Transport Studies in Alcator C-Mod ITB Plasmas

Science.gov (United States)

Fiore, C. L.; Bonoli, P. T.; Ernst, D.; Greenwald, M. J.; Ince-Cushman, A.; Lin, L.; Marmar, E. S.; Porkolab, M.; Rice, J. E.; Wukitch, S.; Rowan, W.; Bespamyatnov, I.; Phillips, P.

2008-11-01

Internal transport barriers occur in C-Mod plasmas that have off-axis ICRF heating and also in Ohmic H-mode plasmas. These ITBs are marked by highly peaked density and pressure profiles, as they rely on a reduction of particle and thermal flux in the barrier region which allows the neoclassical pinch to peak the central density without reducing the central temperature. Enhancement of several core diagnostics has resulted in increased understanding of C-Mod ITBs. Ion temperature profile measurements have been obtained using an innovative design for x-ray crystal spectrometry and clearly show a barrier forming in the ion temperature profile. The phase contrast imaging (PCI) provides limited localization of the ITB related fluctuations that increase in strength as the central density increases. Simulation of triggering conditions, integrated simulations with fluctuation measurements, parametric studies, and transport implications of fully ionized boron impurity profiles in the plasma are under study. A summary of these results will be presented.

Long Term Retention of Deuterium and Tritium in Alcator C-Mod

International Nuclear Information System (INIS)

FIORE, C.; LABOMBARD, B.; LIPSCHULTZ, B.; PITCHER, C.S.; SKINNER, C.H.; WAMPLER, WILLIAM R.

1999-01-01

We estimate the total in-vessel deuterium retention in Alcator C-Mod from a run campaign of about 1090 plasmas. The estimate is based on measurements of deuterium retained on 22 molybdenum tiles from the inner wall and divertor. The areal density of deuterium on the tiles was measured by nuclear reaction analysis. From these data, the in-vessel deuterium inventory is estimated to be about 0.1 gram, assuming the deuterium coverage is toroidally symmetric. Most of the retained deuterium is on the walls of the main plasma chamber, only about 2.5% of the deuterium is in the divertor. The D coverage is consistent with a layer saturated by implantation with ions and charge-exchange neutrals from the plasma. This contrasts with tokamaks with carbon plasma-facing components (PFC's) where long-term retention of tritium and deuterium is large and mainly in the divertor due to codeposition with carbon eroded by the plasma. The low deuterium retention in the C-Mod divertor is mainly due to the absence of carbon PFC's in C-Mod and the low erosion rate of Mo

The Escherichia coli modE gene: effect of modE mutations on molybdate dependent modA expression.

Science.gov (United States)

McNicholas, P M; Chiang, R C; Gunsalus, R P

1996-11-15

The Escherichia coli modABCD operon, which encodes a high-affinity molybdate uptake system, is transcriptionally regulated in response to molybdate availability by ModE. Here we describe a highly effective enrichment protocol, applicable to any gene with a repressor role, and establish its application in the isolation of transposon mutations in modE. In addition we show that disruption of the ModE C-terminus abolishes derepression in the absence of molybdate, implying this region of ModE controls the repressor activity. Finally, a mutational analysis of a proposed molybdate binding motif indicates that this motif does not function in regulating the repressor activity of ModE.

Correlation ECE diagnostic in Alcator C-Mod

International Nuclear Information System (INIS)

Sung, C.; Irby, J.; Leccacorvi, R.; Vieira, R.; Oi, C.; Rice, J.; Reinke, M.; Gao, C.; Ennever, P.; Porkolab, M.; Churchill, R.; Theiler, C.; Walk, J.; Hughes, J.; Hubbard, A.; Greenwald, M.

2015-01-01

Correlation ECE (CECE) is a diagnostic technique that allows measurement of small amplitude electron temperature, Te, fluctuations through standard cross-correlation analysis methods. In Alcator C-Mod, a new CECE diagnostic has been installed[Sung RSI 2012], and interesting phenomena have been observed in various plasma conditions. We find that local Te fluctuations near the edge (ρ ~ 0:8) decrease across the linearto- saturated ohmic confinement transition, with fluctuations decreasing with increasing plasma density [Sung NF 2013], which occurs simultaneously with rotation reversals [Rice NF 2011]. Te fluctuations are also reduced across core rotation reversals with an increase of plasma density in RF heated L-mode plasmas, which implies that the same physics related to the reduction of Te fluctuations may be applied to both ohmic and RF heated L-mode plasmas. In I-mode plasmas, we observe the reduction of core Te fluctuations, which indicates changes of turbulence occur not only in the pedestal region but also in the core across the L/I transition [White NF 2014]. The present CECE diagnostic system in C-Mod and these experimental results are described in this paper

Internal transport barriers on Alcator C-Mod

International Nuclear Information System (INIS)

Fiore, C.L.; Rice, J.E.; Bonoli, P.T.; Boivin, R.L.; Goetz, J.A.; Hubbard, A.E.; Hutchinson, I.H.; Granetz, R.S.; Greenwald, M.J.; Marmar, E.S.; Mossessian, D.; Porkolab, M.; Taylor, G.; Snipes, J.; Wolfe, S.M.; Wukitch, S.J.

2001-01-01

The formation of internal transport barriers (ITBs) has been observed in the core region of Alcator C-Mod [I. H. Hutchinson et al., Phys. Plasmas 1, 1511 (1994)] under a variety of conditions. The improvement in core confinement following pellet injection (pellet enhanced performance or PEP mode) has been well documented on Alcator C-Mod in the past. Recently three new ITB phenomena have been observed which require no externally applied particle or momentum input. Short lived ITBs form spontaneously following the high confinement to low confinement mode transition and are characterized by a large increase in the global neutron production (enhanced neutron or EN modes). Experiments with ion cyclotron range of frequencies power injection to the plasma off-axis on the high field side results in the central density rising abruptly and becoming peaked. The ITB formed at this time lasts for ten energy confinement times. The central toroidal rotation velocity decreases and changes sign as the density rises. Similar spontaneous ITBs have been observed in ohmically heated H-mode plasmas. All of these ITB events have strongly peaked density profiles with a minimum in the density scale length occurring near r/a=0.5 and have improved confinement parameters in the core region of the plasma

C-Mod Collaboration Informal Technical Progress Report

International Nuclear Information System (INIS)

Kenneth W. Gentle

2007-01-01

The aims of the collaboration have not changed. A specific list of tasks was agreed upon during the Fall of 2006 in preparation for the 2007 C-Mod campaign by Earl Marmar, Head of the Alcator Project, Kenneth Gentle, Principal Investigator, and William Rowan, Collaboration Coordinator with the facilitation of Adam Rosenberg (DOE grant monitor for the collaboration). The activities follow the list of tasks and are discussed in this progress report

Investigation of RF-enhanced plasma potentials on Alcator C-Mod

International Nuclear Information System (INIS)

Ochoukov, R.; Whyte, D.G.; Brunner, D.; Cziegler, I.; LaBombard, B.; Lipschultz, B.; Myra, J.; Terry, J.; Wukitch, S.

2013-01-01

Radio frequency (RF) sheath rectification is a leading mechanism suspected of causing anomalously high erosion of plasma facing materials in RF-heated plasmas on Alcator C-Mod. An extensive experimental survey of the plasma potential (Φ P ) in RF-heated discharges on C-Mod reveals that significant Φ P enhancement (>100 V) is found on outboard limiter surfaces, both mapped and not mapped to active RF antennas. Surfaces that magnetically map to active RF antennas show Φ P enhancement that is, in part, consistent with the recently proposed slow wave rectification mechanism. Surfaces that do not map to active RF antennas also experience significant Φ P enhancement, which strongly correlates with the local fast wave intensity. In this case, fast wave rectification is a leading candidate mechanism responsible for the observed enhancement

Migration of alcator C-Mod computer infrastructure to Linux

International Nuclear Information System (INIS)

Fredian, T.W.; Greenwald, M.; Stillerman, J.A.

2004-01-01

The Alcator C-Mod fusion experiment at MIT in Cambridge, Massachusetts has been operating for twelve years. The data handling for the experiment during most of this period was based on MDSplus running on a cluster of VAX and Alpha computers using the OpenVMS operating system. While the OpenVMS operating system provided a stable reliable platform, the support of the operating system and the software layered on the system has deteriorated in recent years. With the advent of extremely powerful low cost personal computers and the increasing popularity and robustness of the Linux operating system a decision was made to migrate the data handling systems for C-Mod to a collection of PC's running Linux. This paper will describe the new system configuration, the effort involved in the migration from OpenVMS, the results of the first run campaign under the new configuration and the impact the switch may have on the rest of the MDSplus community

Alcator C-Mod predictive modeling

International Nuclear Information System (INIS)

Pankin, Alexei; Bateman, Glenn; Kritz, Arnold; Greenwald, Martin; Snipes, Joseph; Fredian, Thomas

2001-01-01

Predictive simulations for the Alcator C-mod tokamak [I. Hutchinson et al., Phys. Plasmas 1, 1511 (1994)] are carried out using the BALDUR integrated modeling code [C. E. Singer et al., Comput. Phys. Commun. 49, 275 (1988)]. The results are obtained for temperature and density profiles using the Multi-Mode transport model [G. Bateman et al., Phys. Plasmas 5, 1793 (1998)] as well as the mixed-Bohm/gyro-Bohm transport model [M. Erba et al., Plasma Phys. Controlled Fusion 39, 261 (1997)]. The simulated discharges are characterized by very high plasma density in both low and high modes of confinement. The predicted profiles for each of the transport models match the experimental data about equally well in spite of the fact that the two models have different dimensionless scalings. Average relative rms deviations are less than 8% for the electron density profiles and 16% for the electron and ion temperature profiles

Real-time sensing and gas jet mitigation of VDEs on Alcator C-Mod

Science.gov (United States)

Granetz, R. S.; Wolfe, S. M.; Izzo, V. A.; Reinke, M. L.; Terry, J. L.; Hughes, J. W.; Zhurovich, K.; Whyte, D. G.; Bakhtiari, M.; Wurden, G.

2006-10-01

Experiments have been carried out in Alcator C-Mod to test the effectiveness of gas jet disruption mitigation of VDEs with real-time detection and triggering by the C-Mod digital plasma control system (DPCS). The DPCS continuously computes the error in the plasma vertical position from the magnetics diagnostics. When this error exceeds an adjustable preset value, the DPCS triggers the gas jet valve (with a negligible latency time). The high-pressure gas (argon) only takes a few milliseconds to enter the vacuum chamber and begin affecting the plasma, but this is comparable to the VDE timescale on C-Mod. Nevertheless, gas jet injection reduced the halo current, increased the radiated power fraction, and reduced the heating of the divertor compared to unmitigated disruptions, but not quite as well as in earlier mitigation experiments with vertically stable plasmas. Presumably a faster overall response time would be beneficial, and several ways to achieve this will also be discussed.

Experiments and Simulations of ITER-like Plasmas in Alcator C-Mod

International Nuclear Information System (INIS)

Wilson, R.; Kessel, C.E.; Wolfe, S.; Hutchinson, I.H.; Bonoli, P.; Fiore, C.; Hubbard, A.E.; Hughes, J.; Lin, Y.; Ma, Y.; Mikkelsen, D.; Reinke, M.; Scott, S.; Sips, A.C.C.; Wukitch, S.

2010-01-01

Alcator C-Mod is performing ITER-like experiments to benchmark and verify projections to 15 MA ELMy H-mode Inductive ITER discharges. The main focus has been on the transient ramp phases. The plasma current in C-Mod is 1.3 MA and toroidal field is 5.4 T. Both Ohmic and ion cyclotron (ICRF) heated discharges are examined. Plasma current rampup experiments have demonstrated that (ICRF and LH) heating in the rise phase can save voltseconds (V-s), as was predicted for ITER by simulations, but showed that the ICRF had no effect on the current profile versus Ohmic discharges. Rampdown experiments show an overcurrent in the Ohmic coil (OH) at the H to L transition, which can be mitigated by remaining in H-mode into the rampdown. Experiments have shown that when the EDA H-mode is preserved well into the rampdown phase, the density and temperature pedestal heights decrease during the plasma current rampdown. Simulations of the full C-Mod discharges have been done with the Tokamak Simulation Code (TSC) and the Coppi-Tang energy transport model is used with modified settings to provide the best fit to the experimental electron temperature profile. Other transport models have been examined also.

Investigation of RF-enhanced plasma potentials on Alcator C-Mod

Energy Technology Data Exchange (ETDEWEB)

Ochoukov, R., E-mail: ochoukov@psfc.mit.edu [PSFC MIT, NW17, 175 Albany Street, Cambridge, MA 02139 (United States); Whyte, D.G.; Brunner, D. [PSFC MIT, NW17, 175 Albany Street, Cambridge, MA 02139 (United States); Cziegler, I. [Center for Energy Research, UCSD, 9500 Gilman Drive, La Jolla, CA 92093 (United States); LaBombard, B.; Lipschultz, B. [PSFC MIT, NW17, 175 Albany Street, Cambridge, MA 02139 (United States); Myra, J. [Lodestar Research Corporation, 2400 Central Avenue P-5, Boulder, CO 80301 (United States); Terry, J.; Wukitch, S. [PSFC MIT, NW17, 175 Albany Street, Cambridge, MA 02139 (United States)

2013-07-15

Radio frequency (RF) sheath rectification is a leading mechanism suspected of causing anomalously high erosion of plasma facing materials in RF-heated plasmas on Alcator C-Mod. An extensive experimental survey of the plasma potential (Φ{sub P}) in RF-heated discharges on C-Mod reveals that significant Φ{sub P} enhancement (>100 V) is found on outboard limiter surfaces, both mapped and not mapped to active RF antennas. Surfaces that magnetically map to active RF antennas show Φ{sub P} enhancement that is, in part, consistent with the recently proposed slow wave rectification mechanism. Surfaces that do not map to active RF antennas also experience significant Φ{sub P} enhancement, which strongly correlates with the local fast wave intensity. In this case, fast wave rectification is a leading candidate mechanism responsible for the observed enhancement.

Testing Gyrokinetics on C-Mod and NSTX

International Nuclear Information System (INIS)

Redi, M.H.; Dorland, W.; Fiore, C.L.; Stutman, D.; Baumgaertel, J.A.; Davis, B.; Kaye, S.M.; McCune, D.C.; Menard, J.; Rewoldt, G.

2005-01-01

Quantitative benchmarks of computational physics codes against experiment are essential for the credible application of such codes. Fluctuation measurements can provide necessary critical tests of nonlinear gyrokinetic simulations, but such require extraordinary computational resources. Linear micro-stability calculations with the GS2 [1] gyrokinetic code have been carried out for tokamak and ST experiments which exhibit internal transport barriers (ITB) and good plasma confinement. Qualitative correlation is found for improved confinement before and during ITB plasmas on Alcator C-Mod [2] and NSTX [3], with weaker long wavelength micro-instabilities in the plasma core regions. Mixing length transport models are discussed. The NSTX L-mode is found to be near marginal stability for kinetic ballooning modes. Fully electromagnetic, linear, gyrokinetic calculations of the Alcator C-Mod ITB during off-axis rf heating, following four plasma species and including the complete electron response show ITG/TEM microturbulence is suppressed in the plasma core and in the barrier region before barrier formation, without recourse to the usual requirements of velocity shear or reversed magnetic shear [4-5]. No strongly growing long or short wavelength drift modes are found in the plasma core but strong ITG/TEM and ETG drift wave turbulence is found outside the barrier region. Linear microstability analysis is qualitatively consistent with the experimental transport analysis, showing low transport inside and high transport outside the ITB region before barrier formation, without consideration of ExB shear stabilization

Comparison of tungsten nano-tendrils grown in Alcator C-Mod and linear plasma devices

International Nuclear Information System (INIS)

Wright, G.M.; Brunner, D.; Baldwin, M.J.; Bystrov, K.; Doerner, R.P.; Labombard, B.; Lipschultz, B.; De Temmerman, G.; Terry, J.L.; Whyte, D.G.; Woller, K.B.

