature of the capabilities to be acquired. Project AVE resulted in the merger of the Asco and Vandellos II Training services. (Author)

  1. Spent Nuclear Fuel project, project management plan

    International Nuclear Information System (INIS)

    Fuquay, B.J.

    1995-01-01

    The Hanford Spent Nuclear Fuel Project has been established to safely store spent nuclear fuel at the Hanford Site. This Project Management Plan sets forth the management basis for the Spent Nuclear Fuel Project. The plan applies to all fabrication and construction projects, operation of the Spent Nuclear Fuel Project facilities, and necessary engineering and management functions within the scope of the project

  2. ARTIST Project

    CSIR Research Space (South Africa)

    Ferguson, K

    2012-10-01

    Full Text Available Biennial Conference Presented by: Keith Ferguson Date: 9 October 2012 Mobile IPTV Broadcasting Platform Consortium: CSIR, UCT, ECA Funded by TIA 2008-2011 ARTIST Project Min time - sacrifice quality Max quality - sacrifice time Application Context... idth > ARTIST Platform Advertiser Client 1 Client 2 Client 3 Client 4 Sport channel News channel Wildlife channel Advert database Transaction database Transcoder Servers Media Switching Servers INTERNET Channel viewing Advert upload...

  3. CARA project

    International Nuclear Information System (INIS)

    Bergallo, Juan E.; Brasnarof, Daniel O.

    2000-01-01

    The CARA (Advanced Fuels for Argentine Reactors) Project successfully completed its first stage, phase one, last year. The performance of this fuel has been partially examined, using CNEA and CONUAR facilities and personnel. With the results obtained in this stage, determined by the corresponding tests and verification of the fuel behavior, the performance of the second stage started immediately afterwards. Works performed and results obtained during the development of the second stage are generally described in this paper. (author)

  4. Polytope projects

    CERN Document Server

    Iordache, Octavian

    2013-01-01

    How do you know what works and what doesn't? This book contains case studies highlighting the power of polytope projects for complex problem solving. Any sort of combinational problem characterized by a large variety of possibly complex constructions and deconstructions based on simple building blocks can be studied in a similar way. Although the majority of case studies are related to chemistry, the method is general and equally applicable to other fields for engineering or science.

  5. Projection Methods

    DEFF Research Database (Denmark)

    Wagner, Falko Jens; Poulsen, Mikael Zebbelin

    1999-01-01

    When trying to solve a DAE problem of high index with more traditional methods, it often causes instability in some of the variables, and finally leads to breakdown of convergence and integration of the solution. This is nicely shown in [ESF98, p. 152 ff.].This chapter will introduce projection...... methods as a way of handling these special problems. It is assumed that we have methods for solving normal ODE systems and index-1 systems....

  6. Project Phaseolus

    International Nuclear Information System (INIS)

    Anon.

    Research carried out through the Phaseolus Project of the 'Centro de Energia Nuclear na Agricultura' (CENA) Piracicaba, Sao Paulo State, Brazil, is described. It comprises the following subject s: plant breeding; nitrogen fixation; tissue cultures; proteins; photosynthetic efficiency; soil-plant interactions; electron microscopy of the golden mosaic virus; pest control; production of 15 N-enriched ammonium sulfate, and determination of elements in the beans plant. (M.A.) [pt

  7. Numatron project

    Energy Technology Data Exchange (ETDEWEB)

    Sugimoto, K [Osaka Univ., Toyonaka (Japan). Dept. of Physics; Hirao, Yasuo

    1977-04-01

    A project of high energy heavy ion acceleration is under consideration. The high energy heavy ions can produce highly condensed states of nuclei. A new phase of nucleus would be seen at the incident energy higher than 140 MeV/nucleon. High energy heavy ions causing high density states and meson emission will produce various new nuclides. Process of formation of atomic elements will be studied. Various fields of science can be also investigated by the high energy heavy ions. Spectroscopic study of multi-valent ions will be made high energy uranium. Study of materials for the fusion reactor is important. Impurity heavy ion from the wall of the fusion reactor may lose the energy of the reactor, and the characteristic features of heavy ions should be investigated. The highly ionized states of atoms are also produced by heavy ion injection into material. Several projects of heavy ion acceleration are in progress in the world. The Numatron project in Japan is to construct a combination machine of a Cockcroft type machine, three linear accelerator and a synchrotron. The planned energy of the machine is 670 MeV/nucleon. Technical problems are under investigation.

  8. Project Exodus

    Science.gov (United States)

    1990-01-01

    Project Exodus is an in-depth study to identify and address the basic problems of a manned mission to Mars. The most important problems concern propulsion, life support, structure, trajectory, and finance. Exodus will employ a passenger ship, cargo ship, and landing craft for the journey to Mars. These three major components of the mission design are discussed separately. Within each component the design characteristics of structures, trajectory, and propulsion are addressed. The design characteristics of life support are mentioned only in those sections requiring it.

  9. CAREM Project

    International Nuclear Information System (INIS)

    Ishida, Viviana; Gomez, Silvia

    2001-01-01

    CAREM project consists on the development and design of an advanced nuclear power plant. CAREM is a very low power innovative reactor conceived with new generation design solutions. Based on an indirect cycle integrated light water reactor using enriched uranium, CAREM has some distinctive features that greatly simplify the reactor and also contribute to a high level of safety: integrated primary system, primary system cooling by natural convection, self pressurization, and passive safety systems. In order to verify its innovative features the construction of a prototype is planned. (author)

  10. PORTNUS Project

    Energy Technology Data Exchange (ETDEWEB)

    Loyal, Rebecca E. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2015-07-14

    The objective of the Portunus Project is to create large, automated offshore ports that will the pace and scale of international trade. Additionally, these ports would increase the number of U.S. domestic trade vessels needed, as the imported goods would need to be transported from these offshore platforms to land-based ports such as Boston, Los Angeles, and Newark. Currently, domestic trade in the United States can only be conducted by vessels that abide by the Merchant Marine Act of 1920 – also referred to as the Jones Act. The Jones Act stipulates that vessels involved in domestic trade must be U.S. owned, U.S. built, and manned by a crew made up of U.S. citizens. The Portunus Project would increase the number of Jones Act vessels needed, which raises an interesting economic concern. Are Jones Act ships more expensive to operate than foreign vessels? Would it be more economically efficient to modify the Jones Act and allow vessels manned by foreign crews to engage in U.S. domestic trade? While opposition to altering the Jones Act is strong, it is important to consider the possibility that ship-owners who employ foreign crews will lobby for the chance to enter a growing domestic trade market. Their success would mean potential job loss for thousands of Americans currently employed in maritime trade.

  11. FLORAM project

    Energy Technology Data Exchange (ETDEWEB)

    Zulauf, W E [Sao Paolos Environmental Secretariat, Sao Paolo (Brazil); Goelho, A S.R. [Riocell, S.A. (Brazil); Saber, A [IEA-Instituto de Estudos Avancados (Brazil); and others

    1996-12-31

    The project FLORAM was formulated at the `Institute for Advanced Studies` of the University of Sao Paulo. It aims at decreasing the level of carbon dioxide in the atmosphere and thus curbing the green-house effect by way of a huge effort of forestation and reforestation. The resulting forests when the trees mature, will be responsible for the absorption of about 6 billion tons of excess carbon. It represents 5 % of the total amount of CO{sub 2} which is in excess in the earth`s atmosphere and represents 5 % of the available continental surfaces which can be forested as well. Therefore, if similar projects are implemented throughout the world, in theory all the exceeding CO{sub 2}, responsible for the `greenhouse effect`, (27 % or 115 billion tons of carbon) would be absorbed. Regarding this fact, there would be a 400 million hectar increase of growing forests. FLORAM in Brazil aims to plant 20.000.000 ha in 2 years at a cost of 20 billion dollars. If it reaches its goals that will mean that Brazil will have reforested an area almost half as big as France. (author)

  12. FLORAM project

    Energy Technology Data Exchange (ETDEWEB)

    Zulauf, W.E. [Sao Paolos Environmental Secretariat, Sao Paolo (Brazil); Goelho, A.S.R. [Riocell, S.A. (Brazil); Saber, A. [IEA-Instituto de Estudos Avancados (Brazil)] [and others

    1995-12-31

    The project FLORAM was formulated at the `Institute for Advanced Studies` of the University of Sao Paulo. It aims at decreasing the level of carbon dioxide in the atmosphere and thus curbing the green-house effect by way of a huge effort of forestation and reforestation. The resulting forests when the trees mature, will be responsible for the absorption of about 6 billion tons of excess carbon. It represents 5 % of the total amount of CO{sub 2} which is in excess in the earth`s atmosphere and represents 5 % of the available continental surfaces which can be forested as well. Therefore, if similar projects are implemented throughout the world, in theory all the exceeding CO{sub 2}, responsible for the `greenhouse effect`, (27 % or 115 billion tons of carbon) would be absorbed. Regarding this fact, there would be a 400 million hectar increase of growing forests. FLORAM in Brazil aims to plant 20.000.000 ha in 2 years at a cost of 20 billion dollars. If it reaches its goals that will mean that Brazil will have reforested an area almost half as big as France. (author)

  13. SISCAL project

    Science.gov (United States)

    Santer, Richard P.; Fell, Frank

    2003-05-01

    The first "ocean colour" sensor, Coastal Zone Color Scanner (CZCS), was launched in 1978. Oceanographers learnt a lot from CZCS but it remained a purely scientific sensor. In recent years, a new generation of satellite-borne earth observation (EO) instruments has been brought into space. These instruments combine high spectral and spatial resolution with revisiting rates of the order of one per day. More instruments with further increased spatial, spectral and temporal resolution will be available within the next years. In the meantime, evaluation procedures taking advantage of the capabilities of the new instruments were derived, allowing the retrieval of ecologically important parameters with higher accuracy than before. Space agencies are now able to collect and to process satellite data in real time and to disseminate them via the Internet. It is therefore meanwhile possible to envisage using EO operationally. In principle, a significant demand for EO data products on terrestrial or marine ecosystems exists both with public authorities (environmental protection, emergency management, natural resources management, national parks, regional planning, etc) and private companies (tourist industry, insurance companies, water suppliers, etc). However, for a number of reasons, many data products that can be derived from the new instruments and methods have not yet left the scientific community towards public or private end users. It is the intention of the proposed SISCAL (Satellite-based Information System on Coastal Areas and Lakes) project to contribute to the closure of the existing gap between space agencies and research institutions on one side and end users on the other side. To do so, we intend to create a data processor that automatically derives and subsequently delivers over the Internet, in Near-Real-Time (NRT), a number of data products tailored to individual end user needs. The data products will be generated using a Geographical Information System (GIS

  14. Project Financing

    OpenAIRE

    S. GATTI

    2005-01-01

    Στην εισαγωγή της παρούσας εργασίας δίνεται ο ορισμός του project financing, τα ιστορικά στοιχεία και οι τάσεις αγοράς του. Στο πρώτο κεφάλαιο αναφέρεται γιατί οι εταιρείες προτιμούν την χρηματοδότηση με project financing. Γίνεται λόγος για τα πλεονεκτήματά του έναντι της άμεσης χρηματοδότησης, καθώς και για τα μειονεκτήματα του project financing. Στο δεύτερο κεφάλαιο παρουσιάζονται τα χρηματοοικονομικά στοιχεία και ο ρόλος του χρηματοοικονομικού συμβούλου. Στην τρίτη ενότητα γίνεται η αναγνώ...