2013-01-01

Growth of tungsten nano-tendrils (“fuzz”) has been observed for the first time in the divertor region of a high-power density tokamak experiment. After 14 consecutive helium L-mode discharges in Alcator C-Mod, the tip of a tungsten Langmuir probe at the outer strike point was fully covered with a layer of nano-tendrils. The depth of the W fuzz layer (600 ± 150 nm) is consistent with an empirical growth formula from the PISCES experiment. Re-creating the C-Mod exposures as closely as possible in Pilot-PSI experiment can produce nearly-identical nano-tendril morphology and layer thickness at surface temperatures that agree with uncertainties with the C-Mod W probe temperature data. Helium concentrations in W fuzz layers are measured at 1–4 at.%, which is lower than expected for the observed sub-surface voids to be filled with several GPa of helium pressure. This possibly indicates that the void formation is not pressure driven

Numerical modelling of ICRF physics experiments in the Alcator C-mod tokamak

International Nuclear Information System (INIS)

Bonoli, P.T.; Boivin, R.L.; Brambilla, M.

2001-01-01

A full-wave spectral code (TORIC) has been used to simulate mode converted ion Bernstein wave (IBW) propagation and absorption for the first time at high poloidal mode number (-80< m<+80). Converged wave solutions for the mode converted wave are obtained in this limit and the predicted electron damping of the IBW is found to be consistent with experimental measurements from the Alcator C-Mod tokamak. The TORIC code has also been coupled to a bounce-averaged Fokker Planck module FPPRF and the combined codes are now run within the transport analysis tool TRANSP. This model was used to analyze off-axis hydrogen minority heating experiments in C-Mod where an internal transport barrier was obtained. (author)

Conceptual design Alcator C-MOD magnetic systems

International Nuclear Information System (INIS)

Schultz, J.H.; Becker, H.; Fertl, K.; Gwinn, D.; Montgomery, D.B.; Pierce, N.T.; Pillsbury, R.D. Jr.; Thome, R.J.

1986-01-01

The conceptual designs of the magnetic systems for Alcator C-MOD, a proposed tokamak at M.I.T., are described, including the toroidal magnet, the poloidal field coils and the cryogenic system. The toroidal magnet is constructed from rectangular plates, connected by sliding joints. Toroidal magnet forces are contained by a steel superstructure. Poloidal coil system options are largely or wholly inside the TF magnet, in order to control plasmas with high current, strong shaping, and expanded boundaries. All magnets are cryocooled by the natural circulation of boiling liquid nitrogen. 3 refs., 5 figs

IAEA programme on research reactor safety

International Nuclear Information System (INIS)

Alcala, F.; Di Meglio, A.F.

1995-01-01

This paper describes the IAEA programme on research reactor safety and includes the safety related areas of conversions to the use of low enriched uranium (LEU) fuel. The program is based on the IAEA statutory responsibilities as they apply to the requirements of over 320 research reactors operating around the world. The programme covers four major areas: (a) the development of safety documents; (b) safety missions to research reactor facilities; (c) support of research programmes on research reactor safety; (d) support of Technical Cooperation projects on research reactor safety issues. The demand for these activities by the IAEA member states has increased substantially in recent years especially in developing countries with increasing emphasis being placed on LEU conversion matters. In response to this demand, the IAEA has undertaken an extensive programme for each of the four areas above. (author)

Disruption Neutral Point Experiment on Alcator C-Mod

Science.gov (United States)

Granetz, R. S.; Nakamura, Y.

2000-10-01

Disruptions of single-null elongated plasmas generally result in loss of vertical position control, leading to a current quench occurring at the top or bottom of the machine, with all the attendant problems of halo and eddy currents flowing in divertor structures. On JT-60U, it has been found that if the plasma is operated with its magnetic axis at a particular height, called the neutral point, the initial vertical drift after a thermal quench is significantly slower than usual, and sometimes can even be arrested, thereby avoiding a current quench in the divertor region entirely. In an ongoing collaboration between MIT and JAERI, the neutral point concept is being tested in Alcator C-Mod, which has a significantly higher plasma elongation than JT-60U (1.65 vs 1.3). Calculations using TSC predict a neutral point at z~=+1 cm above the midplane (a=22 cm). The existence of a neutral point has now been experimentally confirmed, albeit at a height of z=+2.7 cm. The plasma has remained vertically stable for up to 9 ms after the disruption thermal quench, which in principle, is long enough for the PF control system to respond, if programmed appropriately. In addition, the physics of the neutral point stability on C-Mod appears to be somewhat different than that on JT-60U.

Assessment of ICRF Antenna Performance in Alcator C-Mod

International Nuclear Information System (INIS)

Schilling, G.; Wukitch, S.J.; Lin, Y.; Basse, N.; Bonoli, P.T.; Edlund, E.; Lin, L.; Parisot, A.; Porkolab, M.

2004-01-01

The Alcator C-Mod has presented a challenge to install high-power ICRF antennas in a tight space. Modifications have been made to the antenna plasma-facing surfaces and the internal current-carrying structure in order to overcome performance limitations. At the present time, the antennas have exceeded 5 MW into plasma with heating phasing, up to 2.7 MW with current-drive phasing, with good efficiency and no deleterious effects

Analyses for MARIA Research Reactor with RELAP/MOD3 code

International Nuclear Information System (INIS)

Szczurek, J.; Czerski, P.

2004-01-01

This paper deals with the application of the RELAP5/MOD3 code to the transient analyses for MARIA research reactor. Poland's MARIA Research Reactor is water and beryllium moderated, water-cooled reactor of a pool type with pressurized fuel channels containing concentric multi-tube assemblies of highly enriched uranium clad in aluminium. The RELAP5/MOD3 input data model includes the whole primary cooling circuit of the MARIA reactor. The model was qualified against the reactor data at steady state conditions and additionally against the existing reliable experimental data for a transient initiated by the reactor scram. The RELAP transient simulation was performed for loss of forced flow accidents including two scenarios with protected and unprotected (no scram) reactor core. Calculations allow estimating time margin for reactor scram initiation and reactivity feedbacks contribution to the results. (author)

The Role of Plasma Rotation in C-Mod Internal Transport Barriers

Science.gov (United States)

Fiore, C. L.; Ernst, D. R.; Rice, J. E.; Podpaly, Y.; Reinke, M. L.; Greenwald, M. J.; Hughes, J. W.; Ma, Y.; Bespamyatnov, I. O.; Rowan, W. L.

2010-11-01

ITBs in Alcator C-Mod featuring highly peaked density and pressure profiles are induced by injecting ICRF power with the second harmonic of the resonant frequency for minority hydrogen off-axis at the plasma half radius. These ITBs are formed in the absence of particle or momentum injection, and with monotonic q profiles with qmin ITB forms, this rotation decreases in the center of the plasma and forms a well, and often reverses direction in the core. This indicates that there is a strong EXB shearing rate in the region where the foot in the ITB density profile is observed. Preliminary gyrokinetic analyses indicate that this shearing rate is comparable to the ion temperature gradient mode (ITG) growth rate at this location and may be responsible for stabilizing the turbulence. Gyrokinetic analyses of recent experimental data obtained from a complete scan of the ICRF resonance position across the entire C-Mod plasma will be presented.

The design of a second harmonic tangential array interferometer for C-Mod

International Nuclear Information System (INIS)

Bretz, N.; Jobes, F.; Irby, J.

1997-01-01

A design for a tangential array interferometer for C-Mod operating at 1.06 and 0.53 μm is presented. This is a special type of two color interferometer in which a Nd:YAG laser is frequency doubled in a nonlinear crystal. Because the doubling efficiency is imperfect, two frequencies propagate collinearly through the plasma after which the 1.06 μm ray is doubled again mixing in the optical domain with the undoubled ray. The resulting interference is insensitive to path length but is affected by plasma dispersion in the usual way. A typical central fringe shift in C-Mod is expected to be 0.1 endash 1.0, but the absolute and relative accuracy in n e l measurements can be as high as in a conventional interferometer. This design uses a repetitively pulsed laser which is converted to a fan beam crossing the horizontal midplane. The chordal array is defined by internal retroreflectors on the C-Mod midplane which return the beam to the second doubler and a detector array. This interferometer design has beam diameters of a few millimeters and element spacings of a few centimeters, uses a repetitively pulsed, TEM 00 Nd:YAG laser, fiber optic beam transport, commercial components, and a compact optical design which minimizes port space requirements. An optical system design is presented which is based on the performance of a tabletop prototype at Princeton Plasma Physics Laboratory. copyright 1997 American Institute of Physics

Effect of reflection on Hα emissions in Alcator C-MOD

International Nuclear Information System (INIS)

Karney, C.F.; Stotler, D.P.; Skinner, C.H.; Terry, J.L.; Pappas, D.A.

1999-01-01

In order to explain anomalous intensity ratios which have been observed in Alcator C-MOD, the H α emissions in that experiment have been modeled with the DEGAS 2 code including the effects of wall reflection. By assuming that the first wall has different reflection coefficients for the two polarizations, we have qualitatively reproduced the observed anomaly. copyright 1999 American Institute of Physics

Particle size distribution of dust collected from Alcator C-MOD

International Nuclear Information System (INIS)

Gorman, S.V.; Carmack, W.J.; Hembree, P.B.

1998-01-01

There are important safety issues associated with tokamak dust, accumulated primarily from sputtering and disruptions. The dust may contain tritium, it may be activated, chemically toxic, and chemically reactive. The purpose of this paper is to present results from analyses of particulate collected from the Alcator C-MOD tokamak located at Massachusetts Institute of Technology (MIT) in Cambridge, Massachusetts. The sample obtained from C-MOD was not originally intended for examination outside of MIT. The sample was collected with the intent of performing only a composition analysis. However, MIT provided the INEEL with this sample for particle analysis. The sample was collected by vacuuming a section of the machine (covering approximately 1/3 of the machine surface) with a coarse fiber filter as the collection surface. The sample was then analyzed using an optical microscope, SEM microscope, Microtrac FRA particle size analyzer. The data fit a log-normal distribution. The count median diameter (CMD) of the samples ranged from 0.3 microm to 1.1 microm with geometric standard deviations (GSD) ranging from 2.8 to 5.2 and a mass median diameter (MMD) ranging from 7.22 to 176 microm

Web based electronic logbook and experiment run database viewer for Alcator C-Mod

International Nuclear Information System (INIS)

Fredian, T.W.; Stillerman, J.A.

2006-01-01

Since 1991, the scientists and engineers at the Alcator C-Mod experiment at MIT have been recording text entries about the experiments being performed in an electronic logbook. In addition, separate documents such as run plans, run summaries and experimental proposals have been created and stored in a variety of formats in computer files. This information has now been organized and made available via any modern web browser. The new web based interface permits the user to browse through all the logbook entries, run information and even view some key data traces of the experiment. Since this information is being catalogued by Internet search engines, these tools can also be used to quickly locate information. The web based logbook and run information interface provides some additional capabilities. Once logged into the web site, users can add, delete or modify logbook entries directly from their browser. The logbook window on their browser also provides dynamic updating when any new logbook entries are made. There is also live C-Mod operation status information with optional audio announcements available. The user can receive the same state change announcements such as 'entering init' or 'entering pulse' as they would if they were sitting in the C-Mod control room. This paper will describe the functionality of the web based logbook and how it was implemented

Molybdenum erosion measurements in Alcator C-Mod

Energy Technology Data Exchange (ETDEWEB)

Wampler, W.R. [Sandia National Labs., Albuquerque, NM (United States); LaBombard, B.; Lipshultz, B.; Pappas, D.; Pitcher, C.S. [Massachusetts Inst. of Tech., Cambridge, MA (United States); McCracken, G.M. [JET Joint Undertaking, Abingdon (United Kingdom)

1998-05-01

Erosion of molybdenum was measured on a set of 21 tiles after a run campaign of 1,090 shots in the Alcator C-Mod tokamak. The net erosion of molybdenum, was determined from changes in the depth of a thin chromium marker layer measured by Rutherford backscattering. Net Mo erosion was found to be approximately 150 nm near the outer divertor strike point, and much less everywhere else. Gross erosion rates by sputtering were estimated using ion energies and fluxes obtained from Langmuir probe measurements of edge-plasma conditions. Predicted net erosion using calculated gross erosion with prompt redeposition and measured net erosion agree within a factor of 3. Sputtering by boron and molybdenum impurities dominates erosion.

Finnish bioenergy research programme

Energy Technology Data Exchange (ETDEWEB)

Asplund, D. [VTT Energy, Jyvaeskylae (Finland)

1996-12-31

Finland is a leading country in the use of biofuels and has excellent opportunities to increase the use of biofuels by up to 25-30 %. The Finnish Government has set an objective for the promotion of bioenergy. The aim is to increase the use of bioenergy by about 25 % from the present level by 2005, and the increment corresponds to 1.5 million tonnes of oil equivalent (toe) per year. The R and D work has been considered as an important factor to achieve this ambitious goal. Energy research was organised into a series of research programmes in 1988 in accordance with the proposal of Finnish Energy Research Committee. The object of the research programmes is to enhance research activities and to bundle individual projects together into larger research packages. The common target of the Finnish energy research programmes is to proceed from basic and applied research to product development and pilot operation, and after that to the first commercial applications, e.g. demonstrations. As the organisation of energy research to programmes has led to good results, the Finnish Ministry of Trade and Industry decided to go on with this practice by launching new six-year programmes in 1993-1998. One of these programmes is the Bioenergy Research Programme and the co-ordination of this programme is carried out by VTT Energy. Besides VTT Energy the Finnish Forest Research Institute, Work Efficiency Institute, Metsaeteho and University of Joensuu are participating in the programme 7 refs.

Finnish bioenergy research programme

Energy Technology Data Exchange (ETDEWEB)

Asplund, D [VTT Energy, Jyvaeskylae (Finland)

1997-12-31

Finland is a leading country in the use of biofuels and has excellent opportunities to increase the use of biofuels by up to 25-30 %. The Finnish Government has set an objective for the promotion of bioenergy. The aim is to increase the use of bioenergy by about 25 % from the present level by 2005, and the increment corresponds to 1.5 million tonnes of oil equivalent (toe) per year. The R and D work has been considered as an important factor to achieve this ambitious goal. Energy research was organised into a series of research programmes in 1988 in accordance with the proposal of Finnish Energy Research Committee. The object of the research programmes is to enhance research activities and to bundle individual projects together into larger research packages. The common target of the Finnish energy research programmes is to proceed from basic and applied research to product development and pilot operation, and after that to the first commercial applications, e.g. demonstrations. As the organisation of energy research to programmes has led to good results, the Finnish Ministry of Trade and Industry decided to go on with this practice by launching new six-year programmes in 1993-1998. One of these programmes is the Bioenergy Research Programme and the co-ordination of this programme is carried out by VTT Energy. Besides VTT Energy the Finnish Forest Research Institute, Work Efficiency Institute, Metsaeteho and University of Joensuu are participating in the programme 7 refs.

Cloud-based uniform ChIP-Seq processing tools for modENCODE and ENCODE.

Science.gov (United States)

Trinh, Quang M; Jen, Fei-Yang Arthur; Zhou, Ziru; Chu, Kar Ming; Perry, Marc D; Kephart, Ellen T; Contrino, Sergio; Ruzanov, Peter; Stein, Lincoln D

2013-07-22

Funded by the National Institutes of Health (NIH), the aim of the Model Organism ENCyclopedia of DNA Elements (modENCODE) project is to provide the biological research community with a comprehensive encyclopedia of functional genomic elements for both model organisms C. elegans (worm) and D. melanogaster (fly). With a total size of just under 10 terabytes of data collected and released to the public, one of the challenges faced by researchers is to extract biologically meaningful knowledge from this large data set. While the basic quality control, pre-processing, and analysis of the data has already been performed by members of the modENCODE consortium, many researchers will wish to reinterpret the data set using modifications and enhancements of the original protocols, or combine modENCODE data with other data sets. Unfortunately this can be a time consuming and logistically challenging proposition. In recognition of this challenge, the modENCODE DCC has released uniform computing resources for analyzing modENCODE data on Galaxy (https://github.com/modENCODE-DCC/Galaxy), on the public Amazon Cloud (http://aws.amazon.com), and on the private Bionimbus Cloud for genomic research (http://www.bionimbus.org). In particular, we have released Galaxy workflows for interpreting ChIP-seq data which use the same quality control (QC) and peak calling standards adopted by the modENCODE and ENCODE communities. For convenience of use, we have created Amazon and Bionimbus Cloud machine images containing Galaxy along with all the modENCODE data, software and other dependencies. Using these resources provides a framework for running consistent and reproducible analyses on modENCODE data, ultimately allowing researchers to use more of their time using modENCODE data, and less time moving it around.

Blob sizes and velocities in the Alcator C-Mod scrape-off layer

DEFF Research Database (Denmark)

Kube, R.; Garcia, O.E.; LaBombard, B.

A new blob-tracking algorithm for the GPI diagnostic installed in the outboard-midplane of Alcator C-Mod is developed. I t tracks large-amplitude fluctuations propagating through the scrape-off layer and calculates blob sizes and velocities. We compare the results of this method to a blob velocity...

Transport and Stability in C-Mod ITBs in Diverse Regimes

Science.gov (United States)

Fiore, C. L.; Ernst, D. R.; Howard, N. T.; Kasten, C. P.; Mikkelsen, D.; Reinke, M. L.; Rice, J. E.; White, A. E.; Rowan, W. L.; Bespamyatnov, I.

2012-10-01

Internal Transport Barriers (ITBs) in C-Mod feature highly peaked density and pressure profiles and are typically induced by the introduction of radio frequency power in the ion cyclotron range of frequencies (ICRF) with the second harmonic of the resonance for minority hydrogen ions positioned off-axis at the plasma half radius on either the low or high field side of the plasma. These ITBs are formed in the absence of particle or momentum injection, and with monotonic q profiles with qminITB dynamics in a reactor relevant regime. Recently, linear and non-linear gyrokinetic simulations have demonstrated that changes in the ion temperature and plasma rotation profiles, coincident with the application of off-axis ICRF heating, contribute to greater stability to ion temperature gradient driven fluctuation in the plasma. This results in reduced turbulent driven outgoing heat flux. To date, ITB formation in C-Mod has only been observed in EDA H-mode plasmas with moderate (2-3 MW) ICRF power. Experiments to explore the formation of ITBs in other operating regimes such as I-mode and also with high ICRF power are being undertaken to understand further the process of ITB formation and sustainment, especially with regard to turbulent driven transport.

Vectors and Rotations in 3-Dimensions: Vector Algebra for the C++ Programmer

Science.gov (United States)

2016-12-01

release; distribution is unlimited. 1. Introduction This report describes 2 C++ classes: a Vector class for performing vector algebra in 3-dimensional...ARL-TR-7894•DEC 2016 US Army Research Laboratory Vectors and Rotations in 3-Dimensions:Vector Algebra for the C++ Programmer by Richard Saucier...Army Research Laboratory Vectors and Rotations in 3-Dimensions:Vector Algebra for the C++ Programmer by Richard Saucier Survivability/Lethality

Investigation of the critical edge ion heat flux for L-H transitions in Alcator C-Mod and its dependence on B T

Science.gov (United States)

Schmidtmayr, M.; Hughes, J. W.; Ryter, F.; Wolfrum, E.; Cao, N.; Creely, A. J.; Howard, N.; Hubbard, A. E.; Lin, Y.; Reinke, M. L.; Rice, J. E.; Tolman, E. A.; Wukitch, S.; Ma, Y.; ASDEX Upgrade Team; Alcator C-Mod Team

2018-05-01

This paper presents investigations on the role of the edge ion heat flux for transitions from L-mode to H-mode in Alcator C-Mod. Previous results from the ASDEX Upgrade tokamak indicated that a critical value of edge ion heat flux per particle is needed for the transition. Analysis of C-Mod data confirms this result. The edge ion heat flux is indeed found to increase linearly with density at given magnetic field and plasma current. Furthermore, the Alcator C-Mod data indicate that the edge ion heat flux at the L-H transition also increases with magnetic field. Combining the data from Alcator C-Mod and ASDEX Upgrade yields a general expression for the edge ion heat flux at the L-H transition. These results are discussed from the point of view of the possible physics mechanism of the L-H transition. They are also compared to the L-H power threshold scaling and an extrapolation for ITER is given.

Estimation des paramètres de modèles pour la digestion anaérobie

OpenAIRE

Martinez , Ricardo

2003-01-01

La finalité de ce travail a été d'estimer de la meilleure manière possible des paramètres de différents modèles sur la respiration anaérobie. Dans un premier temps nous présentons les bases qu'on utilise pour construire les modèles du procédé biochimique. Puis nous faisons une analyse qualitative des modèles les plus connus sur le sujet. Dans un deuxième temps nous avons suggéré différents modèles, afin de mieux estimer les paramètres du modèle initial. Nous avons mis au point un programme d'...

Edge Turbulence Imaging on NSTX and Alcator C-Mod

International Nuclear Information System (INIS)

S.J. Zweben; R.A. Maqueda; J.L. Terry; B. Bai; C.J. Boswell; C.E. Bush; D. D'Ippolito; E.D. Fredrickson; M. Greenwald; K. Hallatschek; S. Kaye; B. LaBombard; R. Maingi; J. Myra; W.M. Nevins; B.N. Rogers; D.P. Stotler; J. Wilgen; and X.Q. Xu

2002-01-01

Edge turbulence images have been made using an ultra-high speed CCD camera on both NSTX and Alcator C-Mod. In both cases, the D-alpha or HeI (587.6 nm) line emission from localized deuterium or helium gas puffs was viewed along a local magnetic field line near the outer midplane. Fluctuations in this line emission reflect fluctuations in electron density and/or electron temperature through the atomic excitation rates, which can be modeled using the DEGAS-2 code. The 2-D structure of the measured turbulence can be compared with theoretical simulations based on 3-D fluid models

FFUSION research programme 1993-1998. Final report of the Finnish fusion research programme

Energy Technology Data Exchange (ETDEWEB)

Karttunen, S.; Heikkinen, J.; Korhonen, R. [VTT Energy, Espoo (Finland)] [and others

1998-12-31

This report summarizes the results of the Fusion Energy Research Programme, FFUSION, during the period 1993-1998. After the planning phase the programme started in 1994, and later in March 1995 the FFUSION Programme was integrated into the EU Fusion Programme and the Association Euratom-Tekes was established. Research areas in the FFUSION Programme are (1) fusion physics and plasma engineering, (2) fusion reactor materials and (3) remote handling systems. In all research areas industry is involved. Recently, a project on environmental aspects of fusion and other future energy systems started as a part of the socio-economic research (SERF) in the Euratom Fusion Programme. A crucial component of the FFUSION programme is the close collaboration between VTT Research Institutes, universities and Finnish industry. This collaboration has guaranteed dynamic and versatile research teams, which are large enough to tackle challenging research and development projects. Regarding industrial fusion R and D activities, the major step was the membership of Imatran Voima Oy in the EFET Consortium (European Fusion Engineering and Technology), which further strengthened the position of industry in the engineering design activities of ITER. The number of FFUSION research projects was 66. In addition, there were 32 industrial R and D projects. The total cost of the FFUSION Programme in 1993-1998 amounted to FIM 54 million in research at VTT and universities and an additional FIM 21 million for R and D in Finnish industry. The main part of the funding was provided by Tekes, 36%. Since 1995, yearly Euratom funding has exceeded 25%. The FFUSION research teams have played an active role in the European Programme, receiving excellent recognition from the European partners. Theoretical and computational fusion physics has been at a high scientific level and the group collaborates with the leading experimental laboratories in Europe. Fusion technology is focused on reactor materials, joining

FFUSION research programme 1993-1998. Final report of the Finnish fusion research programme

International Nuclear Information System (INIS)

Karttunen, S.; Heikkinen, J.; Korhonen, R.

1998-01-01

This report summarizes the results of the Fusion Energy Research Programme, FFUSION, during the period 1993-1998. After the planning phase the programme started in 1994, and later in March 1995 the FFUSION Programme was integrated into the EU Fusion Programme and the Association Euratom-Tekes was established. Research areas in the FFUSION Programme are (1) fusion physics and plasma engineering, (2) fusion reactor materials and (3) remote handling systems. In all research areas industry is involved. Recently, a project on environmental aspects of fusion and other future energy systems started as a part of the socio-economic research (SERF) in the Euratom Fusion Programme. A crucial component of the FFUSION programme is the close collaboration between VTT Research Institutes, universities and Finnish industry. This collaboration has guaranteed dynamic and versatile research teams, which are large enough to tackle challenging research and development projects. Regarding industrial fusion R and D activities, the major step was the membership of Imatran Voima Oy in the EFET Consortium (European Fusion Engineering and Technology), which further strengthened the position of industry in the engineering design activities of ITER. The number of FFUSION research projects was 66. In addition, there were 32 industrial R and D projects. The total cost of the FFUSION Programme in 1993-1998 amounted to FIM 54 million in research at VTT and universities and an additional FIM 21 million for R and D in Finnish industry. The main part of the funding was provided by Tekes, 36%. Since 1995, yearly Euratom funding has exceeded 25%. The FFUSION research teams have played an active role in the European Programme, receiving excellent recognition from the European partners. Theoretical and computational fusion physics has been at a high scientific level and the group collaborates with the leading experimental laboratories in Europe. Fusion technology is focused on reactor materials, joining

An evaluation of TRAC-PF1/MOD1 computer code performance during posttest simulations of Semiscale MOD-2C feedwater line break transients

International Nuclear Information System (INIS)

Hall, D.G.; Watkins, J.C.

1987-01-01

This report documents an evaluation of the TRAC-PF1/MOD1 reactor safety analysis computer code during computer simulations of feedwater line break transients. The experimental data base for the evaluation included the results of three bottom feedwater line break tests performed in the Semiscale Mod-2C test facility. The tests modeled 14.3% (S-FS-7), 50% (S-FS-11), and 100% (S-FS-6B) breaks. The test facility and the TRAC-PF1/MOD1 model used in the calculations are described. Evaluations of the accuracy of the calculations are presented in the form of comparisons of measured and calculated histories of selected parameters associated with the primary and secondary systems. In addition to evaluating the accuracy of the code calculations, the computational performance of the code during the simulations was assessed. A conclusion was reached that the code is capable of making feedwater line break transient calculations efficiently, but there is room for significant improvements in the simulations that were performed. Recommendations are made for follow-on investigations to determine how to improve future feedwater line break calculations and for code improvements to make the code easier to use

13C-Tracer Experiments in DIII-D Preliminary to Thermal Oxidation Experiments to Understand Tritium Recovery in DIII-D, JET, C-Mod, and MAST

International Nuclear Information System (INIS)

Stangeby, P.; Allen, S.; Bekris, N.; Brooks, N.; Christie, K.; Chrobak, C.; Coad, J.; Counsell, G.; Davis, J.; Elder, J.; Fenstermacher, M.; Groth, M.; Haasz, A.; Likonen, J.; Lipschultz, B.; McLean, A.; Philipps, V.; Porter, G.; Rudakov, D.; Shea, J.; Wampler, W.; Watkins, J.; West, W.; Whyte, D.

2006-01-01

Retention of tritium in carbon co-deposits is a serious concern for ITER. Developing a reliable in-situ removal method of the co-deposited tritium would allow the use of carbon plasma-facing components which have proven reliable in high heat flux conditions and compatible with high performance plasmas. Thermal oxidation is a potential solution, capable of reaching even hidden locations. It is necessary to establish the least severe conditions to achieve adequate tritium recovery, minimizing damage and reconditioning time. The first step in this multi-machine project is 13 C-tracer experiments in DIII-D, JET, C-Mod and MAST. In DIII-D and JET, 13 CH 4 has been (and in C-Mod and MAST, will be) injected toroidally symmetrically, facilitating quantification and interpretation of the results. Tiles have been removed, analyzed for 13 C content and will next be evaluated in a thermal oxidation test facility in Toronto with regard to the ability of different severities of oxidation exposure to remove the different types of (known and measured) 13 C co-deposit. Removal of D/T from B on Mo tiles from C-Mod will also be tested. OEDGE interpretive code analysis of the 13 C deposition patterns is used to generate the understanding needed to apply findings to ITER. First results are reported here for the 13 C injection experiments IN DIII-D

SCDAP/RELAP5/MOD3 code development

International Nuclear Information System (INIS)

Allison, C.M.; Siefken, J.L.; Coryell, E.W.

1992-01-01

The SCOAP/RELAP5/MOD3 computer code is designed to describe the overall reactor coolant system (RCS) thermal-hydraulic response, core damage progression, and fission product release and transport during severe accidents. The code is being developed at the Idaho National Engineering Laboratory (INEL) under the primary sponsorship of the Office of Nuclear Regulatory Research of the US Nuclear Regulatory Commission (NRC). Code development activities are currently focused on three main areas - (a) code usability, (b) early phase melt progression model improvements, and (c) advanced reactor thermal-hydraulic model extensions. This paper describes the first two activities. A companion paper describes the advanced reactor model improvements being performed under RELAP5/MOD3 funding

Stability of Microturbulent Drift Modes during Internal Transport Barrier Formation in the Alcator C-Mod Radio Frequency Heated H-mode

International Nuclear Information System (INIS)

Redi, M.H.; Fiore, C.L.; Dorland, W.; Mikkelsen, D.R.; Rewoldt, G.; Bonoli, P.T.; Ernst, D.R.; Rice, J.E.; Wukitch, S.J.