  15. Project: Ultracentrifuges

    International Nuclear Information System (INIS)

    Olea C, O.

    1990-07-01

    The trans elastic ultracentrifuge of magnetic suspension, is an instrument that arose of an interdisciplinary group directed by the Dr. James Clark Keith where it was projected, designed and built a centrifuge that didn't exist, to be applied in forced diffusion of uranium, like one of the many application fields. The written present, has as purpose to give to know the fundamental physical principles of this technology, its fundamental characteristics of design, the application of this in the separation process of isotopes, as well as the previous studies and essential control parameters in the experimental processes, the same thing that, the most outstanding results and the detection systems used in the confirmation and finally, the carried out potential applications of the principles of the ultracentrifugation technology. (Author)

  16. ENVISION Project

    CERN Multimedia

    Ballantine, A; Dixon-Altaber, H; Dosanjh, M; Kuchina, L

    2011-01-01

    Hadrontherapy is a highly advanced technique of cancer radiotherapy that uses beams of charged particles (ions) to destroy tumour cells. While conventional X-rays traverse the human body depositing radiation as they pass through, ions deliver most of their energy at one point. Hadrontherapy is most advantageous once the position of the tumour is accurately known, so that healthy tissues can be protected. Accurate positioning is a crucial challenge for targeting moving organs, as in lung cancer, and for adapting the irradiation as the tumour shrinks with treatment. Therefore, quality assurance becomes one of the most relevant issues for an effective outcome of the cancer treatment. In order to improve the quality assurance tools for hadrontherapy, the European Commission is funding ENVISION, a 4-year project that aims at developing solutions for: real-• time non invasive monitoring • quantitative imaging • precise determination of delivered dose • fast feedback for optimal treatment planning • real-t...

  17. EUROTRAC projects

    International Nuclear Information System (INIS)

    Slanina, J.; Arends, B.G.; Wyers, G.P.

    1992-07-01

    The projects discussed are BIATEX (BIosphere-ATmosphere EXchange of pollutants), ACE (Acidity in Clouds Experiment) and GCE (Ground-based Cloud Experiment). ECN also coordinates BIATEX and contributes to the coordination of EUROTRAC. Research in BIATEX is aimed at the development of equipment, by which atmosphere-surface interactions of air pollution can be quantified. A ion chromatograph, connected to a rotating denuder, is developed to be applicated in the field for on-line analysis of denuder extracts and other samples. To investigate dry deposition of ammonia a continuous-flow denuder has been developed. A thermodenuder system to measure the concentrations of HNO 3 and NH 4 NO 3 in the ambient air is optimized to determine depositions and is part of the ECN monitoring station in Zegveld, Netherlands. An aerosol separation technique, based on a cyclone separator, has also been developed. All this equipment has been used in field experiments above wheat and heather. An automated monitoring station for long-term investigations of NH 3 , HNO 3 and SO 2 dry deposition on grassland and the impact of the deposition on the presence and composition of water films has been set up and fully tested. Research in GCE concerns the uptake and conversion of air pollution in clouds (cloud chemistry). Measuring equipment from several collaborative institutes has been specified and calibrated in a cloud chamber at ECN. The ECN contribution is the determination of the gas phase composition and the micro-physical characterization of the clouds. Measurement campaigns were carried out in the Po area (Italy) in fog, and in Kleiner Feldberg near Frankfurt, Germany, in orographic clouds. Estimations are given of the deposition of fog water and cloud water on forests in the Netherlands and the low mountain range in Germany. The project ACE was not started because of financial reasons and will be reconsidered. 26 figs., 1 tab., 3 apps., 34 refs

  18. Project Success in IT Project Management

    OpenAIRE

    Siddiqui, Farhan Ahmed

    2010-01-01

    The rate of failed and challenged Information Technology (IT) projects is too high according to the CHAOS Studies by the Standish Group and the literature on project management (Standish Group, 2008). The CHAOS Studies define project success as meeting the triple constraints of scope, time, and cost. The criteria for project success need to be agreed by all parties before the start of the project and constantly reviewed as the project progresses. Assessing critical success factors is another ...

  19. Project LASER

    Science.gov (United States)

    1990-01-01

    NASA formally launched Project LASER (Learning About Science, Engineering and Research) in March 1990, a program designed to help teachers improve science and mathematics education and to provide 'hands on' experiences. It featured the first LASER Mobile Teacher Resource Center (MTRC), is designed to reach educators all over the nation. NASA hopes to operate several MTRCs with funds provided by private industry. The mobile unit is a 22-ton tractor-trailer stocked with NASA educational publications and outfitted with six work stations. Each work station, which can accommodate two teachers at a time, has a computer providing access to NASA Spacelink. Each also has video recorders and photocopy/photographic equipment for the teacher's use. MTRC is only one of the five major elements within LASER. The others are: a Space Technology Course, to promote integration of space science studies with traditional courses; the Volunteer Databank, in which NASA employees are encouraged to volunteer as tutors, instructors, etc; Mobile Discovery Laboratories that will carry simple laboratory equipment and computers to provide hands-on activities for students and demonstrations of classroom activities for teachers; and the Public Library Science Program which will present library based science and math programs.

  20. Project Longshot

    Science.gov (United States)

    West, J. Curtis; Chamberlain, Sally A.; Stevens, Robert; Pagan, Neftali

    1989-01-01

    Project Longshot is an unmanned probe to our nearest star system, Alpha Centauri, 4.3 light years away. The Centauri system is a trinary system consisting of two central stars (A and B) orbiting a barycenter, and a third (Proxima Centauri) orbiting the two. The system is a declination of -67 degrees. The goal is to reach the Centauri system in 50 years. This time space was chosen because any shorter time would be impossible of the relativistic velocities involved, and any greater time would be impossible because of the difficulty of creating a spacecraft with such a long lifetime. Therefore, the following mission profile is proposed: (1) spacecraft is assembled in Earth orbit; (2) spacecraft escapes Earth and Sun in the ecliptic with a single impulse maneuver; (3) spacecraft changed declination to point toward Centauri system; (4) spacecraft accelerates to 0.1c; (5) spacecraft coasts at 0.1c for 41 years; (6) spacecraft decelerates upon reaching Centauri system; and (7) spacecraft orbits Centauri system, conducts investigations, and relays data to Earth. The total time to reach the Centauri system, taking into consideration acceleration and deceleration, will be approximately 50 years.

  1. Project Success in Agile Development Software Projects

    Science.gov (United States)

    Farlik, John T.

    2016-01-01

    Project success has multiple definitions in the scholarly literature. Research has shown that some scholars and practitioners define project success as the completion of a project within schedule and within budget. Others consider a successful project as one in which the customer is satisfied with the product. This quantitative study was conducted…

  2. Ace Project as a Project Management Tool

    Science.gov (United States)

    Cline, Melinda; Guynes, Carl S.; Simard, Karine

    2010-01-01

    The primary challenge of project management is to achieve the project goals and objectives while adhering to project constraints--usually scope, quality, time and budget. The secondary challenge is to optimize the allocation and integration of resources necessary to meet pre-defined objectives. Project management software provides an active…

  3. Organizations, projects and culture

    NARCIS (Netherlands)

    J. van Cleeff; Pieter van Nispen tot Pannerden

    2016-01-01

    Purpose: to explore and demonstrate the effects of organizational culture on projects, in particular project culture and project management style. Methodology/approach: descriptive and explorative; through students’ groups. Findings: the cultural relationship between organizations, their projects

  4. INTEGRATIVE PSYCHOTHERAPY AND MINDFULNESS: THE CASE OF SARA

    Directory of Open Access Journals (Sweden)

    Mihael Černetič

    2015-02-01

    Full Text Available The article explores the relationship between Integrative Psychotherapy and mindfulness on a theoretical as well as practical level. Although mindfulness is not an explicit constituent of Integrative Psychotherapy, the two are arguably a natural fit. Mindfulness has the potential to enhance internal and external contact, a central concept in Integrative Psychotherapy, as well as strengthen a client’s Adult ego state. This article presents a case study whereby Integrative Psychotherapy is analysed from the perspective of mindfulness. Within the course of therapy, parallels were observed between the client's increased mindfulness, improved internal and external contact, strengthened Adult ego state, mastery of introjections, as well as diminished feelings of guilt, improved mood, self care and ability to engage in appropriate separation and individuation. These gains support the conclusion that Integrative Psychotherapy and mindfulness are inherently related and that explicit incorporation of mindfulness may enhance the therapeutic process of Integrative Psychotherapy.

  5. Discovery of carbon nanotubes. Sara ni carbon nanotube e

    Energy Technology Data Exchange (ETDEWEB)

    Iijima, S

    1994-01-20

    This paper describes the following matters on carbon nanotubes (CNt): CNt is discovered in carbon deposits generated in the tip of a negative electrode during DC arc discharge between carbon electrodes. CNt has a construction in which cylinders made of normally several layers are superposed, based on cylindrical crystals in a single layer with six-member rings of carbon atoms laid out. Spiral arrangement of carbon six-member rings has been discovered in the single-layered crystals. Five-member rings exist in a location where the CNt tip is closed, and seven-member rings in a location where the CNt presents a saddle-like curve, without exceptions. It is introduced theoretically that the electronic structure of the single-layered CNt depends on the cylinder diameter and spiral pitch. Replacing part of the carbon negative electrode with iron, and vaporizing iron and carbon simultaneously through arc discharge can result in a single-layered CNt with a diameter of 1 nm. Heating the CNt deposited with metallic lead in an oxygen atmosphere can form CNt containing lead compounds. 19 refs., 9 figs.

  6. AFSC/REFM: Alaska Stock Assessment Results Archive (SARA)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Each year over 50 Alaskan groundfish stock assessments report the condition of Alaskan fisheries resources in the U.S. Exclusive Economic Zone. Stock assessment...

  7. INTEGRATIVE PSYCHOTHERAPY AND MINDFULNESS: THE CASE OF SARA

    OpenAIRE

    Mihael Černetič

    2015-01-01

    The article explores the relationship between Integrative Psychotherapy and mindfulness on a theoretical as well as practical level. Although mindfulness is not an explicit constituent of Integrative Psychotherapy, the two are arguably a natural fit. Mindfulness has the potential to enhance internal and external contact, a central concept in Integrative Psychotherapy, as well as strengthen a client’s Adult ego state. This article presents a case study whereby Integrative Psychotherapy is ana...

  8. Gene : CBRC-SARA-01-0604 [SEVENS

    Lifescience Database Archive (English)

    Full Text Available and polyadenylation specific factor 1, 160kDa, isoform CRA_a [Homo sapiens] gb|EAW82107.1| cleavage and poly...adenylation specific factor 1, 160kDa, isoform CRA_a [Homo sapiens] gb|EAW82108.1| cleavage and polyadenylat...ion specific factor 1, 160kDa, isoform CRA_a [Homo sapiens] 3e-16 77% MSTVPTVSCTS...TDRWGLVGTGRCYGSGRGGSMLASCGELSQAIALPKPVLSGHQAGSDPAGSSLYLVLPEGRCLPSVPAHVCPGTAEPAQHSQTPLQRELRISVLPAYLSYDAPWPVRKIPLRCTAHYVAYHVESKVCPWAGVPRAGRPGPQAQPALSFRCMQWPPAPIRHAPASHA ...

  9. Evaluation of Project Achievements in VOMARE -project

    OpenAIRE

    Kokkarinen, Eeva

    2011-01-01

    The purpose of the thesis is to study the achievements of VOMARE –project from the Finnish Lifeboat Institutions perspective. The organisation is a roof organisation for voluntary maritime rescue operation in Finland. The Finnish Lifeboat Institution is a lead partner in VOMARE –project which is EU funded project and the aim of the project is to start voluntary rescue operations in Estonia. The theoretical part of the work is divided into two main categories; project management and planni...

  10. Modeling of reflood of severely damaged reactor core

    OpenAIRE

    Bachrata, Andrea

    2012-01-01

    Les événements récents au Japon sur les centrales nucléaires de Fukushima ont montré que des accidents conduisant à la fusion du cœur peuvent survenir bine plus souvent qu’on ne l’avait supposé et que leur impact sur l’environnement et la vie publique est considérable. Pour les réacteurs actuels, un des moyens principaux pour stopper la progression de l’accident est de tenter de refroidir le plus rapidement possible les matériaux en utiliser une injection d’eau de secours. Suivant l’instant d...

  11. Transient quenching of superheated debris beds during bottom reflood

    International Nuclear Information System (INIS)

    Tutu, N.K.; Ginsberg, T.; Klein, J.; Schwarz, C.E.; Klages, J.

    1984-01-01

    The experimental data suggest that for small liquid supply rate and low initial particle temperature, the bed quench process is a one-dimensional frontal phenomenon. The bed heat flux is constant during most of the duration of the quench period. The range of conditions which display one-dimensional frontal cooling characteristics is identified as the deep bed regime of bed quenching, and a limiting mathematical model was developed to describe the observed behavior. For large liquid supply rate and high initial bed temperature, the bed quench process is a complex phenomenon. Under these conditions, the bed heat flux displays a nonuniform time dependence. In order to characterize this shallow bed regime, it was necessary to develop a detailed transient model of the coolant-debris interaction. This model, while developed for the shallow bed regime, also applies to the deep bed regime. Numerical computations clearly demonstrate the importance of developing a general reliable model for the solid-fluid heat transfer coefficients

  12. Reflooding the Faguibine floodplain system, northern Mali: potential ...

    African Journals Online (AJOL)

    An economic evaluation of the system in 2011 showed US$100 000 per year of net income per flooded km² in Lake Faguibine, allowing vulnerable people to practise recession agriculture, to fish and to graze livestock. An intensive investment phase, combined with an approach of rebuilding local governance systems and ...

  13. Improvement of digital data acquisition system in reflood test rig

    International Nuclear Information System (INIS)

    Sudoh, Takashi; Murao, Yoshio; Niitsuma, Yasushi

    1979-03-01

    The original master digital data acquisition system was designed to collect 30 channels of analog data rapidly and convert them into digital form for recording on a magnetic tape. Due to the increases in the number of channels and the ranges of measurement, an additional acquisition device was needed for the original system. This report descrives the design of the additional data acquisition device and the results of performance tests. The operational manual is attached as an appendix. It was confirmed that the new system satisfied the requirements of system. (author)

  14. Heat transfer in circular ring channel under reflooding conditions

    International Nuclear Information System (INIS)

    Blaha, V.; Nikonov, S.P.

    1981-01-01

    The method and equipment are described for flooding experiments in a ring-shaped channel with an unheated external wall. The values measured during the experiment are given of tube wall temperature, the power input of the heating rod, the temperature of the flooding medium, the flow, the temperature of the envelope, pressure gradient in the measured section, pressure in the storage tank and temperature in the upper chamber. The dependence is shown of the coefficient of heat transfer on the temperature gradient between the wall and the medium which may be degasified water, CO 2 saturated water of N 2 saturated water. (J.B.)

  15. Rewetting and liquid entrainment during reflooding: state of the art

    International Nuclear Information System (INIS)

    Elias, E.; Yadigaroglu, G.

    1977-05-01

    Considerable interest has recently been generated in the problems of surface rewetting and the physics of liquid droplet entrainment due to their role in light water nuclear reactor safety. Published models of the rewetting process include simple one-dimensional solutions in two axial regions, one-dimensional solutions in three axial regions with or without precursory cooling, one- and two-dimensional numerical-difference techniques using temperature dependent heat transfer coefficients, and analytical two-dimensional solutions. The basic assumptions of these models and the numerical values assigned to the various parameters, as well as empirical rewetting correlations, are discussed. The various mechanisms for liquid droplet entrainment and analytical formulations of the critical gas velocity and of the droplet diameter at the onset of entrainment are reviewed

  16. Experimental Setup for Reflood Quench of Accident Tolerant Fuel Claddings

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Chan; Lee, Kwan Geun; In, Wang Kee [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    The concept of accident tolerant fuel (ATF) is a solution to suppress the hydrogen generation in loss of coolant accident (LOCA) situation without safety injection, which was the critical incident in the severe accident in the Fukushima. The changes in fuel and cladding materials may cause a significant difference in reactor performance in long term operation. Properties in terms of material science and engineering have been tested and showed promising results. However, numerous tests are still required to ensure the design performance and safety. Thermal hydraulic tests including boiling and quenching are partly confirmed, but not yet complete. We have been establishing the experimental setup to confirm the properties in the terms of thermal hydraulics. Design considerations and preliminary tests are introduced in this paper. An experimental setup to test thermal hydraulic characteristics of new ATF claddings are established and tested. The W heater set inside the cladding is working properly, exceeding 690 W/m linear power with thermocouples and insulating ceramic sheaths inside. The coolant injection control was also working in good conditions. The setup is about to complete and going to simulate quenching behavior of the ATF in the LOCA situation.

  17. Managing projects using a project management approach

    Directory of Open Access Journals (Sweden)

    Marko D. Andrejić

    2011-04-01

    Full Text Available Modern management theory treats all complex tasks and duties like projects and make these projects possible to be managed by a particular organizational-management concept in order to achieve a goal effectively. A large number of jobs and tasks performed in the system of defense or for defense purposes have the characteristics of projects. Project management is both a skill and a science of monitoring human, material, financial, energy and other resources to achieve required objectives within the given limits: deadlines, time, budget, possibility of realization and the satisfaction of the interests of all project participants. Project management is a traditional area of applied (or functional management focused on managing complex and uncertain situations with defined goals. Introduction In conditions of rapid change and high uncertainty, only adaptive organizations survive, i. e. those that are able not only to react quickly to changes but also to proactively take advantage of changes. Development of project management The biggest influence on the development of the area had complex jobs within the engineering profession. In parallel with the traditional approach new approaches began to develop, while the traditional one still remained in use. Contrary to the traditional engineering approach, a dynamic model first developed in order to respond to demands for greater control of costs. Project management Project management is a skill and knowledge of human and material resources to achieve set objectives within prescribed limits: deadlines, time, budget, possibility of realization, and the satisfaction of all participants in the project. In order to realize a project effectively, it is necessary to manage it rationally. Planning and project management A project plan is a document that allows all team members insight on where to go, when to start and when to arrive, what is necessary to be done in order to achieve the project objectives and what

  18. Storytelling in Projects

    DEFF Research Database (Denmark)

    Munk-Madsen, Andreas; Andersen, Peter Bøgh

    2006-01-01

    project managers should not only be concerned with project plans, but also with project stories. In this paper we explore some basic principles for transforming project plans into appealing stories. We discuss what may happen to stories once they are released into public space. And we illustrate how......Plans and stories are two different ways of communicating about projects. Project plans are formalized descriptions, primarily supporting coordination. Project stories are accounts whose primary function is emotional appeal. Project stories influence the projects’ chances of success. Therefore...... the possibilities of telling favorable stories may have repercussions on the project planning....

  19. The Ethiopian Flora Project

    DEFF Research Database (Denmark)

    Demissew, Sebsebe; Brochmann, Christian; Kelbessa, Ensermu

    2011-01-01

    The account reviews and analyses the scietific projects derived from activities in connection with the Ethiopian Flora Project, including the [Ethiopian] Monocot Project, the Afro-alpine "Sky-island" project, the Vegetation and Ecological Conditions of Plantations Project, the Fire Ecology Projec...

  20. Capital projects coordination

    Directory of Open Access Journals (Sweden)

    Zubović Jovan

    2004-01-01

    Full Text Available This paper looks at the difficulties of managing modem capital projects and endeavors to reduce the complexities to simpler and more understandable terms. It examines the project environment, defines project management and discusses points of difference from traditional management. In the second part of the paper are presented fundamentals for project success for different types of projects.