2003-01-01

Recent H-mode experiments on Alcator C-Mod [I.H. Hutchinson, et al., Phys. Plasmas 1 (1994) 1511] which exhibit an internal transport barrier (ITB), have been examined with flux tube geometry gyrokinetic simulations, using the massively parallel code GS2 [M. Kotschenreuther, G. Rewoldt, and W.M. Tang, Comput. Phys. Commun. 88 (1995) 128]. The simulations support the picture of ion/electron temperature gradient (ITG/ETG) microturbulence driving high xi/ xe and that suppressed ITG causes reduced particle transport and improved ci on C-Mod. Nonlinear calculations for C-Mod confirm initial linear simulations, which predicted ITG stability in the barrier region just before ITB formation, without invoking E x B shear suppression of turbulence. Nonlinear fluxes are compared to experiment, which both show low heat transport in the ITB and higher transport within and outside of the barrier region

Edge Minority Heating Experiment in Alcator C-Mod

International Nuclear Information System (INIS)

Zweben, S.J.; Terry, J.L.; Bonoli, P.; Budny, R.; Chang, C.S.; Fiore, C.; Schilling, G.; Wukitch, S.; Hughes, J.; Lin, Y.; Perkins, R.; Porkolab, M.; Alcator C-Mod Team

2005-01-01

An attempt was made to control global plasma confinement in the Alcator C-Mod tokamak by applying ion cyclotron resonance heating (ICRH) power to the plasma edge in order to deliberately create a minority ion tail loss. In theory, an edge fast ion loss could modify the edge electric field and so stabilize the edge turbulence, which might then reduce the H-mode power threshold or improve the H-mode barrier. However, the experimental result was that edge minority heating resulted in no improvement in the edge plasma parameters or global stored energy, at least at power levels of P RF (le) 5.5 MW. A preliminary analysis of these results is presented and some ideas for improvement are discussed

Pendulum : une extension réactive pour la programmation Web en OCaml

OpenAIRE

El Sibaïe , Rémy; Chailloux , Emmanuel

2016-01-01

International audience; La programmation des interactions des différents composants d'une application Web est devenue particulièrement complexe tant au niveau de la conception que de la mise au point. Peu de garanties peuvent être apportées sur la coordination des interactions internes et les réactions aux événements externes reposant sur le modèle de concurrence de JavaScript. Il devient alors nécessaire de proposer un modèle de concurrence simple améliorant cette situation. Dans ce cadre, c...

The measurement of the intrinsic impurities of molybdenum and carbon in the Alcator C-Mod tokamak plasma using low resolution spectroscopy

Science.gov (United States)

May, M. J.; Finkenthal, M.; Regan, S. P.; Moos, H. W.; Terry, J. L.; Goetz, J. A.; Graf, M. A.; Rice, J. E.; Marmar, E. S.; Fournier, K. B.; Goldstein, W. H.

1997-06-01

The intrinsic impurity content of molybdenum and carbon was measured in the Alcator C-Mod tokamak using low resolution, multilayer mirror (MLM) spectroscopy ( Delta lambda ~1-10 AA). Molybdenum was the dominant high-Z impurity and originated from the molybdenum armour tiles covering all of the plasma facing surfaces (including the inner column, the poloidal divertor plates and the ion cyclotron resonant frequency (ICRF) limiter) at Alcator C-Mod. Despite the all metal first wall, a carbon concentration of 1 to 2% existed in the plasma and was the major low-Z impurity in Alcator C-Mod. Thus, the behaviour of intrinsic molybdenum and carbon penetrating into the main plasma and the effect on the plasma must be measured and characterized during various modes of Alcator C-Mod operation. To this end, soft X-ray extreme ultraviolet (XUV) emission lines of charge states, ranging from hydrogen-like to helium-like lines of carbon (radius/minor radius, r/a~1) at the plasma edge to potassium to chlorine-like (0.4Data Nucl. Data Tables 33 (1985) 149), which were incorporated into the collisional radiative model. The intrinsic i

Overview of Recent Alcator C-Mod Highlights

Science.gov (United States)

Marmar, Earl; C-Mod Team

2013-10-01

Analysis and modeling of recent C-Mod experiments has yielded significant results across multiple research topics. I-mode provides routine access to high confinement plasma (H98 up to 1.2) in quasi-steady state, without large ELMs; pedestal pressure and impurity transport are regulated by short-wavelength EM waves, and core turbulence is reduced. Multi-channel transport is being investigated in Ohmic and RF-heated plasmas, using advanced diagnostics to validate non-linear gyrokinetic simulations. Results from the new field-aligned ICRF antenna, including significantly reduced high-Z metal impurity contamination, and greatly improved load-tolerance, are being understood through antenna-plasma modeling. Reduced LHCD efficiency at high density correlates with parametric decay and enhanced edge absorption. Strong flow drive and edge turbulence suppression are seen from LHRF, providing new approaches for plasma control. Plasma density profiles directly in front of the LH coupler show non-linear modifications, with important consequences for wave coupling. Disruption-mitigation experiments using massive gas injection at multiple toroidal locations show unexpected results, with potentially significant implications for ITER. First results from a novel accelerator-based PMI diagnostic are presented. What would be the world's first actively-heated high-temperature advanced tungsten divertor is designed and ready for construction. Conceptual designs are being developed for an ultra-advanced divertor facility, Alcator DX, to attack key FNSF and DEMO heat-flux challenges integrated with a high-performance core. Supported by USDOE.

Stationary density profiles in the Alcator C-mod tokamak

International Nuclear Information System (INIS)

Kesner, J.; Ernst, D.; Hughes, J.; Mumgaard, R.; Shiraiwa, S.; Whyte, D.; Scott, S.

2012-01-01

In the absence of an internal particle source, plasma turbulence will impose an intrinsic relationship between an inwards pinch and an outwards diffusion resulting in a stationary density profile. The Alcator C-mod tokamak utilizes RF heating and current drive so that fueling only occurs in the vicinity of the separatrix. Discharges that transition from L-mode to I-mode are seen to maintain a self-similar stationary density profile as measured by Thomson scattering. For discharges with negative magnetic shear, an observed rise of the safety factor in the vicinity of the magnetic axis appears to be accompanied by a decrease of electron density, qualitatively consistent with the theoretical expectations.

Validation of TGLF in C-Mod and DIII-D using machine learning and integrated modeling tools

Science.gov (United States)

Rodriguez-Fernandez, P.; White, Ae; Cao, Nm; Creely, Aj; Greenwald, Mj; Grierson, Ba; Howard, Nt; Meneghini, O.; Petty, Cc; Rice, Je; Sciortino, F.; Yuan, X.

2017-10-01

Predictive models for steady-state and perturbative transport are necessary to support burning plasma operations. A combination of machine learning algorithms and integrated modeling tools is used to validate TGLF in C-Mod and DIII-D. First, a new code suite, VITALS, is used to compare SAT1 and SAT0 models in C-Mod. VITALS exploits machine learning and optimization algorithms for the validation of transport codes. Unlike SAT0, the SAT1 saturation rule contains a model to capture cross-scale turbulence coupling. Results show that SAT1 agrees better with experiments, further confirming that multi-scale effects are needed to model heat transport in C-Mod L-modes. VITALS will next be used to analyze past data from DIII-D: L-mode ``Shortfall'' plasma and ECH swing experiments. A second code suite, PRIMA, allows for integrated modeling of the plasma response to Laser Blow-Off cold pulses. Preliminary results show that SAT1 qualitatively reproduces the propagation of cold pulses after LBO injections and SAT0 does not, indicating that cross-scale coupling effects play a role in the plasma response. PRIMA will be used to ``predict-first'' cold pulse experiments using the new LBO system at DIII-D, and analyze existing ECH heat pulse data. Work supported by DE-FC02-99ER54512, DE-FC02-04ER54698.

High Speed Images of Edge Plasmas in NSTX and Alcator C-Mod

International Nuclear Information System (INIS)

Maqueda, R.J.; Grulke, O.; Terry, J.L.; Zweben, S.J.

2007-01-01

This talk will describe the high speed imaging diagnostics on NSTX and Alcator C-Mod and show movies of various edge phenomena, including turbulence during L-modes and H modes, L-H and H-L transitions, effects of MHD activity and ELMs of various types, and wide angle views of the toroidal vs. poloidal structure of these edge '' filaments ''. Issues concerning the interpretation of these images will be discussed. (author)

Production of internal transport barriers via self-generated mean flows in Alcator C-Mod

Energy Technology Data Exchange (ETDEWEB)

Fiore, C. L.; Ernst, D. R.; Podpaly, Y. A.; Howard, N. T.; Lee, Jungpyo; Reinke, M. L.; Rice, J. E.; Hughes, J. W.; Ma, Y. [MIT-PSFC, 77 Mass. Ave., Cambridge, Massachusetts 02139 (United States); Mikkelsen, D. [Princeton Plasma Physics Laboratory, P.O. Box 451, Princeton, New Jersey 08543-0451 (United States); Rowan, W. L.; Bespamyatnov, I. [FRC, U of Texas at Austin, Austin, Texas 78712 (United States)

2012-05-15

New results suggest that changes observed in the intrinsic toroidal rotation influence the internal transport barrier (ITB) formation in the Alcator C-Mod tokamak [E. S. Marmar and Alcator C-Mod group, Fusion Sci. Technol. 51, 261 (2007)]. These arise when the resonance for ion cyclotron range of frequencies (ICRF) minority heating is positioned off-axis at or outside of the plasma half-radius. These ITBs form in a reactor relevant regime, without particle or momentum injection, with Ti Almost-Equal-To Te, and with monotonic q profiles (q{sub min} < 1). C-Mod H-mode plasmas exhibit strong intrinsic co-current rotation that increases with increasing stored energy without external drive. When the resonance position is moved off-axis, the rotation decreases in the center of the plasma resulting in a radial toroidal rotation profile with a central well which deepens and moves farther off-axis when the ICRF resonance location reaches the plasma half-radius. This profile results in strong E Multiplication-Sign B shear (>1.5 Multiplication-Sign 10{sup 5} rad/s) in the region where the ITB foot is observed. Gyrokinetic analyses indicate that this spontaneous shearing rate is comparable to the linear ion temperature gradient (ITG) growth rate at the ITB location and is sufficient to reduce the turbulent particle and energy transport. New and detailed measurement of the ion temperature demonstrates that the radial profile flattens as the ICRF resonance position moves off axis, decreasing the drive for the ITG the instability as well. These results are the first evidence that intrinsic rotation can affect confinement in ITB plasmas.

Neutral particle dynamics in the Alcator C-Mod tokamak

Energy Technology Data Exchange (ETDEWEB)

Niemczewski, Artur P. [Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)

1995-08-01

This thesis presents an experimental study of neutral particle dynamics in the Alcator C-Mod tokamak. The primary diagnostic used is a set of six neutral pressure gauges, including special-purpose gauges built for in situ tokamak operation. While a low main chamber neutral pressure coincides with high plasma confinement regimes, high divertor pressure is required for heat and particle flux dispersion in future devices such as ITER. Thus we examine conditions that optimize divertor compression, defined here as a divertor-to-midplane pressure ratio. We find both pressures depend primarily on the edge plasma regimes defined by the scrape-off-layer heat transport. While the maximum divertor pressure is achieved at high core plasma densities corresponding to the detached divertor state, the maximum compression is achieved in the high-recycling regime. Variations in the divertor geometry have a weaker effect on the neutral pressures. For otherwise similar plasmas the divertor pressure and compression are maximum when the strike point is at the bottom of the vertical target plate. We introduce a simple flux balance model, which allows us to explain the divertor neutral pressure across a wide range of plasma densities. In particular, high pressure sustained in the detached divertor (despite a considerable drop in the recycling source) can be explained by scattering of neutrals off the cold plasma plugging the divertor throat. Because neutrals are confined in the divertor through scattering and ionization processes (provided the mean-free-paths are much shorter than a typical escape distance) tight mechanical baffling is unnecessary. The analysis suggests that two simple structural modifications may increase the divertor compression in Alcator C-Mod by a factor of about 5. Widening the divertor throat would increase the divertor recycling source, while closing leaks in the divertor structure would eliminate a significant neutral loss mechanism.

High performance discharges and capabilities in Alcator C-Mod

International Nuclear Information System (INIS)

Porkolab, M.

1996-01-01

Alcator C-Mod is a compact, diverted, shaped, high magnetic field (B = 9 T) tokamak operating at the Massachusetts Institute of Technology Plasma Fusion Center. The machine interior is all metallic, and the walls and divertor region are covered with molybdenum tiles. The vacuum vessel is a continuous, thick wall stainless steel construction, prototypical of future fusion devices (e.g., ITER). Typical discharge cleaning utilizes ECDC, or electron-cyclotron discharge cleaning, in the steady state at low magnetic field (0.0875 T). While its dimensions are compact (R = 0.67 m, a = 0.22 m, K = 1.8), C-Mod is designed to operate up to 2.5 MA at 9.0 T magnetic field. To present date the machine has operated at currents up to 1.5 MA at B = 5.3 T, and magnetic fields up to 8.0 T at I p = 1.2 MA. Due to the high current density, line average densities of 4.0 x 10 20 m -3 are obtained with gas fueling, and peak densities in excess of 1.0 x 10 21 m -3 have been obtained with pellet fueling. Typical pulse lengths are up to 2.0 seconds, with a flat-top of typically 1.0 sec. Presently the device is equipped with 4.0 MW of ICRF heating power operating at 80 MHz, but this capability is being upgraded to 8.0 MW with the addition of 4.0 MW of tunable ICRF power operating at 40.80 MHz. A 20 pellet/pulse deuterium injector is operational, and a 4 pellet Li injector is also operational. To reduce the influx of metallic impurities during high power operation, recently boronization of the machine interior was begun prior to plasma discharges, this allowed plasma operation with full auxiliary power capability without excessive radiative power losses from the plasma core. 7 refs

Neutral particle dynamics in the Alcator C-Mod tokamak

International Nuclear Information System (INIS)

Niemczewski, A.P.

1995-08-01

This thesis presents an experimental study of neutral particle dynamics in the Alcator C-Mod tokamak. The primary diagnostic used is a set of six neutral pressure gauges, including special-purpose gauges built for in situ tokamak operation. While a low main chamber neutral pressure coincides with high plasma confinement regimes, high divertor pressure is required for heat and particle flux dispersion in future devices such as ITER. Thus we examine conditions that optimize divertor compression, defined here as a divertor-to-midplane pressure ratio. We find both pressures depend primarily on the edge plasma regimes defined by the scrape-off-layer heat transport. While the maximum divertor pressure is achieved at high core plasma densities corresponding to the detached divertor state, the maximum compression is achieved in the high-recycling regime. Variations in the divertor geometry have a weaker effect on the neutral pressures. For otherwise similar plasmas the divertor pressure and compression are maximum when the strike point is at the bottom of the vertical target plate. We introduce a simple flux balance model, which allows us to explain the divertor neutral pressure across a wide range of plasma densities. In particular, high pressure sustained in the detached divertor (despite a considerable drop in the recycling source) can be explained by scattering of neutrals off the cold plasma plugging the divertor throat. Because neutrals are confined in the divertor through scattering and ionization processes (provided the mean-free-paths are much shorter than a typical escape distance) tight mechanical baffling is unnecessary. The analysis suggests that two simple structural modifications may increase the divertor compression in Alcator C-Mod by a factor of about 5. Widening the divertor throat would increase the divertor recycling source, while closing leaks in the divertor structure would eliminate a significant neutral loss mechanism. 146 refs., 82 figs., 14 tabs

Principals, agents and research programmes

OpenAIRE

Elizabeth Shove

2003-01-01

Research programmes appear to represent one of the more powerful instruments through which research funders (principals) steer and shape what researchers (agents) do. The fact that agents navigate between different sources and styles of programme funding and that they use programmes to their own ends is readily accommodated within principal-agent theory with the help of concepts such as shirking and defection. Taking a different route, I use three examples of research programming (by the UK, ...