  1. From project management to project leadership

    NARCIS (Netherlands)

    Braun, F.; Avital, M.

    2010-01-01

    It is virtually a truism that good leadership practices can help project managers with attaining the desired project outcome. However, a better understanding of which leadership practices enable project managers to be more effective warrants further investigation. Subsequently, in this study, we

  2. An IS Project Management Course Project

    Science.gov (United States)

    Frank, Ronald L.

    2010-01-01

    Information Systems curricula should provide project management (PM) theory, current practice, and hands-on experience. The schedule usually does not allow time in Analysis and Design courses for development oriented project management instruction other than a short introduction. Similarly, networking courses usually don't put project management…

  3. Managing Projects for Change: Contextualised Project Management

    Science.gov (United States)

    Tynan, Belinda; Adlington, Rachael; Stewart, Cherry; Vale, Deborah; Sims, Rod; Shanahan, Peter

    2010-01-01

    This paper will detail three projects which focussed on enhancing online learning at a large Australian distance education University within a School of Business, School of Health and School of Education. Each project had special funding and took quite distinctive project management approaches, which reflect the desire to embed innovation and…

  4. I-15 North Project

    Science.gov (United States)

    2013-11-05

    Goals of this project were as follows: (1) Conduct a comprehensive evaluation study on Nevada's I-15 North Design Build Project; (2) Analyze project implementation with respect to construction zone rules by which the contractor had to abide; (3) Anal...

  5. Project assembling and commissioning of a rewetting test facility

    International Nuclear Information System (INIS)

    Rezende, H.C.

    1985-08-01

    A test facility (ITR - Instalacao de Testes de Remolhamento) has been erected at the Thermal-hydraulics Laboratory of CDTN, dedicated to the investigation of the basic phenomena that can occur during the reflood phase of a Loss of Coolant Accident (LOCA) in a Pressurized Water Reactor (PWR), utilizing tubular and annular test sections. The present work consists in a presentation of the facility design and a report of its commissioning. The mechanical aspects of the facility, its power supply system and its instrumentation are described. The results of the instruments calibration and two operational tests are presented and a comparison is done with calculations perfomed usign a computer code. (Author) [pt

  6. Web Project Management

    OpenAIRE

    Suralkar, Sunita; Joshi, Nilambari; Meshram, B B

    2013-01-01

    This paper describes about the need for Web project management, fundamentals of project management for web projects: what it is, why projects go wrong, and what's different about web projects. We also discuss Cost Estimation Techniques based on Size Metrics. Though Web project development is similar to traditional software development applications, the special characteristics of Web Application development requires adaption of many software engineering approaches or even development of comple...

  7. USAID Anticorruption Projects Database

    Data.gov (United States)

    US Agency for International Development — The Anticorruption Projects Database (Database) includes information about USAID projects with anticorruption interventions implemented worldwide between 2007 and...

  8. Project 2010 Bible

    CERN Document Server

    Marmel, Elaine

    2010-01-01

    A comprehensive reference on the latest version of the leading enterprise project management software: Microsoft Project 2010. Microsoft Project allows users to manage business activities effectively by sharing project information, performing modeling and scenario analyses, standardizizing reporting processes, and more. This soup-to-nuts reference covers both the professional and standard versions of the latest iteration of Microsoft Project, as well as Project Server, so that you can efficiently manage your business projects. Veteran author Elaine Marmel begins with an overview of project man

  9. Project 2010 For Dummies

    CERN Document Server

    Muir, Nancy C

    2010-01-01

    A friendly reference guide to Microsoft Project, the leading enterprise project management software. As project management software, Microsoft Project allows you to oversee your business activities effectively. You can manage resources, share project info, perform modeling and scenario analysis, and standardize reporting processes. This easy-to-understand guide is completely updated to cover the latest changes and newest enhancements to Project 2010 and shows you how to get Project 2010 to work for you. After an introduction to basic project management concepts, you'll discover the mechanics o

  10. Project development symposium

    Energy Technology Data Exchange (ETDEWEB)

    1983-01-01

    Papers were presented on the following: project evaluation; case studies - minerals; finance; applied finance; legal; manpower/industrial relations; and new technologies. Those papers on the coal industry were: mine planning for coal project development; the planning and management of a lignite exploration contract in Thailand; development of the West Cliff extended project; Ulan: a resource development; Saxonvale mine development a case study in project planning and project management; the role of marketing in the development of a new coal project; technical support for coal marketing; infrastructure development for the Ulan project; underground mine project developments; the bucketwheel excavator at Goonyella - a case study; tax aspects of mining development projects; cost of capital mining development projects; and trends in development project finance. 16 papers were abstracted separately.

  11. PROJECT SCOPE MANAGEMENT PROCESS

    Directory of Open Access Journals (Sweden)

    Yana Derenskaya

    2018-01-01

    Full Text Available The purpose of the article is to define the essence of project scope management process, its components, as well as to develop an algorithm of project scope management in terms of pharmaceutical production. Methodology. To carry out the study, available information sources on standards of project management in whole and elements of project scope management in particular are analysed. Methods of system and structural analysis, logical generalization are used to study the totality of subprocesses of project scope management, input and output documents, and to provide each of them. Methods of network planning are used to construct a precedence diagram of project scope management process. Results of the research showed that components of the project scope management are managing the scope of the project product and managing the content of project work. It is the second component is investigated in the presented work as a subject of research. Accordingly, it is defined that project scope management process is to substantiate and bring to the realization the necessary amount of work that ensures the successful implementation of the project (achievement of its goal and objectives of individual project participants. It is also determined that the process of managing the project scope takes into account the planning, definition of the project scope, creation of the structure of project work, confirmation of the scope and management of the project scope. Participants of these subprocesses are: customer, investor, and other project participants – external organizations (contractors of the project; project review committee; project manager and project team. It is revealed that the key element of planning the project scope is the formation of the structure of design work, the justification of the number of works, and the sequence of their implementation. It is recommended to use the following sequence of stages for creating the structure of project work

  12. Introduction to the Project

    DEFF Research Database (Denmark)

    Kuhn, Johan M.; Malchow-Møller, Nikolaj; Sørensen, Anders

    In this note a short introduction to the project “Employment Effects of Entrepreneurs” is presented. First, we describe the purpose of the project; second, we present the background; third, we briefly describe the three papers that constitute the output of the project, and fourth, we discuss two...... important qualifications for the understanding of the contributions and results established in the project....

  13. The virtual GULLIVER project

    NARCIS (Netherlands)

    Trappl, R.; Nijholt, Antinus; Stuk, M.; Zwiers, Jakob

    2002-01-01

    In this paper we discuss our virtual reality project Gulliver. This project is part of a more comprehensive project conceived by two artists, Matjaž Štuk and Alena Hudcovicová, called “Gulliver’s Museum of Living Art��?. Our part of the project involves a virtual reality version of Swift’s Gulliver

  14. Innovations in project activities

    Directory of Open Access Journals (Sweden)

    Serbskaya O.V.

    2016-11-01

    Full Text Available this article considers the ways of project management, models of project management: classical model and the model of flexible designing Agile, pays more attention to the process of project management using Agile model and to the problems of using the project management models in modern conditions.

  15. The 100 People Project

    Science.gov (United States)

    McLeod, Keri

    2007-01-01

    This article describes the 100 People Project and how the author integrates the project in her class. The 100 People Project is a nonprofit organization based in New York City. The organization poses the question: If there were only 100 people in the world, what would the world look like? Through the project, students were taught about ethics in…

  16. Earth System Science Project

    Science.gov (United States)

    Rutherford, Sandra; Coffman, Margaret

    2004-01-01

    For several decades, science teachers have used bottles for classroom projects designed to teach students about biology. Bottle projects do not have to just focus on biology, however. These projects can also be used to engage students in Earth science topics. This article describes the Earth System Science Project, which was adapted and developed…

  17. Projects as value constellations

    DEFF Research Database (Denmark)

    Laursen, Markus

    Creating value has been outlined as very central to projects applying the organizational perspective to projects. It has been suggested that value is created in value constellations or project networks, where actors work together to create value. However, research on the value creation process...... in value constellations is scarce, and through an exploratory study of two project networks in a cultural setting we investigate how value is created in value constellations. We outline how each project may be a distinct type of value constellation, one project creates value for the partners of the network...... as a consortium, and the project creates value primarily for others as a facilitator....

  18. Project stakeholder management

    CERN Document Server

    Eskerod, Pernille

    2013-01-01

    Carrying out a project as planned is not a guarantee for success. Projects may fail because project management does not take the requirements, wishes and concerns of stakeholders sufficiently into account. Projects can only be successful though contributions from stakeholders. And in the end, it is the stakeholders that evaluate whether they find that the project is a success. To manage stakeholders effectively, you need to know your stakeholders, their behaviours and attitudes towards the project. In Project Stakeholder Management, the authors give guidance on how to adopt an analytical and s

  19. Modern project-management

    CERN Multimedia

    CERN. Geneva

    2003-01-01

    This lecture will focus on the following issues: - The current state of the art in Project Management, especially the integration of Project Management with general management activities, and the integrated view of resources allocation. - Overview of the project life cycle, the phases and the deliverables - Necessity and limits of planning in a research environment - Organizational aspects of the projects the roles of the stakeholders - How to get the resources when they are needed - Risk Management in Projects - Earned value - How to keep a project on track (schedule and budget) - Management of the suppliers - Closing of the project

  20. Introduction to the Project

    DEFF Research Database (Denmark)

    Kuhn, Johan M.; Malchow-Møller, Nikolaj; Sørensen, Anders

    In this note a short introduction to the project “Employment Effects of Entrepreneurs” is presented. First, we describe the purpose of the project; second, we present the background; third, we briefly describe the three papers that constitute the output of the project, and fourth, we discuss two ...... important qualifications for the understanding of the contributions and results established in the project.......In this note a short introduction to the project “Employment Effects of Entrepreneurs” is presented. First, we describe the purpose of the project; second, we present the background; third, we briefly describe the three papers that constitute the output of the project, and fourth, we discuss two...

  1. Choice of large projects

    Energy Technology Data Exchange (ETDEWEB)

    Harris, R

    1978-08-01

    Conventional cost/benefit or project analysis has generally not taken into account circumstances in which the project under consideration is large enough that its introduction to the economy would have significant general equilibrium effects. In this paper, rules are examined that would indicate whether such large projects should be accepted or rejected. The rules utilize information yielded by before-project and after-project equilibrium prices and production data. Rules are developed for the undistorted ''first-best'' case, the case in which the fixed costs of the project are covered by distortionary taxation, and for the case of projects producing public goods. 34 references.