Ohmic ITBs in Alcator C-Mod

Science.gov (United States)

Fiore, C. L.; Rowan, W. L.; Dominguez, A.; Hubbard, A. E.; Ince-Cushman, A.; Greenwald, M. J.; Lin, L.; Marmar, E. S.; Reinke, M.; Rice, J. E.; Zhurovich, K.

2007-11-01

Internal transport barrier plasmas can arise spontaneously in ohmic Alcator C-Mod plasmas where an EDA H-mode has been developed by magnetic field ramping. These ohmic ITBs share the hallmarks of ITBs created with off-axis ICRF injection in that they have highly peaked density and pressure profiles and the peaking can be suppressed by on-axis ICRF. There is a reduction of particle and thermal flux in the barrier region which then allows the neoclassical pinch to peak the central density. Recent work on ITB onset conditions [1] which was motivated by turbulence studies [2] points to the broadening of the Ti profile with off-axis ICRF acting to reduce the ion temperature gradient. This suppresses ITG instability driven particle fluxes, which is thought to be the primary mechanism for ITB formation. The object of this study is to examine the characteristics of ohmic ITBs to find whether the stability of plasmas and the plasma parameters support the onset model. [1]K. Zhurovich, et al., To be published in Nuclear Fusion [2] D. R. Ernst, et al., Phys. Plasmas 11, 2637 (2004)

TRAC-PF1/MOD2 status and plans

International Nuclear Information System (INIS)

Spore, J.W.; Steinke, R.G.; Nelson, R.A.; Cappiello, M.W.; Jenks, R.

1989-01-01

The development of the TRAC-PF1/MOD1 code was completed in July 1988 with the release of Version 14.4. A TRAC-PF1/MOD2 code development plan addresses code deficiencies identified in the MOD1 code in order to provide an accurate and defensible tool that can be used to simulate large-break loss-of-coolant accidents (LOCAs), small-break LOCAs, and operational transients. The MOD2 code development plan is an international cooperative effort that includes contributions from Los Alamos National Laboratory, Idaho National Engineering Laboratory (INEL), Japanese Atomic Energy Research Institute (JAERI), Cray Research, Central Electricity Generating Board (CEGB), and United Kingdom Atomic Energy Authority (UKAEA)

An analysis of the binding of repressor protein ModE to modABCD (molybdate transport) operator/promoter DNA of Escherichia coli.

Science.gov (United States)

Grunden, A M; Self, W T; Villain, M; Blalock, J E; Shanmugam, K T

1999-08-20

Expression of the modABCD operon in Escherichia coli, which codes for a molybdate-specific transporter, is repressed by ModE in vivo in a molybdate-dependent fashion. In vitro DNase I-footprinting experiments identified three distinct regions of protection by ModE-molybdate on the modA operator/promoter DNA, GTTATATT (-15 to -8; region 1), GCCTACAT (-4 to +4; region 2), and GTTACAT (+8 to +14; region 3). Within the three regions of the protected DNA, a pentamer sequence, TAYAT (Y = C or T), can be identified. DNA-electrophoretic mobility experiments showed that the protected regions 1 and 2 are essential for binding of ModE-molybdate to DNA, whereas the protected region 3 increases the affinity of the DNA to the repressor. The stoichiometry of this interaction was found to be two ModE-molybdate per modA operator DNA. ModE-molybdate at 5 nM completely protected the modABCD operator/promoter DNA from DNase I-catalyzed hydrolysis, whereas ModE alone failed to protect the DNA even at 100 nM. The apparent K(d) for the interaction between the modA operator DNA and ModE-molybdate was 0.3 nM, and the K(d) increased to 8 nM in the absence of molybdate. Among the various oxyanions tested, only tungstate replaced molybdate in the repression of modA by ModE, but the affinity of ModE-tungstate for modABCD operator DNA was 6 times lower than with ModE-molybdate. A mutant ModE(T125I) protein, which repressed modA-lac even in the absence of molybdate, protected the same region of modA operator DNA in the absence of molybdate. The apparent K(d) for the interaction between modA operator DNA and ModE(T125I) was 3 nM in the presence of molybdate and 4 nM without molybdate. The binding of molybdate to ModE resulted in a decrease in fluorescence emission, indicating a conformational change of the protein upon molybdate binding. The fluorescence emission spectra of mutant ModE proteins, ModE(T125I) and ModE(Q216*), were unaffected by molybdate. The molybdate-independent mutant Mod

Design of a New Optical System for Alcator C-Mod Motional Stark Effect Diagnostic

International Nuclear Information System (INIS)

Ko, Jinseok; Scott, Steve; Bitter, Manfred; Lerner, Scott

2009-01-01

The motional Stark effect (MSE) diagnostic on Alcator C-Mod uses an in-vessel optical system (five lenses and three mirrors) to relay polarized light to an external polarimeter because port access limitations on Alcator C-Mod preclude a direct view of the diagnostic beam. The system experiences unacceptable, spurious drifts of order several degrees in measured pitch angle over the course of a run day. Recent experiments illuminated the MSE diagnostic with polarized light of fixed orientation as heat was applied to various optical elements. A large change in measured angle was observed as two particular lenses were heated, indicating that thermal-stress-induced birefringence is a likely cause of the spurious variability. Several new optical designs have been evaluated to eliminate the affected in-vessel lenses and to replace the focusing they provide with curved mirrors; however, ray tracing calculations imply that this method is not feasible. A new approach is under consideration that utilizes in situ calibrations with in-vessel reference polarized light sources. 2008 American Institute of Physics.

Vessel coolant mass depletion during a 5% SBLOCA in the Semiscale Mod-2C facility

International Nuclear Information System (INIS)

Shaw, R.A.; Loomis, G.G.

1985-01-01

Experimental results are presented from two 5% small-break loss-of-coolant accident (SBLOCA) simulations in the Semiscale Mod-2C facility. In performing the simulated 5% SBLOCAs, boundary conditions scaled from a pressurized water reactor (PWR) were used. The experiment was run with initial conditions typical of a PWR (15.6 MPa pressure and 35 K core differential temperature). The Mod-2C facility represents the state-of-the-art in small facilities scaled from PWRs. Phenomena which occurred during the transient included: primary fluid saturation (change from subcooled to saturated blowdown), break uncovery (a centerline break was simulated), condensation-induced liquid hold-up in the steam generator primary tubes, pump suction liquid seal formation and core level depression with resulting core rod temperature excursion, pump suction liquid seal clearance, loop fluid mass redistribution, and gradual core rewet. The influence of core bypass flow is also discussed. 11 refs., 13 figs

Environmental and climate research programme 1988/89

International Nuclear Information System (INIS)

1987-01-01

The Study Group of the Large-scale Research Institutes (AGF) has been reporting on these projects since 1972, in its programme for 'Environmental and Climate Research'. The programme, which is worked out by the AGF's Coordination Office for Environmental Research, is closely connected with the programmes of the Federal Government; it is revised and updated periodically by the AGF's Coordination Committees for 'Environmental Research' and 'Climate Research'. The 1988/89 programme gives an up-to-date overview of research projects in the field of 'Research and Technology for Health, Nutrition and the Environment' financed with the AGF programme budget of 1988. At the same time, however, it also documents projects of other areas of the programme concerned with environmental issues. Development trends are also discernible in the specification of the goals for 1989. The figures mentioned in the present programme are not comparable with those of earlier programmes, owing to inclusion of the programme section concerned with issues of climate, and to structural changes. (orig./KW) [de

Comparison and Evaluation of Annual NDVI Time Series in China Derived from the NOAA AVHRR LTDR and Terra MODIS MOD13C1 Products.

Science.gov (United States)

Guo, Xiaoyi; Zhang, Hongyan; Wu, Zhengfang; Zhao, Jianjun; Zhang, Zhengxiang

2017-06-06

Time series of Normalized Difference Vegetation Index (NDVI) derived from multiple satellite sensors are crucial data to study vegetation dynamics. The Land Long Term Data Record Version 4 (LTDR V4) NDVI dataset was recently released at a 0.05 × 0.05° spatial resolution and daily temporal resolution. In this study, annual NDVI time series that are composited by the LTDR V4 and Moderate Resolution Imaging Spectroradiometer (MODIS) NDVI datasets (MOD13C1) are compared and evaluated for the period from 2001 to 2014 in China. The spatial patterns of the NDVI generally match between the LTDR V4 and MOD13C1 datasets. The transitional zone between high and low NDVI values generally matches the boundary of semi-arid and sub-humid regions. A significant and high coefficient of determination is found between the two datasets according to a pixel-based correlation analysis. The spatially averaged NDVI of LTDR V4 is characterized by a much weaker positive regression slope relative to that of the spatially averaged NDVI of the MOD13C1 dataset because of changes in NOAA AVHRR sensors between 2005 and 2006. The measured NDVI values of LTDR V4 were always higher than that of MOD13C1 in western China due to the relatively lower atmospheric water vapor content in western China, and opposite observation appeared in eastern China. In total, 18.54% of the LTDR V4 NDVI pixels exhibit significant trends, whereas 35.79% of the MOD13C1 NDVI pixels show significant trends. Good agreement is observed between the significant trends of the two datasets in the Northeast Plain, Bohai Economic Rim, Loess Plateau, and Yangtze River Delta. By contrast, the datasets contrasted in northwestern desert regions and southern China. A trend analysis of the regression slope values according to the vegetation type shows good agreement between the LTDR V4 and MOD13C1 datasets. This study demonstrates the spatial and temporal consistencies and discrepancies between the AVHRR LTDR and MODIS MOD13C1 NDVI

Thermal-hydraulic modelling of the SAFARI-1 research reactor using RELAP/SCDAPSIM/MOD3.4

International Nuclear Information System (INIS)

Sekhri, Abdelkrim; Graham, Andy; D'Arcy, Alan; Oliver, Melissa

2008-01-01

The SAFARI-1 reactor is a tank-in-pool MTR type research reactor operated at a nominal core power of 20 MW. It operates exclusively in the single phase liquid water regime with nominal water and fuel temperatures not exceeding 100 deg. C. RELAP/SCDAPSIM/MOD3.4 is a Best Estimate Code for light water reactors as well as for low pressure transients, as part of the code validation was done against low pressure facilities and research reactor experimental data. The code was used to simulate SAFARI-1 in normal and abnormal operation and validated against the experimental data in the plant and was used extensively in the upgrading of the Safety Analysis Report (SAR) of the reactor. The focus of the following study is the safety analysis of the SAFARI-1 research reactor and describes the thermal hydraulic modelling and analysis approach. Particular emphasis is placed on the modelling detail, the application of the no-boiling rule and predicting the Onset of Nucleate Boiling and Departure from Nucleate Boiling under Loss of Flow conditions. Such an event leads the reactor to switch to a natural convection regime which is an adequate mode to maintain the clad and fuel temperature within the safety margin. It is shown that the RELAP/SCDAPSIM/MOD3.4 model can provide accurate predictions as long as the clad temperature remains below the onset of nucleate boiling temperature and the DNB ratio is greater than 2. The results are very encouraging and the model is shown to be appropriate for the analysis of SAFARI-1 research reactor. (authors)

South African southern ocean research programme

CSIR Research Space (South Africa)

SASCAR

1987-01-01

Full Text Available This document describes the South African National Antarctic Research Programme's (SANARP) physical, chemical and biological Southern Ocean research programme. The programme has three main components: ecological studies of the Prince Edward Islands...

Neutral particle diagnostics for ALCATOR C-Mod

International Nuclear Information System (INIS)

Kurz, C.; Fiore, C.L.

1990-01-01

The ALCATOR C-Mod experiment will be equipped with two PPPL charge exchange neutral particle analyzers (CENAs), one of which views the plasma tangentially (R tan /R 0 =1.05), whereas the second has a horizontally scannable sight line (0≤R tan /R 0 ≤0.51). The perpendicularly viewing CENA will be capable of analyzing neutrals up to 600 keV amu for up to three separate species simultaneously. Thus high-energy tails can be observed together with the bulk ion temperature. The operation of both analyzers will allow simultaneous measurements from both the perpendicular and tangential chords. The CENAs will be used to study the effect of ICRF heating on the ion energy distribution with emphasis on the high-energy tail. A Fokker--Planck code (FPPRF) [Hammett, Ph.D. thesis, Princeton (1986)] is used to assess the appropriate operating regime of the analyzer (n≤4x10 20 m -3 for T i =2 keV, for Maxwellian ion energy distribution). The experimental design and computer simulations will be detailed

A Conceptual Approach to Teaching Object-Orientation to C Programmers

DEFF Research Database (Denmark)

Madsen, Ole Lehrmann; Torgersen, Mads; Røn, Henrik

1998-01-01

This paper describes experiences from a three-day course held as part of a collaborative research project, in which object-oriented programming was taught to a group of engineers who were all proficient C programmers. Our approach to teaching object-oriented programming focuses on conceptual...... modeling, emphasizing that object-orientation is not a bag of solutions and technology; rather, object-orientation is a means to understand, describe (model) and communicate. The paper describes a general approach to teaching object-oriented programming to C-programmers and reports on the experience from...

Control of internal transport barriers on Alcator C-Mod

International Nuclear Information System (INIS)

Fiore, C.L.; Bonoli, P.T.; Ernst, D.R.; Hubbard, A.E.; Greenwald, M.J.; Lynn, A.; Marmar, E.S.; Phillips, P.; Redi, M.H.; Rice, J.E.; Wolfe, S.M.; Wukitch, S.J.; Zhurovich, K.

2004-01-01

Recent studies of internal transport and double transport barrier regimes in the Alcator C-Mod [I. H. Hutchinson et al., Phys. Plasmas 1, 1511 (1994)] have explored the limits for forming, maintaining, and controlling these plasmas. The C-Mod provides a unique platform for studying such discharges: the ions and electrons are tightly coupled by collisions and the plasma has no internal particle or momentum sources. The double-barrier mode comprised of an edge barrier with an internal transport barrier (ITB) can be induced at will using off-axis ion cyclotron range of frequency (ICRF) injection on either the low or high field side of the plasma with either of the available ICRF frequencies (70 or 80 MHz). When an enhanced D α high confinement mode (EDA H-mode) is accessed in Ohmic plasmas, the double barrier ITB forms spontaneously if the H-mode is sustained for ∼2 energy confinement times. The ITBs formed in both Ohmic and ICRF heated plasmas are quite similar regardless of the trigger method. They are characterized by strong central peaking of the electron density, and a reduction of the core particle and energy transport. The control of impurity influx and heating of the core plasma in the presence of the ITB have been achieved with the addition of central ICRF power in both the Ohmic H-mode and ICRF induced ITBs. The radial location of the particle transport barrier is dependent on the toroidal magnetic field but not on the location of the ICRF resonance. A narrow region of decreased electron thermal transport, as determined by sawtooth heat pulse analysis, is found in these plasmas as well. Transport analysis indicates that a reduction of the particle diffusivity in the barrier region allows the neoclassical pinch to drive the density and impurity accumulation in the plasma center. An examination of the gyrokinetic stability at the trigger time for the ITB suggests that the density and temperature profiles are inherently stable to ion temperature gradient and

Mod i ledelse

DEFF Research Database (Denmark)

Mellon, Karsten

2016-01-01

Mod i ledelse er en efterspurgt vare i offentligt regi som modsvar på stigende kompleksitet og pres. Men hvad er ’mod i ledelse’ – og er du selv en modig leder?......Mod i ledelse er en efterspurgt vare i offentligt regi som modsvar på stigende kompleksitet og pres. Men hvad er ’mod i ledelse’ – og er du selv en modig leder?...

SCDAP/RELAP5/MOD3 code development and assessment

International Nuclear Information System (INIS)

Allison, C.M.; Heath, C.H.; Siefken, L.J.; Hohorst, J.K.

1991-01-01

The SCDAP/RELAP5/MOD3 computer code is designed to describe the overall reactor coolant system (RCS) thermal-hydraulic response, core damage progression, and fission product release and transport during severe accidents. The code is being developed at the Idaho National Engineering Laboratory (INEL) under the primary sponsorship of the Office of Nuclear Regulatory Research of the Nuclear Regulatory Commission (NRC). SCDAP/RELAP5/MOD3, created in January, 1991, is the result of merging RELAP5/MOD3 with SCDAP and TRAP-MELT models from SCDAP/RELAP5/MOD2.5. The RELAP5 models calculate the overall RCS thermal-hydraulics, control system interactions, reactor kinetics, and the transport of noncondensible gases, fission products, and aerosols. The SCDAP models calculate the damage progression in the core structures, the formation, heatup, and melting of debris, and the creep rupture failure of the lower head and other RCS structures. The TRAP-MELT models calculate the deposition of fission products upon aerosols or structural surfaces; the formation, growth, or deposition of aerosols; and the evaporation of species from surfaces. The systematic assessment of modeling uncertainties in SCDAP/RELAP5 code is currently underway. This assessment includes (a) the evaluation of code-to-data comparisons using stand-alone SCDAP and SCDAP/RELAP5/MOD3, (b) the estimation of modeling and experimental uncertainties, and (c) the determination of the influence of those uncertainties on predicted severe accident behavior

Tungsten nano-tendril growth in the Alcator C-Mod divertor

International Nuclear Information System (INIS)

Wright, G.M.; Brunner, D.; Labombard, B.; Lipschultz, B.; Terry, J.L.; Whyte, D.G.; Baldwin, M.J.; Doerner, R.P.

2012-01-01

Growth of tungsten nano-tendrils (‘fuzz’) has been observed for the first time in the divertor region of a high-power density tokamak experiment. After 14 consecutive helium L-mode discharges in Alcator C-Mod, the tip of a tungsten Langmuir probe at the outer strike point was fully covered with a layer of nano-tendrils. The thickness of the individual nano-tendrils (50–100 nm) and the depth of the layer (600 ± 150 nm) are consistent with observations from experiments on linear plasma devices. The observation of tungsten fuzz in a tokamak may have important implications for material erosion, dust formation, divertor lifetime and tokamak operations in next-step devices. (letter)

Fast Wave Transmission Measurements on Alcator C-Mod

Science.gov (United States)

Reardon, J.; Bonoli, P. T.; Porkolab, M.; Takase, Y.; Wukitch, S. J.

1997-11-01

Data are presented from an array of single-turn loop probes newly installed on the inner wall of C-Mod, directly opposite one of the two fast-wave antennas. The 8-loop array extends 32^circ in the toroidal direction at the midplane and can distinguish electromagnetic from electrostatic modes. Data are acquired by 1GHz digitizer, spectrum analyzer, and RF detector circuit. Phase measurements during different heating scenarios show evidence of both standing and travelling waves. The measurement of toroidal mode number N_tor (conserved under the assumption of axisymmetry) is used to guide the toroidal full-wave code TORIC(Brambilla, M., IPP Report 5/66, February 1996). Amplitude measurements show modulation both by Type III ELMs and sawteeth; the observed sawtooth modulation may be interpreted as due to changes in central absorption. The amplitude of tildeB_tor measured at the inner wall is compared to the prediction of TORIC.

Influence of boronization on operation with high-Z plasma facing components in Alcator C-Mod

International Nuclear Information System (INIS)

Lipschultz, B.; Lin, Y.; Marmar, E.S.; Whyte, D.G.; Wukitch, S.; Hutchinson, I.H.; Irby, J.; LaBombard, B.; Reinke, M.L.; Terry, J.L.; Wright, G.

2007-01-01

We report the results of operation of Alcator C-Mod with all high-Z molybdenum plasma facing component (PFC) surfaces. Without boron-coated PFCs energy confinement was poor (H ITER,89 ∼ 1) due to high core molybdenum (n Mo /n e ≤ 0.1%) and radiation. After applying boron coatings, n Mo /n e was reduced by a factor of 10-20 with H ITER,89 approaching 2. Results of between-discharge boronization, localized at various major radii, point towards important molybdenum source regions being small, outside the divertor, and due to RF-sheath-rectification. Boronization also has a significant effect on the plasma startup phase lowering Z eff , radiation, and lowering the runaway electron damage. The requirement of low-Z coatings over at least a fraction of the Mo PFCs in C-Mod for best performance together with the larger than expected D retention in Mo, give impetus for further high-Z PFC investigations to better predict the performance of un-coated tungsten surfaces in ITER and beyond

Experimental/theoretical comparisons of the turbulence in the scrape-off-layers of Alcator C-Mod, DIII-D, and NSTX

International Nuclear Information System (INIS)

Terry, J.L. . E-mail : terry@psfc.mit.edu; Zweben, S.J.; Rudakov, D.L.

2003-01-01

The intermittent turbulent transport in the scrape-off-layers of Alcator C-Mod, DIII-D, and NSTX is studied experimentally. On DIII-D the fluctuations of both density and temperature have strongly non-Gaussian statistics, and events with amplitudes above 10 times the mean level are responsible for large fractions of the net particle and heat transport, indicating the importance of turbulence on the transport. In C-Mod and NSTX the turbulence is imaged with a very high density of spatial measurements. The 2-D structure and dynamics of emission from a localized gas puff are observed, and intermittent features (also sometimes called 'blobs') are typically seen. On DIII-D the turbulence is imaged using BES and similar intermittent features are seen. The dynamics of these intermittent features are discussed. The experimental observations are compared with numerical simulations of edge turbulence. The electromagnetic turbulence in a 3-D geometry is computed using non-linear plasma fluid equations. The wavenumber spectra in the poloidal dimension of the simulations are in reasonable agreement with those of the C-Mod experimental images once the response of the optical system is accounted for. The resistive ballooning mode is the dominant linear instability in the simulations. (author)

Boundary plasma heat flux width measurements for poloidal magnetic fields above 1 Tesla in the Alcator C-Mod tokamak

Science.gov (United States)

Brunner, Dan; Labombard, Brian; Kuang, Adam; Terry, Jim; Alcator C-Mod Team

2017-10-01

The boundary heat flux width, along with the total power flowing into the boundary, sets the power exhaust challenge for tokamaks. A multi-machine boundary heat flux width database found that the heat flux width in H-modes scaled inversely with poloidal magnetic field (Bp) and was independent of machine size. The maximum Bp in the database was 0.8 T, whereas the ITER 15 MA, Q =10 scenario will be 1.2 T. New measurements of the boundary heat flux width in Alcator C-Mod extend the international database to plasmas with Bp up to 1.3 T. C-Mod was the only experiment able to operate at ITER-level Bp. These new measurements are from over 300 plasma shots in L-, I-, and EDA H-modes spanning essentially the whole operating space in C-Mod. We find that the inverse-Bp dependence of the heat flux width in H-modes continues to ITER-level Bp, further reinforcing the empirical projection of 500 μm heat flux width for ITER. We find 50% scatter around the inverse-Bp scaling and are searching for the `hidden variables' causing this scatter. Supported by USDoE award DE-FC02-99ER54512.

Algebraic Structures on MOD Planes

OpenAIRE

Kandasamy, Vasantha; Ilanthenral, K.; Smarandache, Florentin

2015-01-01

Study of MOD planes happens to a very recent one. In this book, systematically algebraic structures on MOD planes like, MOD semigroups, MOD groups and MOD rings of different types are defined and studied. Such study is innovative for a large four quadrant planes are made into a small MOD planes. Several distinct features enjoyed by these MOD planes are defined, developed and described.

Vérification de programmes OCaml fortement impératifs avec Why3

OpenAIRE

Filliâtre , Jean-Christophe; Pereira , Mário; Melo De Sousa , Simão

2018-01-01

International audience; Cet article présente une méthodologie pour prouver des programmes OCaml fortement impératifs avec l'outil de vérification déductive Why3. Pour un programme OCaml donné, un modèle mémoire spécifique est construit et on vérifie un programme Why3 qui le mani-pule. Une fois la preuve terminée, on utilise la capacité de Why3 à traduire ses programmes vers le langage OCaml, tout en remplaçant les opérations sur le modèle mémoire par les opérations correspondantes sur des typ...

Modelling of advanced tokamak physics scenarios in ALCATOR C-Mod

International Nuclear Information System (INIS)

Bonoli, P.T.; Porkolab, M.; Ramos, J.

2001-01-01

Advanced tokamak modes of operation in Alcator C-Mod have been investigated using a simulation model which combines an MHD equilibrium and current profile control calculation with an ideal MHD stability analysis. Stable access to high β t operating modes with reversed shear current density profiles has been demonstrated using 2.4-3.0 MW of off-axis lower hybrid current drive (LHCD). Here β t =2μ 0 (p)/B 2 0 is the volume averaged toroidal plasma beta. Current profile control at the β-limit and beyond has also been demonstrated. The effects of LH power level as well as changes in the profiles of density and temperature on shear reversal radius have been quantified and are discussed. (author)

Energetic ion loss detector on the Alcator C-Mod tokamak.

Science.gov (United States)

Pace, D C; Granetz, R S; Vieira, R; Bader, A; Bosco, J; Darrow, D S; Fiore, C; Irby, J; Parker, R R; Parkin, W; Reinke, M L; Terry, J L; Wolfe, S M; Wukitch, S J; Zweben, S J

2012-07-01

A scintillator-based energetic ion loss detector has been successfully commissioned on the Alcator C-Mod tokamak. This probe is located just below the outer midplane, where it captures ions of energies up to 2 MeV resulting from ion cyclotron resonance heating. After passing through a collimating aperture, ions impact different regions of the scintillator according to their gyroradius (energy) and pitch angle. The probe geometry and installation location are determined based on modeling of expected lost ions. The resulting probe is compact and resembles a standard plasma facing tile. Four separate fiber optic cables view different regions of the scintillator to provide phase space resolution. Evolving loss levels are measured during ion cyclotron resonance heating, including variation dependent upon individual antennae.

Molybdenum emission from impurity-induced m= 1 snake-modes on the Alcator C-Mod tokamak

Energy Technology Data Exchange (ETDEWEB)

Delgado-Aparicio, L. [Princeton Plasma Physics Laboratory, Princeton, New Jersey 08540 (United States); MIT - Plasma Science and Fusion Center, Cambridge, Massachusetts 02139 (United States); Bitter, M.; Gates, D.; Hill, K.; Pablant, N. [Princeton Plasma Physics Laboratory, Princeton, New Jersey 08540 (United States); Granetz, R.; Reinke, M.; Podpaly, Y.; Rice, J. [MIT - Plasma Science and Fusion Center, Cambridge, Massachusetts 02139 (United States); Beiersdorfer, P. [Lawrence Livermore National Laboratory, Livermore, California 94550 (United States); Sugiyama, L. [MIT - Laboratory for Nuclear Science, Cambridge, Massachusetts 02139 (United States)

2012-10-15

A suite of novel high-resolution spectroscopic imaging diagnostics has facilitated the identification and localization of molybdenum impurities as the main species during the formation and lifetime of m= 1 impurity-induced snake-modes on Alcator C-Mod. Such measurements made it possible to infer, for the first time, the perturbed radiated power density profiles from which the impurity density can be deduced.

Distribution of the type III DNA methyltransferases modA, modB and modD among Neisseria meningitidis genotypes: implications for gene regulation and virulence.

Science.gov (United States)

Tan, Aimee; Hill, Dorothea M C; Harrison, Odile B; Srikhanta, Yogitha N; Jennings, Michael P; Maiden, Martin C J; Seib, Kate L

2016-02-12

Neisseria meningitidis is a human-specific bacterium that varies in invasive potential. All meningococci are carried in the nasopharynx, and most genotypes are very infrequently associated with invasive meningococcal disease; however, those belonging to the 'hyperinvasive lineages' are more frequently associated with sepsis or meningitis. Genome content is highly conserved between carriage and disease isolates, and differential gene expression has been proposed as a major determinant of the hyperinvasive phenotype. Three phase variable DNA methyltransferases (ModA, ModB and ModD), which mediate epigenetic regulation of distinct phase variable regulons (phasevarions), have been identified in N. meningitidis. Each mod gene has distinct alleles, defined by their Mod DNA recognition domain, and these target and methylate different DNA sequences, thereby regulating distinct gene sets. Here 211 meningococcal carriage and >1,400 disease isolates were surveyed for the distribution of meningococcal mod alleles. While modA11-12 and modB1-2 were found in most isolates, rarer alleles (e.g., modA15, modB4, modD1-6) were specific to particular genotypes as defined by clonal complex. This suggests that phase variable Mod proteins may be associated with distinct phenotypes and hence invasive potential of N. meningitidis strains.

Evaluation of the Radiation Protection Research Programmes (1980-1984 and 1985-1989)

International Nuclear Information System (INIS)

Wambersie, A.; Akehurst, R.L.; Marcus, F.; Proukakis, C.; Rajewsky, M.F.; Sinclair, W.K.