  2. Project Half Double

    DEFF Research Database (Denmark)

    Svejvig, Per; Gerstrøm, Anna; Frederiksen, Signe Hedeboe

    The Half Double mission: Project Half Double has a clear mission. We want to succeed in finding a project methodology that can increase the success rate of our projects while increasing the development speed of new products and services. We are convinced that by doing so we can strengthen...... the competitiveness of Denmark and play an important role in the battle for jobs and future welfare. The overall goal is to deliver “Projects in half the time with double the impact” where projects in half the time should be understood as half the time to impact (benefit realization, effect is achieved......) and not as half the time for project execution. The Half Double project journey: It all began in May 2013 when we asked ourselves: How do we create a new and radical project paradigm that can create successful projects? Today we are a movement of hundreds of passionate project people, and it grows larger...

  3. Project Finance: Basic Components

    OpenAIRE

    Alfieri Li Ojeda, Jaime

    2015-01-01

    The natural speed of the contemporary world demands large investment projects which require specialized financial techniques such as Project Finance, defined as a fund to finance investment projects of great magnitude. Every Project Finance involves a wide range of elements such as promoters, government, contractors andsuppliers, among others, that will ensure project success. La rapidez del mundo contemporáneo exige que los grandes proyectos de inversión requieran de técnicas financieras ...

  4. Project delivery system (PDS)

    CERN Document Server

    2001-01-01

    As business environments become increasingly competitive, companies seek more comprehensive solutions to the delivery of their projects. "Project Delivery System: Fourth Edition" describes the process-driven project delivery systems which incorporates the best practices from Total Quality and is aligned with the Project Management Institute and ISO Quality Standards is the means by which projects are consistently and efficiently planned, executed and completed to the satisfaction of clients and customers.

  5. IT Project Management Metrics

    Directory of Open Access Journals (Sweden)

    2007-01-01

    Full Text Available Many software and IT projects fail in completing theirs objectives because different causes of which the management of the projects has a high weight. In order to have successfully projects, lessons learned have to be used, historical data to be collected and metrics and indicators have to be computed and used to compare them with past projects and avoid failure to happen. This paper presents some metrics that can be used for the IT project management.

  6. Methodologies of Project Management

    Directory of Open Access Journals (Sweden)

    Wojciech Macek

    2011-07-01

    Full Text Available This paper presents comparison of three most popular project management standardsbelonging to a wider group of models (for example, PMBOK, Prince 2, CMMI, ISO 10006,BS 6079, IPMA Competence Baseline, European Commission Project Cycle ManagementGuidelines. The author discusses methods of project management according to PMBoK,Prince 2 and ISO 10006, some chosen criteria and fields of knowledge, such as generalregulations of standards, project range management, resources management, and processesconnected with risk, systems of project quality management.

  7. Project Half Double

    DEFF Research Database (Denmark)

    Svejvig, Per; Ehlers, Michael; Adland, Karoline Thorp

    activities carried out within the framework of the projects. The formal part of Project Half Double was initiated in June 2015. We started out by developing, refining and testing the Half Double methodology on seven pilot projects in the first phase of the project, which will end June 2016. The current......Project Half Double has a clear mission to succeed in finding a project methodology that can increase the success rate of our projects while increasing the speed at which we generate new ideas and develop new products and services. Chaos and complexity should be seen as a basic condition...... and as an opportunity rather than a threat and a risk. We are convinced that by doing so, we can strengthen Denmark’s competitiveness and play an important role in the battle for jobs and future welfare. The overall goal is to deliver “projects in half the time with double the impact”, where projects in half the time...

  8. Project management case studies

    CERN Document Server

    Kerzner, Harold R

    2013-01-01

    A new edition of the most popular book of project management case studies, expanded to include more than 100 cases plus a ""super case"" on the Iridium Project Case studies are an important part of project management education and training. This Fourth Edition of Harold Kerzner''s Project Management Case Studies features a number of new cases covering value measurement in project management. Also included is the well-received ""super case,"" which covers all aspects of project management and may be used as a capstone for a course. This new edition:Contains 100-plus case studies drawn from re

  9. The USE Project

    DEFF Research Database (Denmark)

    Frøkjær, E.; Hornbæk, K.; Høegh, Rune Thaarup

    2006-01-01

    This paper provides experience from activities in the USE project. The USE project is a research project that aims at bridging the gap between usability evaluation and user interface design. It is conducted from 2005 to 2008 in collaboration between researchers from Aalborg University and Copenha......This paper provides experience from activities in the USE project. The USE project is a research project that aims at bridging the gap between usability evaluation and user interface design. It is conducted from 2005 to 2008 in collaboration between researchers from Aalborg University...... and Copenhagen University, and developers and managers working in software development organizations....

  10. IT Project Selection

    DEFF Research Database (Denmark)

    Pedersen, Keld

    2016-01-01

    for initiation. Most of the research on project selection is normative, suggesting new methods, but available empirical studies indicate that many methods are seldom used in practice. This paper addresses the issue by providing increased understanding of IT project selection practice, thereby facilitating...... the development of methods that better fit current practice. The study is based on naturalistic decision-making theory and interviews with experienced project portfolio managers who, when selecting projects, primarily rely on political skills, experience and personal networks rather than on formal IT project......-selection methods, and these findings point to new areas for developing new methodological support for IT project selection....

  11. One project's waste is another project's resource

    International Nuclear Information System (INIS)

    Short, J.

    1997-01-01

    The author describes the efforts being made toward pollution prevention within the DOE complex, as a way to reduce overall project costs, in addition to decreasing the amount of waste to be handled. Pollution prevention is a concept which is trying to be ingrained into project planning. Part of the program involves the concept that ultimately the responsibility for waste comes back to the generator. Parts of the program involve efforts to reuse materials and equipment on new projects, to recycle wastes to generate offsetting revenue, and to increase awareness, accountability and incentives so as to stimulate action on this plan. Summaries of examples are presented in tables

  12. Integrated project support environments the ASPECT project

    CERN Document Server

    Brown, Alan W

    1991-01-01

    A major part of software engineering developments involve the use of computing tools which facilitate the management, maintenance, security, and building of long-scale software engineer projects. Consequently, there have been a proliferation of CASE tools and IPSES. This book looks at IPSES in general and the ASPECT project in particular, providing design and implementation details, as well as locating ASPECT in IPSE developments.Survey of integrated project support environments for more efficient software engineering**Description of a large scale IPSE--ASPECT**Evaluation of formal methods in

  13. MANAGING MULTICULTURAL PROJECT TEAMS

    Directory of Open Access Journals (Sweden)

    Cezar SCARLAT

    2014-06-01

    Full Text Available The article is based on literature review and authors’ own recent experience in managing multicultural project teams, in international environment. This comparative study considers two groups of projects: technical assistance (TA projects versus information technology (IT projects. The aim is to explore the size and structure of the project teams – according to the team formation and its lifecycle, and to identify some distinctive attributes of the project teams – both similarities and differences between the above mentioned types of projects. Distinct focus of the research is on the multiculturalism of the project teams: how the cultural background of the team members influences the team performance and team management. Besides the results of the study are the managerial implications: how the team managers could soften the cultural clash, and avoid inter-cultural misunderstandings and even conflicts – in order to get a better performance. Some practical examples are provided as well.

  14. Construction project management handbook.

    Science.gov (United States)

    2012-03-01

    The purpose of the FTA Construction Project Management Handbook is to provide guidelines for use by public transit agencies (Agen-cies) undertaking substantial construction projects, either for the first time or with little prior experience with cons...

  15. BioProject

    Data.gov (United States)

    U.S. Department of Health & Human Services — The BioProject database provides an organizational framework to access information about research projects with links to data that have been or will be deposited...

  16. The Phebus FP project

    International Nuclear Information System (INIS)

    Delchambre, P.; Von der Hardt, P.

    1989-01-01

    This report summarizes the pre-project studies concerning the PHEBUS FP facility. After recalling the programme objectives, it describes the projected modifications to the PHEBUS reactor, outlines new installations and justifies the selected options

  17. Number projection method

    International Nuclear Information System (INIS)

    Kaneko, K.

    1987-01-01

    A relationship between the number projection and the shell model methods is investigated in the case of a single-j shell. We can find a one-to-one correspondence between the number projected and the shell model states

  18. Successful project management

    CERN Document Server

    Young, Trevor L

    2016-01-01

    Successful Project Management, 5th edition, is an essential guide for anyone who wants to improve the success rate of their projects. It will help managers to maintain a balance between the demands of the customer, the project, the team and the organization. Covering the more technical aspects of a project from start to completion it contains practised and tested techniques, covering project conception and start-up, how to manage stake holders, effective risk management, project planning and launch and execution. Also including a brand new glossary of key terms, it provides help with evaluating your project as well as practical checklists and templates to ensure success for any ambitious project manager. With over one million copies sold, the hugely popular Creating Success series covers a wide variety of topic, with the latest editions including new chapters such as Tough Conversations and Treating People Right. This indispensable business skills collection is suited to a variety of roles, from someone look...

  19. Unicycle Project Report

    OpenAIRE

    Thomson, S

    2010-01-01

    The Unicycle project implemented an institutional Open Educational Resource repository with a view to ensuring sustainability in approach by embedding OER as an Assessment, Learning and Teaching strategy. This is the final submitted report for the project.

  20. Collaborative Contracting in Projects

    NARCIS (Netherlands)

    Suprapto, M.

    2016-01-01

    Project practitioners have increasingly recognized the importance of collaborative relationships to ensure successful executions of projects. However, the ability to sustain and consistenly drive real collaborative attitudes and behavior for achieving the desired outcomes remains of enduring

  1. Project Tasks in Robotics

    DEFF Research Database (Denmark)

    Sørensen, Torben; Hansen, Poul Erik

    1998-01-01

    Description of the compulsary project tasks to be carried out as a part of DTU course 72238 Robotics......Description of the compulsary project tasks to be carried out as a part of DTU course 72238 Robotics...

  2. Venezuela's Bolivarian Schools Project.

    Science.gov (United States)

    Diaz, Maria Magnolia Santamaria

    2002-01-01

    Discusses efforts by the Venezuelan government to improve the nation's school infrastructure through the Bolivarian Schools Project administered by the Ministry of Education, Culture and Sport. The project set educational principles which are guiding current school building efforts. (EV)

  3. Project management process.

    Science.gov (United States)

    2007-03-01

    This course provides INDOT staff with foundational knowledge and skills in project management principles and methodologies. INDOTs project management processes provide the tools for interdisciplinary teams to efficiently and effectively deliver pr...

  4. The Alzheimer's Project

    Science.gov (United States)

    ... Navigation Bar Home Current Issue Past Issues The Alzheimer's Project Past Issues / Spring 2009 Table of Contents ... of this page please turn Javascript on. The Alzheimer's Project A 4-Part Documentary Series Starting May ...

  5. Capital Projects Application (CPA)

    Data.gov (United States)

    General Services Administration — Capital Projects application (CPA) provides users with the ability to maintain project related financial data for Budget Activity (BA) 51, 55, 64, 01, 02, 03, 04....

  6. Earned value project management

    CERN Document Server

    Fleming, Quentin W

    2010-01-01

    Organizations that follow the principles of good Earned Value Management (EVM) create an environment that allows teams to successfully operate and thrive ? even in the face of challenges that could negatively impact their projects. Earned Value Project Management (EVPM) is a methodology used to measure and communicate the real physical progress of a project taking into account the work completed, the time taken and the costs incurred to complete that work. As a result, EVPM allows more educated and effective management decision-making, which helps evaluate and control project risk by measuring project progress in monetary terms. In the first two editions of Earned Value Project Management, Quentin W. Fleming and Joel M. Koppelman provided guidance for project management practitioners already familiar with EVPM, was well as those who were new to the use of this technique. The third edition expanded the information available on of EVPM for medium and smaller projects while still being relevant for larger projec...

  7. IX Disposition Project - project management plan

    International Nuclear Information System (INIS)

    Choi, I.G.

    1994-01-01

    This report presents plans for resolving saving and disposal concerns for ion exchange modules, cartridge filters and columns. This plan also documents the project baselines for schedules, cost, and technical information

  8. Project Management Performance Drivers

    OpenAIRE

    Ra’ad, Mohammed A.; Najdawi, Mohammad K.

    2010-01-01

    The practice of project management has gained enormous importance over the past several years in various business industries. “In industries as diverse as pharmaceuticals, software, and aerospace, projects drive business” (Wheatley). This gain of importance can be attributed to the magnitude of the impact project performance results in terms of time, cost, and scope have over the project performing entity. “On the basis of data released by the Bureau of Economic Analysis, part of the US De...

  9. Managing clinical improvement projects.

    Science.gov (United States)

    Phillips, Joanna; Simmonds, Lorraine

    This paper, the second of a three-part series looking at change management tools, provides a practical guide on how to use common project management principles in practice. Much of the literature on project management focuses on the business arena, with little reference to clinical settings. Identifying this literature and understanding its relevance to managing projects in healthcare can be difficult. This article provides a practical guide to identifying the key principles of good project management and applying these in health settings.

  10. The Dwarf Project: Vidojevica

    Science.gov (United States)

    Vince, O.

    2013-05-01

    The DWARF project is an important international project for observing eclipsing binary stars and searching for third companion which orbit around both stars. Recently, a group of researchers at the Astronomical Observatory of Belgrade joined this project using the 60 cm telescope at the Astronomical Station Vidojevica for observations. All the equipment and the human potential involved with this project from Serbia will be described in this paper.

  11. Project Management Techniques

    OpenAIRE

    Mihalache Anita; Salagean Liana

    2010-01-01

    Project management is a technique that can aid in the planning, scheduling, and monitoring of complex projects characterized by numerous, non repetitive jobs called activities. Examples of projects that would use project management include: - developing a mass rapid – transit system for a metropolitan area; - organizing the relocation of a corporate headquarters; - planning the production of a concert, film, or play; - developing and marketing a new automobile; - constructing a high – rise of...

  12. Project evaluation: main characteristics

    OpenAIRE

    Moutinho, Nuno

    2010-01-01

    — The evaluation process of real investment projects must consider not only the traditional financial approach, but also non-financial aspects. Non financial analysis can provide additional relevant information about projects. We investigate financial and non-financial areas most relevant in project appraisal. We present main critical success factors and areas of analysis that lead to the perception of project success. Finally, companies are segmented to verify its financial and non-financial...

  13. Project mechanisms challenges

    International Nuclear Information System (INIS)

    Perthuis, Ch. de

    2005-06-01

    The project mechanism complete the quotas systems concerning the carbon dioxide emissions market. The author explains and discusses these mechanisms and provides a panorama of the existing and developing projects. More specially she brings information on the mechanism of clean developments and renewable energies, the coordinated mechanisms, the agricultural projects, the financing of the projects and the exchange systeme of the New south Wales. (A.L.B.)

  14. ORGANIZATIONAL PROJECT MANAGEMENT MATURITY

    Directory of Open Access Journals (Sweden)

    Yana Derenskaya

    2017-11-01

    Full Text Available The present article is aimed at developing a set of recommendations for achieving a higher level of organizational project maturity at a given enterprise. Methodology. For the purposes of the current research, the available information sources on the components of project management system are analysed; the essence of “organizational maturity” and the existing models of organizational maturity are studied. The method of systemic and structural analysis, as well as the method of logical generalization, are employed in order to study the existing models of organizational maturity, to describe levels of organizational maturity, and finally to develop a set of methodological recommendations for achieving a higher level of organizational project maturity at a given enterprise. The results of the research showed that the core elements of project management system are methodological, organizational, programtechnical, and motivational components. Project management encompasses a wide range of issues connected with organizational structure, project team, communication management, project participants, etc. However, the fundamental basis for developing project management concept within a given enterprise starts with defining its level of organizational maturity. The present paper describes various models of organizational maturity (staged, continuous, petal-shaped and their common types (H. Кеrzner Organizational Maturity Model, Berkeley PM Maturity Model, Organizational Project Management Maturity Model, Portfolio, Program & Project Management Maturity Model. The analysis of available theoretic works showed that the notion “organizational project maturity” refers to the capability of an enterprise to select projects and manage them with the intention of achieving its strategic goals in the most effective way. Importantly, the level of maturity can be improved by means of formalizing the acquired knowledge, regulating project-related activities

  15. Pilot Project: analysis, development and projection

    OpenAIRE

    Tapia Abril, Verónica Emilia; Chérrez Rodas, Karina; García Pesántez, Gabriela Rosana; Maldonado Marchán, María Elisa; Bustamante Montesdeoca, José Luis

    2014-01-01

    Since the introduction of ICT in architecture and teaching, pedagogies of education have faced their learning paradigms change. Institutes of higher education have folded to this motion and have undergone a process of change by implementing multimedia elements in their subjects. Through the pilot project educational videos that aim to meet the highest standards of educational videos described by Van Dam have been developed. The project expects to generate educational videos for different depa...

  16. Building Project Competence

    DEFF Research Database (Denmark)

    Pemsel, Sofia; Wiewiora, Anna

    This research investigates the development of project competence, and particularly, three related dynamic capabilities (shifting, adapting, leveraging) that contribute to project competence development. In doing so, we make use of the emerging literature on knowledge governance and theorize how...... of dynamic capability building promoting project competence development....

  17. The Llama Project.

    Science.gov (United States)

    Ganzel, Candy; Stuglik, Jan

    2003-01-01

    At a suburban Indiana elementary school, the Project Approach serves as the basis of the curriculum in all Kindergarten classrooms. The four classes of 5- and 6-year-old children at this school chose to study llamas. This article discusses how the project evolved, describes the three phases of the project, and provides teachers' reflections on the…

  18. Nuclear safety projects 1995

    International Nuclear Information System (INIS)

    Carl-Erik Christoffersen

    1996-01-01

    Action plans for the prevention of contamination in the Arctic regions is concretized in a number of international projects. The Norwegian Radiation Protection Authority is responsible for the follow-up of 13 projects. The report describes the development of these projects in 1995

  19. Projection: A Bibliography.

    Science.gov (United States)

    Pedrini, D. T.; Pedrini, Bonnie C.

    Sigmund Freud and his associates did much clinical work with the dynamic of projection, especially with regard to paranoid symptoms and syndromes. Much experimental work has also been done with projection. Sears evaluated the results of some of those studies. Murstein and Pryer sub-classified projection and reviewed typical studies. The…

  20. Mayan Forest Road Projects

    DEFF Research Database (Denmark)

    Conde, Dalia Amor

    2008-01-01

    Road-building projects in the Mayan Biosphere Reserve to connect Mexico and Guatemala were subjected to a cost-benefit evaluation. Up to an estimated 311,000 hectares of jaguar habitat were found to be at risk of deforestation due to these projects. Some of the projects were shown to have negativ...... of continued conservation rather than road development....

  1. Projection Models 2010

    DEFF Research Database (Denmark)

    Illerup, J. B.; Birr-Pedersen, K.; Mikkelsen, M. H

    Models for projection of SO2-, NOx-, NMVOC- and NH3-emissions to the atmosphere have been developed and the Danish emissions have been projected until 2010 from a basis scenario including all implemented and planned measures. The projections of the four pollutants indicate that it may be difficult...

  2. Project Communications Management

    OpenAIRE

    José C. Santiago-Guevara; Mauricio Rojas-Contreras; Luis A. Esteban-Villamizar

    2013-01-01

    This article presents a review in relation to the object of study: Communications Management as an important factor in the management of projects. The review includes the most relevant and most renowned authors in the field of project management, focusing on telecommunications projects, which lets you define a communications management model.

  3. Designing Project Management

    NARCIS (Netherlands)

    Heintz, John Linke; Lousberg, L.; Wamelink, J.W.F.; Saari, A.; Huovinen, P.

    2016-01-01

    In this paper we introduce the concept of Designing Project Management. On the basis of our earlier work, we suggest that there is still a gap between what is known from recent project management literature and what project managers can structurally help in the effectiveness of their work. Assuming

  4. Humane Education Projects Handbook.

    Science.gov (United States)

    Junior League of Ogden, UT.

    This handbook was developed to promote interest in humane education and to encourage the adoption of humane education projects. Although specifically designed to assist Junior Leagues in developing such projects, the content should prove valuable to animal welfare organizations, zoos, aquariums, nature centers, and other project-oriented groups…

  5. MRS project management

    International Nuclear Information System (INIS)

    Doman, J.W.; Vlahakis, J.