1989-07-01

The commission appointed a panel of six independent experts to evaluate its Radiation Protection Research Programmes (1980-84 and 1985-89). The evaluation was carried out according to the guidelines specified by the Council Resolution on the evaluation of R and D programmes (O.J. C213, 09.08.1983), and further developed by the Commission's Plan of Action on Evaluation (O.J. C2(1), 06.01.1987). The scientific evaluation was carried out separately for each of the six sectors of the programme ant the post-Chernobyl actions. The management and socio-economic evaluation was based on discussions with Commission and national officials, programme contractors and site visits to laboratories in the member states. A questionnaire was used to survey scientists involved in the programme

Fluctuating zonal flows in the I-mode regime in Alcator C-Mod

Energy Technology Data Exchange (ETDEWEB)

Cziegler, I.; Diamond, P. H.; Fedorczak, N.; Manz, P.; Tynan, G. R.; Xu, M. [Center for Momentum Transport and Flow Organization, University of California, San Diego, La Jolla, California 92093 (United States); Churchill, R. M.; Hubbard, A. E.; Lipschultz, B.; Sierchio, J. M.; Terry, J. L.; Theiler, C. [Plasma Science and Fusion Center, Massachusetts Institute of Technology, Cambridge, Massachusetts 02138 (United States)

2013-05-15

Velocity fields and density fluctuations of edge turbulence are studied in I-mode [F. Ryter et al., Plasma Phys. Controlled Fusion 40, 725 (1998)] plasmas of the Alcator C-Mod [I. H. Hutchinson et al., Phys. Plasmas 1, 1511 (1994)] tokamak, which are characterized by a strong thermal transport barrier in the edge while providing little or no barrier to the transport of both bulk and impurity particles. Although previous work showed no clear geodesic-acoustic modes (GAM) on C-Mod, using a newly implemented, gas-puff-imaging based time-delay-estimate velocity inference algorithm, GAM are now shown to be ubiquitous in all I-mode discharges examined to date, with the time histories of the GAM and the I-mode specific [D. Whyte et al., Nucl. Fusion 50, 105005 (2010)] Weakly Coherent Mode (WCM, f = 100–300 kHz, Δf/f≈0.5, and k{sub θ}≈1.3 cm{sup −1}) closely following each other through the entire duration of the regime. Thus, the I-mode presents an example of a plasma state in which zero frequency zonal flows and GAM continuously coexist. Using two-field (density-velocity and radial-poloidal velocity) bispectral methods, the GAM are shown to be coupled to the WCM and to be responsible for its broad frequency structure. The effective nonlinear growth rate of the GAM is estimated, and its comparison to the collisional damping rate seems to suggest a new view on I-mode threshold physics.

Kinetic modeling of divertor heat load fluxes in the Alcator C-Mod and DIII-D tokamaks

Energy Technology Data Exchange (ETDEWEB)

Pankin, A. Y. [Tech-X Corporation, Boulder, Colorado 80303 (United States); Rafiq, T.; Kritz, A. H. [Department of Physics, Lehigh University, Bethlehem, Pennsylvania 18015 (United States); Park, G. Y. [National Fusion Research Institute, Daejeon, 305-333 (Korea, Republic of); Chang, C. S.; Ku, S. [Princeton Plasma Physics Laboratory, Princeton, New Jersey 08540 (United States); Brunner, D.; Hughes, J. W.; LaBombard, B.; Terry, J. L. [MIT Plasma Science and Fusion Center, Cambridge, Massachusetts 02139 (United States); Groebner, R. J. [General Atomics, San Diego, California 92121 (United States)

2015-09-15

The guiding-center kinetic neoclassical transport code, XGC0 [Chang et al., Phys. Plasmas 11, 2649 (2004)], is used to compute the heat fluxes and the heat-load width in the outer divertor plates of Alcator C-Mod and DIII-D tokamaks. The dependence of the width of heat-load fluxes on neoclassical effects, neutral collisions, and anomalous transport is investigated using the XGC0 code. The XGC0 code includes realistic X-point geometry, a neutral source model, the effects of collisions, and a diffusion model for anomalous transport. It is observed that the width of the XGC0 neoclassical heat-load is approximately inversely proportional to the total plasma current I{sub p.} The scaling of the width of the divertor heat-load with plasma current is examined for an Alcator C-Mod discharge and four DIII-D discharges. The scaling of the divertor heat-load width with plasma current is found to be weaker in the Alcator C-Mod discharge compared to scaling found in the DIII-D discharges. The effect of neutral collisions on the 1/I{sub p} scaling of heat-load width is shown not to be significant. Although inclusion of poloidally uniform anomalous transport results in a deviation from the 1/I{sub p} scaling, the inclusion of the anomalous transport that is driven by ballooning-type instabilities results in recovering the neoclassical 1/I{sub p} scaling. The Bohm or gyro-Bohm scalings of anomalous transport do not strongly affect the dependence of the heat-load width on plasma current. The inclusion of anomalous transport, in general, results in widening the width of neoclassical divertor heat-load and enhances the neoclassical heat-load fluxes on the divertor plates. Understanding heat transport in the tokamak scrape-off layer plasmas is important for strengthening the basis for predicting divertor conditions in ITER.

Integrated uncertainty analysis using RELAP/SCDAPSIM/MOD4.0

International Nuclear Information System (INIS)

Perez, M.; Reventos, F.; Wagner, R.; Allison, C.

2009-01-01

The RELAP/SCDAPSIM/MOD4.0 code, designed to predict the behavior of reactor systems during normal and accident conditions, is being developed as part of an international nuclear technology Software Development and Training Program (SDTP). RELAP/SCDAPSIM/MOD4.0, which is the first version of RELAP5 completely rewritten to FORTRAN 90/95/2000 standards, uses the publicly available RELAP5 and SCDAP models in combination with (a) advanced programming and numerical techniques, (b) advanced SDTP-member-developed models for LWR, HWR, and research reactor analysis, and (c) a variety of other member-developed computational packages. One such computational package is an integrated uncertainty analysis package being developed jointly by the Technical University of Catalunya (UPC) and Innovative Systems Software (ISS). The integrated uncertainty analysis approach used in the package uses the following steps: 1. Selection of the plant; 2. Selection of the scenario; 3. Selection of the safety criteria; 4. Identification and ranking of the relevant phenomena based on the safety criteria; 5. Selection of the appropriate code parameters to represent those phenomena; 6. Association of uncertainty by means of Probability Distribution Functions (PDFs) for each selected parameter; 7. Random sampling of the selected parameters according to its PDF and performing multiple computer runs to obtain uncertainty bands with a certain percentile and confidence level; 8. Processing the results of the multiple computer runs to estimate the uncertainty bands for the computed quantities associated with the selected safety criteria. The first four steps are performed by the user prior to the RELAP/SCDAPSIM/MOD4.0 analysis. The remaining steps are included with the MOD4.0 integrated uncertainty analysis (IUA) package. This paper briefly describes the integrated uncertainty analysis package including (a) the features of the package, (b) the implementation of the package into RELAP/SCDAPSIM/MOD4.0, and

Two dimensional radiated power diagnostics on Alcator C-Mod

International Nuclear Information System (INIS)

Reinke, M. L.; Hutchinson, I. H.

2008-01-01

The radiated power diagnostics for the Alcator C-Mod tokamak have been upgraded to measure two dimensional structure of the photon emissivity profile in order to investigate poloidal asymmetries in the core radiation. Commonly utilized unbiased absolute extreme ultraviolet (AXUV) diode arrays view the plasma along five different horizontal planes. The layout of the diagnostic set is shown and the results from calibrations and recent experiments are discussed. Data showing a significant, 30%-40%, inboard/outboard emissivity asymmetry during ELM-free H-mode are presented. The ability to use AXUV diode arrays to measure absolute radiated power is explored by comparing diode and resistive bolometer-based emissivity profiles for highly radiative L-mode plasmas seeded with argon. Emissivity profiles match in the core but disagree radially outward resulting in an underprediction of P rad of nearly 50% by the diodes compared to P rad determined using resistive bolometers.

High speed movies of turbulence in Alcator C-Mod

International Nuclear Information System (INIS)

Terry, J.L.; Zweben, S.J.; Bose, B.; Grulke, O.; Marmar, E.S.; Lowrance, J.; Mastrocola, V.; Renda, G.

2004-01-01

A high speed (250 kHz), 300 frame charge coupled device camera has been used to image turbulence in the Alcator C-Mod Tokamak. The camera system is described and some of its important characteristics are measured, including time response and uniformity over the field-of-view. The diagnostic has been used in two applications. One uses gas-puff imaging to illuminate the turbulence in the edge/scrape-off-layer region, where D 2 gas puffs localize the emission in a plane perpendicular to the magnetic field when viewed by the camera system. The dynamics of the underlying turbulence around and outside the separatrix are detected in this manner. In a second diagnostic application, the light from an injected, ablating, high speed Li pellet is observed radially from the outer midplane, and fast poloidal motion of toroidal striations are seen in the Li + light well inside the separatrix

Internal transport barrier production and control in Alcator C-Mod

Energy Technology Data Exchange (ETDEWEB)

Fiore, C L [Plasma Science and Fusion Center, Massachusetts Institute of Technology, Cambridge, MA 02139 (United States); Bonoli, P T [Plasma Science and Fusion Center, Massachusetts Institute of Technology, Cambridge, MA 02139 (United States); Ernst, D R [Plasma Science and Fusion Center, Massachusetts Institute of Technology, Cambridge, MA 02139 (United States); Greenwald, M J [Plasma Science and Fusion Center, Massachusetts Institute of Technology, Cambridge, MA 02139 (United States); Marmar, E S [Plasma Science and Fusion Center, Massachusetts Institute of Technology, Cambridge, MA 02139 (United States); Redi, M H [Princeton Plasma Physics Laboratory, Princeton, NJ (United States); Rice, J E [Plasma Science and Fusion Center, Massachusetts Institute of Technology, Cambridge, MA 02139 (United States); Wukitch, S J [Plasma Science and Fusion Center, Massachusetts Institute of Technology, Cambridge, MA 02139 (United States); Zhurovich, K [Plasma Science and Fusion Center, Massachusetts Institute of Technology, Cambridge, MA 02139 (United States)

2004-12-01

Internal transport barriers (ITBs), marked by a steep density profile, even stronger peaking in the pressure profile and reduction of core transport are obtained in Alcator C-Mod. They are induced by the use of off-axis D(H) ICRF (ion cyclotron range of frequencies) power deposition. They also arise spontaneously in Ohmic H-mode plasmas once the H-mode lasts for several energy confinement times. Recent studies have explored the limits for forming, maintaining and controlling these plasmas. The C-Mod provides a unique platform for studying such discharges: the high density (up to 8 x 10{sup 20} m{sup -3}) causes the ions and electrons to be tightly coupled by collisions with T{sub i}/T{sub e} = 1, and the plasma has no internal particle or momentum sources. The ITBs formed in both Ohmic and ICRF heated plasmas are quite similar regardless of the trigger method. Control of impurity influx and heating of the core plasma in the presence of the ITB have been achieved with the addition of central ICRF power, in both Ohmic H-mode and ICRF induced ITBs. Control of the radial location of the transport barrier is achieved through manipulation of the toroidal magnetic field and plasma current. A narrow region of decreased electron thermal transport, as determined by sawtooth heat pulse analysis, is found in these plasmas as well. Transport analysis indicates that reduction of the particle diffusivity in the barrier region allows the neoclassical pinch to drive the density and impurity accumulation in the plasma centre. Examination of the gyro-kinetic stability indicates that the density and temperature profiles of the plasma core are inherently stable to long-wavelength drift mode driven turbulence at the onset time of the ITB, but that the increasing density gradients cause the trapped electron mode to play a role in providing a control mechanism to ultimately limit the density and impurity rise in the plasma centre.

Mechanisms for ITB formation and control in Alcator C-Mod identified through gyrokinetic simulations of TEM turbulence

International Nuclear Information System (INIS)

Ernst, D.R.; Basse, N.; Bonoli, P.T.; Catto, P.J.; Fiore, C.L.; Greenwald, M.; Hubbard, A.E.; Marmar, E.S.; Porkolab, M.; Rice, J.E.; Zeller, K.; Zhurovich, K.; Dorland, W.

2005-01-01

Internal particle and thermal energy transport barriers are produced in Alcator C-Mod with off-axis ICRF heating, with core densities exceeding 10 21 m -3 , without core fueling, and with little change in the temperature profile. Applying on-axis ICRF heating controls the core density gradient and rate of rise. The present study employs linear and nonlinear gyrokinetic simulations of trapped electron mode (TEM) turbulence to explore mechanisms for ITB formation and control in Alcator C-Mod ITB experiments. Anomalous pinches are found to be negligible in our simulations; further, the collisional Ware pinch is sufficient to account for the slow density rise, lasting many energy confinement times. The simulations have revealed new nonlinear physics of TEM turbulence. The critical density gradient for onset of TEM turbulent transport is nonlinearly up-shifted by zonal flows. As the density profile peaks, during ITB formation, this nonlinear critical gradient is eventually exceeded, and the turbulent particle diffusivity from GS2 gyrokinetic simulations matches the particle diffusivity from transport analysis, within experimental errors. A stable equilibrium is then established when the TEM turbulent diffusion balances the Ware pinch in the ITB. This equilibrium is sensitive to temperature through gyroBohm scaling of the TEM turbulent transport, and the collisionality dependence of the neoclassical pinch, providing for control of the density rate of rise with on-axis RF heating. With no core particle fueling, and ∼1 mm between density spatial channels, the C-Mod experiments provide a nearly ideal test bed for particle transport studies. The pure TEM is the only unstable drift mode in the ITB, producing particle transport driven by the density gradient. (author)

Finnish Fusion Research Programme Yearbook 1993-1994

International Nuclear Information System (INIS)

Karttunen, S.; Paettikangas, T.

1995-05-01

Finnish Fusion Research Programme (FFUSION) is one of the national energy research programmes funded by the Ministry of Trade and Industry and from 1995 by TEKES. National organization for fusion research is necessary for efficient and successful participation in international fusion programmes. FFUSION programme serves well for this purpose and it made possible to establish relations and the dialogue with the European Fusion Programme. The process led to the Finnish Association Euratom-TEKES in early 1995. The first period of the FFUSION programme (1993-1994) was preparation for the association to the Community Programme. The strategy was to emphasize fusion technology parallel with the basic fusion and plasma physics and to activate the related Finnish industry to collaborate and participate in the FFUSION programme and later in the European Fusion Programme. The key element in the strategy is the focusing our fairly small R and D effort to a few topics, which increases possibilities to be competitive in Europe. The physics programme in FFUSION deals mainly with theoretical and computational studies of radio-frequency heating in tokamak plasmas. Technology programme started with prestudies in 1993 and it concentrates into two areas: fusion reactor materials and remote handling systems. (8 figs., 3 tabs.)

Visible Spectrometer at the Compact Toroid Injection Experiment, the Sustained Spheromak Plasma Experiment and the Alcator C-Mod Tokamak for Doppler Width and Shift Measurements

Energy Technology Data Exchange (ETDEWEB)

Graf, A; Howard, S; Horton, R; Hwang, D; May, M; Beiersdorfer, P; McLean, H; Terry, J

2006-05-15

A novel Doppler spectrometer is currently being used for ion or neutral velocity and temperature measurements on the Alcator C-Mod Tokamak. The spectrometer has an f/No. of {approx}3.1 and is appropriate for visible light (3500-6700 {angstrom}). The full width at half maximum from a line emitting calibration source has been measured to be as small as 0.4 {angstrom}. The ultimate time resolution is line brightness light limited and on the order of ms. A new photon efficient detector is being used for the setup at C-Mod. Time resolution is achieved by moving the camera during a plasma discharge in a perpendicular direction through the dispersion plane of the spectrometer causing a vertical streaking across the camera face. Initial results from C-Mod as well as previous measurements from the Compact Toroid Injection Experiment (CTIX) and the Sustained Spheromak Plasma Experiment (SSPX) are presented.

Dissipative divertor operation in the Alcator C-Mod tokamak

International Nuclear Information System (INIS)

Lipschultz, B.; Goetz, J.; LaBombard, B.; McCracken, G.M.; Terry, J.L.; Graf, M.; Granetz, R.S.; Jablonski, D.; Kurz, C.; Niemczewski, A.; Snipes, J.