    1992-01-01

    Management of projects under the control of the Office of Civilian Radioactive Waste Management within the Department of Energy is subject to overview by a variety of internal and external entities. This paper reports that effective project management often requires balancing of conflicting directions and conflicting agendas of the different entities in order to proceed with implementation of the Monitored Retrievable Storage project

  6. Risks management in project planning

    OpenAIRE

    Stankevičiūtė, Roberta

    2017-01-01

    Project management consists of two very important aspects – managing the right project and managing the project right. To know that you are managing the right project you need to ensure that your project is based on an actual requirement and that your project goal is relevant and beneficial. And professional project planning assists in managing project the right way. The project planning process is very time consuming and is one of the most important parts of the project management process. T...

  7. Project report - an overview of the project and experiences with project management

    DEFF Research Database (Denmark)

    Jørgensen, Michael Søgaard; Mikkelsen, Bent Egberg

    1996-01-01

    A collection of the project planning and the experiences with project management from the Catering 2000 project.As appendieces articles etc. from journals, newspapers etc. about the project.......A collection of the project planning and the experiences with project management from the Catering 2000 project.As appendieces articles etc. from journals, newspapers etc. about the project....

  8. Underestimation of Project Costs

    Science.gov (United States)

    Jones, Harry W.

    2015-01-01

    Large projects almost always exceed their budgets. Estimating cost is difficult and estimated costs are usually too low. Three different reasons are suggested: bad luck, overoptimism, and deliberate underestimation. Project management can usually point to project difficulty and complexity, technical uncertainty, stakeholder conflicts, scope changes, unforeseen events, and other not really unpredictable bad luck. Project planning is usually over-optimistic, so the likelihood and impact of bad luck is systematically underestimated. Project plans reflect optimism and hope for success in a supposedly unique new effort rather than rational expectations based on historical data. Past project problems are claimed to be irrelevant because "This time it's different." Some bad luck is inevitable and reasonable optimism is understandable, but deliberate deception must be condemned. In a competitive environment, project planners and advocates often deliberately underestimate costs to help gain project approval and funding. Project benefits, cost savings, and probability of success are exaggerated and key risks ignored. Project advocates have incentives to distort information and conceal difficulties from project approvers. One naively suggested cure is more openness, honesty, and group adherence to shared overall goals. A more realistic alternative is threatening overrun projects with cancellation. Neither approach seems to solve the problem. A better method to avoid the delusions of over-optimism and the deceptions of biased advocacy is to base the project cost estimate on the actual costs of a large group of similar projects. Over optimism and deception can continue beyond the planning phase and into project execution. Hard milestones based on verified tests and demonstrations can provide a reality check.

  9. Fundamentals of Project Management

    CERN Document Server

    Heagney, Joseph

    2011-01-01

    With sales of more than 160,000 copies, Fundamentals of Project Management has helped generations of project managers navigate the ins and outs of every aspect of this complex discipline. Using a simple step-by-step approach, the book is the perfect introduction to project management tools, techniques, and concepts. Readers will learn how to: ò Develop a mission statement, vision, goals, and objectives ò Plan the project ò Create the work breakdown structure ò Produce a workable schedule ò Understand earned value analysis ò Manage a project team ò Control and evaluate progress at every stage.

  10. Visualizations as Projection Devices

    DEFF Research Database (Denmark)

    Harty, Chris; Holm Jacobsen, Peter; Tryggestad, Kjell

    The aim of this paper is to inquire into the role of project visualizations in shaping healthcare spaces and practices. The study draws upon an ethnographic field study from a large on-going hospital construction project in Denmark, and focuses on the early phases of on-boarding the design team...... into the project organization. During the on-boarding visualizations multiplies in form, content and purpose, ranging from paper and digitally based projections of clinical work spaces and practices for the future hospital building in use, to paper and digitally based projections of the cost budget and time...

  11. Managing Projects with KPRO

    Science.gov (United States)

    Braden, Barry M.

    2004-01-01

    How does a Project Management Office provide: Consistent, familiar, easily used scheduling tools to Project Managers and project team members? Provide a complete list of organization resources available for use on the project? Facilitate resource tracking and visibility? Provide the myriad reports that the organization requires? Facilitate consistent budget planning and cost performance information? Provide all of this to the entire organization? Provide for the unique requirement of the organization? and get people to use it? Answer: Implementation of the Kennedy space Center Projects and Resources Online (KPRO), a modified COTS solution.

  12. Project Decision Chain

    DEFF Research Database (Denmark)

    Rolstadås, Asbjørn; Pinto, Jeffrey K.; Falster, Peter

    2015-01-01

    To add value to project performance and help obtain project success, a new framework for decision making in projects is defined. It introduces the project decision chain inspired by the supply chain thinking in the manufacturing sector and uses three types of decisions: authorization, selection......, and plan decision. A primitive decision element is defined where all the three decision types can be accommodated. Each task in the primitive element can in itself contain subtasks that in turn will comprise new primitive elements. The primitive elements are nested together in a project decision chain....

  13. Scheduling for decommissioning projects

    International Nuclear Information System (INIS)

    Podmajersky, O.E.

    1987-01-01

    This paper describes the Project Scheduling system being employed by the Decommissioning Operations Contractor at the Shippingport Station Decommissioning Project (SSDP). Results from the planning system show that the project continues to achieve its cost and schedule goals. An integrated cost and schedule control system (C/SCS) which uses the concept of earned value for measurement of performance was instituted in accordance with DOE orders. The schedule and cost variances generated by the C/SCS system are used to confirm management's assessment of project status. This paper describes the types of schedules and tools used on the SSDP project to plan and monitor the work, and identifies factors that are unique to a decommissioning project that make scheduling critical to the achievement of the project's goals. 1 fig

  14. Managing Distributed Software Projects

    DEFF Research Database (Denmark)

    Persson, John Stouby

    Increasingly, software projects are becoming geographically distributed, with limited face-toface interaction between participants. These projects face particular challenges that need careful managerial attention. This PhD study reports on how we can understand and support the management...... of distributed software projects, based on a literature study and a case study. The main emphasis of the literature study was on how to support the management of distributed software projects, but also contributed to an understanding of these projects. The main emphasis of the case study was on how to understand...... the management of distributed software projects, but also contributed to supporting the management of these projects. The literature study integrates what we know about risks and risk-resolution techniques, into a framework for managing risks in distributed contexts. This framework was developed iteratively...

  15. ASEAN projects reviewed.

    Science.gov (United States)

    1980-01-01

    The ASEAN Population Expert Group met in Manila and was followed by a meeting of the ASEAN heads of population programs, during the period November 5-10, 1979. Heads of population programs from Indonesia, Malaysia, Singapore, Thailand, and the Philippines attended. The meetings were held to review progress-to-date on phase 1 projects and to consider the development of an expanded population program. 5 projects funded by UNFPA are reviewed in tabular form with the project, the sponsoring country, date of implementation, data analysis, and date of completion. Suggestions were made for improving and extending these projects and it was also suggested that all projects being developed and proposed should include a section on use of research. 7 new projects were proposed as phase 2 projects. The 1st, sponsored by Malaysia, deals with women in development; project 2, lead by Thailand, will investigate population movement and its effect on development; project 3, led by the Philippines, will develop and strengthen national population information systems and networks in ASEAN countries; project 4, led by Indonesia, is directed towards institutional development and exchanges of personnel; project 5, led by the Philippines, will examine population and development dynamics and the man/resources balance; project 6, led by Thailand, will develop ASEAN social indicators; and project 7, led by Indonesia and Malaysia, will make a comprehensive analysis of existing medical/health care and family planning systems. It was recommended that an executive director of the proposed ASEAN population coordination unit should be appointed to expedite the recommendations of the meeting related to preparation and submission of phase 2 project proposals.

  16. Perspectives on projects, project success and team work

    OpenAIRE

    Thompson, Karen

    2015-01-01

    This paper brings together perspectives on projects, project success and team work as a background to two graphical tools for considering project success and individual capabilities for working in a project team.

  17. Quality Assurance Project Plan for Citizen Science Projects

    Science.gov (United States)

    The Quality Assurance Project Plan is necessary for every project that collects or uses environmental data. It documents the project planning process and serves as a blueprint for how your project will run.

  18. Project Management and the Project Manager: A Strategy for ...

    African Journals Online (AJOL)

    International Journal of Development and Management Review ... collapse, project failure, project abandonment, project cost and time overruns, etc. ... component parts that constitute project management in the building construction industry.

  19. Theory of Abelian projection

    International Nuclear Information System (INIS)

    Ogilvie, M.C.

    1999-01-01

    Analytic methods for Abelian projection are developed. A number of results are obtained related to string tension measurements. It is proven that even without gauge fixing, Abelian projection yields string tensions of the underlying non-Abelian theory. Strong arguments are given for similar results in the case where gauge fixing is employed. The methods used emphasize that the projected theory is derived from the underlying non-Abelian theory rather than vice versa. In general, the choice of subgroup used for projection is not very important, and need not be Abelian. While gauge fixing is shown to be in principle unnecessary for the success of Abelian projection, it is computationally advantageous for the same reasons that improved operators, e.g., the use of fat links, are advantageous in Wilson loop measurements. Two other issues, Casimir scaling and the conflict between projection and critical universality, are also discussed. copyright 1999 The American Physical Society

  20. Battleground Energy Recovery Project

    Energy Technology Data Exchange (ETDEWEB)

    Bullock, Daniel [USDOE Gulf Coast Clean Energy Application Center, Woodlands, TX (United States)

    2011-12-31

    In October 2009, the project partners began a 36-month effort to develop an innovative, commercial-scale demonstration project incorporating state-of-the-art waste heat recovery technology at Clean Harbors, Inc., a large hazardous waste incinerator site located in Deer Park, Texas. With financial support provided by the U.S. Department of Energy, the Battleground Energy Recovery Project was launched to advance waste heat recovery solutions into the hazardous waste incineration market, an area that has seen little adoption of heat recovery in the United States. The goal of the project was to accelerate the use of energy-efficient, waste heat recovery technology as an alternative means to produce steam for industrial processes. The project had three main engineering and business objectives: Prove Feasibility of Waste Heat Recovery Technology at a Hazardous Waste Incinerator Complex; Provide Low-cost Steam to a Major Polypropylene Plant Using Waste Heat; and Create a Showcase Waste Heat Recovery Demonstration Project.

  1. J-PARC project

    International Nuclear Information System (INIS)

    Nagamiya, Shoji

    2004-01-01

    From Japanese fiscal year JFY01, which started on April 1, 2001, a new accelerator project to provide high-intensity proton beams proceeded into its construction phase. This project, which is now called the Japan Proton Accelerator Research Complex (J-PARC) project, is conducted under a cooperation of two institutions, KEK and Japan Atomic Energy Research Institution. We set a goal to achieve 1 MW proton beams at 3 GeV and 0.75 MW beams at 50 GeV. The project will be completed within six years, with the anticipated first beams in the spring of 2007. In this article I will describe (a) the project itself, (b) sciences to be pursued at this new accelerator complex and (c) the present status and future plans of the project

  2. Photovoltaic demonstration projects

    Energy Technology Data Exchange (ETDEWEB)

    Kaut, W [Commission of the European Communities, Brussels (Belgium); Gillett, W B; Hacker, R J [Halcrow Gilbert Associates Ltd., Swindon (GB)

    1992-12-31

    This publication, comprising the proceedings of the fifth contractor`s meeting organized by the Commission of the European Communities, Directorate-General for Energy, provides an overview of the photovoltaic demonstration projects which have been supported in the framework of the energy demonstration programme since 1983. It includes reports by each of the contractors who submitted proposals in 1987 and 1988, describing progress within their projects. Projects accepted from earlier calls for proposals and not yet completed were reviewed by a rapporteur and are discussed in the summary section. The results of the performance monitoring of all projects and the lessons drawn from the practical experience of the projects are also presented in the summaries and conclusions. Contractors whose projects were submitted in 1989 were also present at the meeting and contributed to the reported discussions. This proceeding is divided into four sessions (General, Housing, technical presentations, other applications) and 24 papers are offered.

  3. AAEC nuclear power projections

    International Nuclear Information System (INIS)

    Khoe, G.; Fredsall, J.; Scurr, I.; Plotnikoff, W.

    1981-01-01

    The nuclear power capacity projections developed in the May-June period of 1981 by the AAEC are presented. There have been downward revisions for nearly all countries with centrally planned economies. Projections for the year 2000 for the Western World have decreased in aggregate by 4.7% (27Gw) compared to those of 1980. However, this reduction is less than the previous estimate reduction and there appears to have been a stabilisation in the projection

  4. What is project finance?

    OpenAIRE

    João M. Pinto

    2017-01-01

    Project finance is the process of financing a specific economic unit that the sponsors create, in which creditors share much of the venture’s business risk and funding is obtained strictly for the project itself. Project finance creates value by reducing the costs of funding, maintaining the sponsors financial flexibility, increasing the leverage ratios, avoiding contamination risk, reducing corporate taxes, improving risk management, and reducing the costs associated with market ...

  5. Computer Assets Recovery Project

    Science.gov (United States)

    CortesPena, Aida Yoguely

    2010-01-01

    This document reports on the project that was performed during the internship of the author. The project involved locating and recovering machines in various locations that Boeing has no need for, and therefore requires that they be transferred to another user or transferred to a non-profit organization. Other projects that the author performed was an inventory of toner and printers, loading new computers and connecting them to the network.

  6. Operational Waste Volume Projection

    Energy Technology Data Exchange (ETDEWEB)

    STRODE, J.N.

    2000-08-28

    Waste receipts to the double-shell tank system are analyzed and wastes through the year 2015 are projected based on generation trends of the past 12 months. A computer simulation of site operations is performed, which results in projections of tank fill schedules, tank transfers, evaporator operations, tank retrieval, and aging waste tank usage. This projection incorporates current budget planning and the clean-up schedule of the Tri-Party Agreement. Assumptions were current as of June. 2000.

  7. Organization of project management

    International Nuclear Information System (INIS)

    Schmidt, R.

    1975-01-01

    When speaking about interfaces within a project and their management, one has to understand and define what an interface is. In general, each component facing another one and each person working on a project with another person represents an interface. Therefore a project will consist practically in its entirety of interfaces with components and people sandwiched between them. This paper is limited to the most important interfaces with a focus on the problems occuring at them and their resolution. (orig.) [de

  8. Operational waste volume projection

    International Nuclear Information System (INIS)

    Koreski, G.M.; Strode, J.N.

    1995-06-01

    Waste receipts to the double-shell tank system are analyzed and wastes through the year 2015 are projected based on generation trends of the past 12 months. A computer simulation of site operations is performed, which results in projections of tank fill schedules, tank transfers, evaporator operations, tank retrieval, and aging waste tank usage. This projection incorporates current budget planning and the clean-up schedule of the tri-party agreement. Assumptions are current as of June 1995

  9. PPP projects in transport

    DEFF Research Database (Denmark)

    Petersen, Ole Helby; Carpintero, Samuel

    2014-01-01

    Public–private partnerships (PPPs) have been extensively used in Spain for the procurement of light rail systems. This paper analyses five projects that have been in operation for more than five years. The authors examine the reasoning behind the selection of the PPP projects, risk......-sharing mechanisms, competition among private providers, and overall cost-effectiveness. The paper demonstrates a need for more rigorous assessments of the merits of PPP projects before they are initiated....

  10. Operational Waste Volume Projection

    International Nuclear Information System (INIS)

    STRODE, J.N.

    2000-01-01

    Waste receipts to the double-shell tank system are analyzed and wastes through the year 2015 are projected based on generation trends of the past 12 months. A computer simulation of site operations is performed, which results in projections of tank fill schedules, tank transfers, evaporator operations, tank retrieval, and aging waste tank usage. This projection incorporates current budget planning and the clean-up schedule of the Tri-Party Agreement. Assumptions were current as of June. 2000

  11. Existence of Projective Planes

    OpenAIRE

    Perrott, Xander

    2016-01-01

    This report gives an overview of the history of finite projective planes and their properties before going on to outline the proof that no projective plane of order 10 exists. The report also investigates the search carried out by MacWilliams, Sloane and Thompson in 1970 [12] and confirms their result by providing independent verification that there is no vector of weight 15 in the code generated by the projective plane of order 10.

  12. Microwave solidification project overview

    Energy Technology Data Exchange (ETDEWEB)

    Sprenger, G.

    1993-01-01

    The Rocky Flats Plant Microwave Solidification Project has application potential to the Mixed Waste Treatment Project and the The Mixed Waste Integrated Program. The technical areas being addressed include (1) waste destruction and stabilization; (2) final waste form; and (3) front-end waste handling and feed preparation. This document covers need for such a program; technology description; significance; regulatory requirements; and accomplishments to date. A list of significant reports published under this project is included.

  13. Oskarshamn 1-project FENIX

    International Nuclear Information System (INIS)

    Sjoeqvist, N.G.

    1994-01-01

    This paper summarizes the actions to be taken in a large re-start and backfitting project such as the Fenix project. It describes the organization, planning and financial management, safety criteria and licensing procedures, safety concept report, health and safety. The results from the unique full system decontamination of the reactor pressure vessel is described. The project is still ongoing and therefore other results and lessons learnt are not reported. (author) 9 figs

  14. Microwave solidification project overview

    International Nuclear Information System (INIS)

    Sprenger, G.

    1993-01-01

    The Rocky Flats Plant Microwave Solidification Project has application potential to the Mixed Waste Treatment Project and the The Mixed Waste Integrated Program. The technical areas being addressed include (1) waste destruction and stabilization; (2) final waste form; and (3) front-end waste handling and feed preparation. This document covers need for such a program; technology description; significance; regulatory requirements; and accomplishments to date. A list of significant reports published under this project is included

  15. Embedded Linux projects using Yocto project cookbook

    CERN Document Server

    González, Alex

    2015-01-01

    If you are an embedded developer learning about embedded Linux with some experience with the Yocto project, this book is the ideal way to become proficient and broaden your knowledge with examples that are immediately applicable to your embedded developments. Experienced embedded Yocto developers will find new insight into working methodologies and ARM specific development competence.

  16. Project Risk Management

    Science.gov (United States)

    Jr., R. F. Miles

    1995-01-01

    Project risk management is primarily concerned with performance, reliability, cost, and schedule. Environmental risk management is primarily concerned with human health and ecological hazards and likelihoods. This paper discusses project risk management and compares it to environmental risk management, both with respect to goals and implementation. The approach of the Jet Propulsion Laboratory to risk management is presented as an example of a project risk management approach that is an extension to NASA NHB 7120.5: Management of Major System Programs and Projects.

  17. HERMES project management I

    CERN Multimedia

    CERN. Geneva

    2013-01-01

    A two-hours course on the HERMES Project Management Methodology to the attention of Project Leaders and Project Participants. The methodology is quickly presented; the focus is put on the roles and responsibilities and on the project initiation phase. The course is given in French with slides in English. On April 22nd 2013, a new version of the HERMES methodology was made public. For practical reasons, this course is still given based on the 2009 version of HERMES (a.k.a. HERMES 4).

  18. Scrum Project Management

    CERN Document Server

    Pries, Kim H

    2010-01-01

    Scrum, which was originally invented solely for software development, can now be applied to all types of projects. This book shows project managers how to implement Scrum by explaining the artifacts, rituals, and roles used. The text provides Scrum planning methods to control project scope and schedule as well as Scrum tracking methods to focus teams on improving throughput and streamlining communications. The authors show how to combine traditional project methods with Scrum and how to adapt the familiar work breakdown structure to create Scrum backlogs and sprints. They also demonstrate how

  19. Severe fuel damage projects

    International Nuclear Information System (INIS)

    Sdouz, G.

    1987-10-01

    After the descriptions of the generation of a Severe Fuel Damage Accident in a LWR the hypothetical course of such an accident is explained. Then the most significant projects are described. At each project the experimental facility, the most important results and the concluding models and codes are discussed. The selection of the projects is concentrated on the German Projekt Nukleare Sicherheit (PNS), tests performed at the Idaho National Engineering Laboratory (INEL) and smaller projects in France and Great Britain. 25 refs., 26 figs. (Author)

  20. Assessment of Students Projects

    DEFF Research Database (Denmark)

    Kofoed, Lise B.; Stachowicz, Marian S.

    2012-01-01

    The evaluation and assessment of engineering programmes is a big issue, and there exist many concepts and methods. This paper deals with the assessment methods which can be used when assessing the knowledge, skills and competences developed in projects using PBL (problem based and project organized...... learning) pedagogical approaches. The experience of assessing first year projects from the Medialogy education at Aalborg University and third year projects from the Electrical and Computer Engineering Department at University of Minnesota, Duluth are presented, and the different methods discussed....... The conclusion is that process as well as product has to be assessed in a way which evaluates all aspects of students’ learning outcomes....