1995-01-01

The achievement of large volumetric power losses (dissipation) in the Alcator C-Mod divertor region is demonstrated in two operational modes: radiative divertor and detached divertor. During radiative divertor operation, the fraction of SOL power lost by radiation is P R /P SOL ∼0.8 with single null plasmas, n e 20 m -3 and I p e,div ≤6x10 20 m -3 . As the divertor radiation and density increase, the plasma eventually detaches abruptly from the divertor plates: I SAT drops at the target and the divertor radiation peak moves to the X-point region. Probe measurements at the divertor plate show that the transition occurs when T e ∼5 eV. The critical n e for detachment depends linearly on the input power. This abrupt divertor detachment is preceded by a comparatively long period ( similar 1-200 ms) where a partial detachment is observed to grow at the outer divertor plate. ((orig.))

Transport of light, trace impurities in Alcator C-Mod

Science.gov (United States)

Rowan, W. L.; Bespamyatnov, I. O.; Liao, K. T.; Horton, W.; Fu, X. R.; Hughes, J. W.

2012-10-01

Light impurity profiles for boron were measured in ITB, H-mode, L-mode, and I-mode discharges in Alcator C-Mod. Within this wide range of modes, the profiles varied from peaked to hollow to flat. Specifically, hollow profiles are often observed in H-mode, while ITBs produce strong peaking, and L-mode produces moderate peaking. I-mode discharges are characterized by flat impurity profiles. For the study reported here, the profiles were measured with charge exchange recombination spectroscopy. The dependences of Rv/D were sought on dimensionless quantities including ion density scale length, effective charge, collisionality, and temperature scale length. We find that neoclassical transport consistently underestimates the measured transport. The excess measured transport is assumed to be turbulent. The strongest dependence of Rv/D is with temperature scale length. In addition, the measured transport was compared with the prediction of an analytical theory of drift wave turbulence that identifies transport implications for drift waves driven by ion and impurity density gradients.

Feedback system for divertor impurity seeding based on real-time measurements of surface heat flux in the Alcator C-Mod tokamak

Science.gov (United States)

Brunner, D.; Burke, W.; Kuang, A. Q.; LaBombard, B.; Lipschultz, B.; Wolfe, S.

2016-02-01

Mitigation of the intense heat flux to the divertor is one of the outstanding problems in fusion energy. One technique that has shown promise is impurity seeding, i.e., the injection of low-Z gaseous impurities (typically N2 or Ne) to radiate and dissipate the power before it arrives to the divertor target plate. To this end, the Alcator C-Mod team has created a first-of-its-kind feedback system to control the injection of seed gas based on real-time surface heat flux measurements. Surface thermocouples provide real-time measurements of the surface temperature response to the plasma heat flux. The surface temperature measurements are inputted into an analog computer that "solves" the 1-D heat transport equation to deliver accurate, real-time signals of the surface heat flux. The surface heat flux signals are sent to the C-Mod digital plasma control system, which uses a proportional-integral-derivative (PID) algorithm to control the duty cycle demand to a pulse width modulated piezo valve, which in turn controls the injection of gas into the private flux region of the C-Mod divertor. This paper presents the design and implementation of this new feedback system as well as initial results using it to control divertor heat flux.

Bioergia Research Programme

International Nuclear Information System (INIS)

Asplund, D.

1997-01-01

The main objectives of Finland's Bioenergia Research Programme are (1) To develop new methods of producing biofuels which can compete with imported fuels, demonstrating the most promising production methods through pilot schemes, (2) To develop and demonstrate 3 - 4 new pieces of equipment or methods connected with handling and using bioenergy, (3) To produce basic information on conversion techniques and evaluate the quality, usability and environmental impacts of the products as well as the overall economy of the entire production chain and to create 2-3 conversion methods for follow-up development by industry. The principle research areas are (1) Development of production technology for wood-derived fuels, (2) Peat production, (3) The use of bioenergy and (4) Biomass conversion. This conference paper discusses the results obtained so far and reviews in some detail the activities of the programme. 3 figs., 3 tabs

Edge Zonal Flows and Blob Propagation in Alcator C-Mod

International Nuclear Information System (INIS)

Zweben, S.; Terry, J.L.; Agostini, M.; Davis, B.; Grulke, O.; Hager, R.; Hughes, J.; LaBombard, B.; D'Ippolito, D.A.; Myra, J.R.; Russell, D.A.

2011-01-01

Here we describe recent measurements of the 2-D motion of turbulence in the edge and scrape-off layer (SOL) of the Alcator C-Mod tokamak. This data was taken using the outer midplane gas puff imaging (GPI) camera, which views a 6 cm radial by 6 cm poloidal region near the separatrix just below the outer midplane [1]. The data were taken in Ohmic or RF heated L-mode plasmas at 400,000 frames/sec for ∼50 msec/shot using a Phantom 710 camera in a 64 x 64 pixel format. The resulting 2-D vs. time movies [2] can resolve the structure and motion of the turbulence on a spatial scale covering 0.3-6 cm. The images were analyzed using either a 2-D cross-correlation code (Sec. 2) or a 2-D blob tracking code (Sec. 3).

A Lower Hybrid Current Drive System for Alcator C-Mod

International Nuclear Information System (INIS)

Bernabei, S.; Hosea, J.C.; Loesser, D.; Rushinski, J.; Wilson, J.R.; Bonoli, P.; Grimes, M.; Parker, R.; Porkolab, M.; Terry, D.; Woskov, P.

2001-01-01

A Lower Hybrid Current Drive system is being constructed jointly by Plasma Science and Fusion Center (PSFC) and Princeton Plasma Physics Laboratory (PPPL) for installation on the Alcator C-Mod tokamak, with the primary goal of driving plasma current in the outer region of the plasma. The Lower Hybrid (LH) system consists of 3 MW power at 4.6 GHz with a maximum pulse length of 5 seconds. Twelve klystrons will feed an array of 4-vertical and 24-horizontal waveguides mounted in one equatorial port. The coupler will incorporate some compact characteristics of the multijunction power splitting while retaining full control of the toroidal phase. In addition a dynamic phase control system will allow feedback stabilization of MHD modes. The desire to avoid possible waveguide breakdown and the need for compactness have resulted in some innovative technical solution which will be presented

Pedestal structure and stability in H-mode and I-mode: a comparative study on Alcator C-Mod

International Nuclear Information System (INIS)

Hughes, J.W.; Walk, J.R.; Davis, E.M.; LaBombard, B.; Baek, S.G.; Churchill, R.M.; Greenwald, M.; Hubbard, A.E.; Lipschultz, B.; Marmar, E.S.; Reinke, M.L.; Rice, J.E.; Theiler, C.; Terry, J.; White, A.E.; Whyte, D.G.; Snyder, P.B.; Groebner, R.J.; Osborne, T.; Diallo, A.

2013-01-01

New experimental data from the Alcator C-Mod tokamak are used to benchmark predictive modelling of the edge pedestal in various high-confinement regimes, contributing to greater confidence in projection of pedestal height and width in ITER and reactors. ELMy H-modes operate near stability limits for ideal peeling–ballooning modes, as shown by calculations with the ELITE code. Experimental pedestal width in ELMy H-mode scales as the square root of β pol at the pedestal top, i.e. the dependence expected from theory if kinetic ballooning modes (KBMs) were responsible for limiting the pedestal width. A search for KBMs in experiment has revealed a short-wavelength electromagnetic fluctuation in the pedestal that is a candidate driver for inter-edge localized mode (ELM) pedestal regulation. A predictive pedestal model (EPED) has been tested on an extended set of ELMy H-modes from C-Mod, reproducing pedestal height and width reasonably well across the data set, and extending the tested range of EPED to the highest absolute pressures available on any existing tokamak and to within a factor of three of the pedestal pressure targeted for ITER. In addition, C-Mod offers access to two regimes, enhanced D-alpha (EDA) H-mode and I-mode, that have high pedestals, but in which large ELM activity is naturally suppressed and, instead, particle and impurity transport are regulated continuously. Pedestals of EDA H-mode and I-mode discharges are found to be ideal magnetohydrodynamic (MHD) stable with ELITE, consistent with the general absence of ELM activity. Invocation of alternative physics mechanisms may be required to make EPED-like predictions of pedestals in these kinds of intrinsically ELM-suppressed regimes, which would be very beneficial to operation in burning plasma devices. (paper)

UKAEA underlying research programme annual report

International Nuclear Information System (INIS)

Moon, D.P.

1990-01-01

Investment in fundamental research is essential to the success of an organisation such as Atomic Energy Authority (AEA) Technology whose business is the selling of Research and Development (R and D) and the services relating to it. Such research supplies the scientific understanding that underpins the technical expertise of the organisation, develops new skills and techniques, and stimulates technical innovation. The resulting scientific and technical excellence is the hall-mark of a major contract R and D organisation. Fundamental research in the AEA is co-ordinated through the Underlying Research Programme. This Report describes progress made during the financial year 1988/89 within all Technical Areas of the Programme, and additionally summarises the AEA's Underlying Research on the Safe Integral Reactor design and on 'Cold Fusion'. Highlights of recent technical achievements within the Programme are described in a separate brochure. (author)

The effects of field reversal on the Alcator C-Mod divertor

International Nuclear Information System (INIS)

Hutchinson, I.H.; LaBombard, B.; Goetz, J.A.; Lipschultz, B.; McCracken, G.M.; Snipes, J.A.; Terry, J.L.

1995-01-01

Imbalances between the inboard and outboard legs of the single null divertor in tokamak Alcator C-Mod are observed to reverse when the direction of the toroidal field is reversed. These imbalances are measured by embedded probes in the target plates, tomographic reconstructions of bolometry and line radiation, and visible imaging. Density imbalances of about a factor of ten at the targets are observed at moderate density, decreasing as the density is raised until they are almost balanced. The data indicate that the electron pressure is not imbalanced, thus arguing against momentum imbalance as the cause of these drift-induced effects. Instead, power flux imbalance caused by E r ''and'' B convection, and enhanced by radiation, is suggested as the underlying cause. (Author)

The flush-mounted rail Langmuir probe array designed for the Alcator C-Mod vertical target plate divertor

Science.gov (United States)

Kuang, A. Q.; Brunner, D.; LaBombard, B.; Leccacorvi, R.; Vieira, R.

2018-04-01

An array of flush-mounted and toroidally elongated Langmuir probes (henceforth called rail probes) have been specifically designed for the Alcator C-Mod's vertical target plate divertor and operated over multiple campaigns. The "flush" geometry enables the tungsten electrodes to survive high heat flux conditions in which traditional "proud" tungsten electrodes suffer damage from melting. The toroidally elongated rail-like geometry reduces the influence of sheath expansion, which is an important effect to consider in the design and interpretation of flush-mounted Langmuir probes. The new rail probes successfully operated during C-Mod's FY2015 and FY2016 experimental campaigns with no evidence of damage, despite being regularly subjected to heat flux densities parallel to the magnetic field exceeding ˜1 GW m-2 for short periods of time. A comparison between rail and proud probe data indicates that sheath expansion effects were successfully mitigated by the rail design, extending the use of these Langmuir probes to incident magnetic field line angles as low as 0.5°.

A CO2 laser polarimeter for measurement of plasma current profile in Alcator C-Mod

International Nuclear Information System (INIS)

Ma, C.H.; Hutchinson, D.P.; Richards, R.K.; Irby, J.; Luke, T.

1994-01-01

A multichannel infrared polarimeter system for measurement of the plasma current profile in Alcator C-Mod has been designed, constructed, and tested. The system utilizes a cw CO 2 , laser at a wavelength of 10.6 μm. An electro-optic polarization-modulation technique has been used to achieve the high sensitivity required for the measurement. The recent results of the measurements as well as the feasibility of its application on ITER are presented

Active control system upgrade design for lower hybrid current drive system on Alcator C-Mod

Energy Technology Data Exchange (ETDEWEB)

Kanojia, A.D., E-mail: akanojia@mit.edu [Massachusetts Institute of Technology Plasma Science and Fusion Center, Cambridge, MA (United States); Wallace, G.M.; Terry, D.R.; Stillerman, J.A.; Burke, W.M.; MacGibbon, P.A.; Johnson, D.K. [Massachusetts Institute of Technology Plasma Science and Fusion Center, Cambridge, MA (United States)

2012-12-15

Highlights: Black-Right-Pointing-Pointer Initial tests of the Hittite microwave components show good or better control of phase and amplitude when compared to the vector modulators used in the current system. Black-Right-Pointing-Pointer With an analog based control component system the system complexity is dramatically reduced. Black-Right-Pointing-Pointer Historically, D-tAcq hardware/software has performed more reliably on DPCS and FFT controllers than the current lower hybrid control system Black-Right-Pointing-Pointer Cost and lead time of the Hittite microwave components is significantly small compared to vector modulators. - Abstract: As a part of the scheduled expansion of the Alcator C-Mod lower hybrid current drive (LHCD) system from 12 to 16 klystrons to accommodate installation of a second LH antenna, the active control system (ACS) is being redesigned to accommodate the additional klystrons. Digitizers and output modules will be cPCI modules provided by D-tAcq Solutions. The real-time application will run on a standard PC server running Linux. Initially, the new ACS system will be designed to control 8 klystrons on the second LH antenna and the existing ACS will control the remaining 8 klystrons on the existing LH antenna. Experience gained operating the existing LHCD system has given us insight into the design of a more robust, compact, efficient and simple system for the new ACS. The design upgrade will be patterned on the digital plasma control system (DPCS [1]) in use on C-Mod.

Modélisation et automatisation des procédés d’écriture et de production de supports de formation numérisés - Le modèle M.A.Ï.HEU.T.I.C. de la CCI de Paris

Directory of Open Access Journals (Sweden)

José Martin

2005-01-01

Full Text Available Cet article expose les conclusions d’un projet de recherche de la Direction de l’Enseignement de la Chambre de Commerce et d’Industrie de Paris (CCIP, mené de 2003 à 2005, dont l’aboutissement est un modèle didactique de production de contenus de cours numérisés, baptisé M.A.Ï.HEU.T.I.C.[[ M.A.Ï.HEU.T.I.C. : Modèle Appliqué d’Interprétation Heuristique des Technologies de l’Information et de la Communication.

Bioergia Research Programme

Energy Technology Data Exchange (ETDEWEB)

Asplund, D

1998-12-31

The main objectives of Finland`s Bioenergia Research Programme are (1) To develop new methods of producing biofuels which can compete with imported fuels, demonstrating the most promising production methods through pilot schemes, (2) To develop and demonstrate 3 - 4 new pieces of equipment or methods connected with handling and using bioenergy, (3) To produce basic information on conversion techniques and evaluate the quality, usability and environmental impacts of the products as well as the overall economy of the entire production chain and to create 2-3 conversion methods for follow-up development by industry. The principle research areas are (1) Development of production technology for wood-derived fuels, (2) Peat production, (3) The use of bioenergy and (4) Biomass conversion. This conference paper discusses the results obtained so far and reviews in some detail the activities of the programme. 3 figs., 3 tabs.

Bioergia Research Programme

Energy Technology Data Exchange (ETDEWEB)

Asplund, D.

1997-12-31

The main objectives of Finland`s Bioenergia Research Programme are (1) To develop new methods of producing biofuels which can compete with imported fuels, demonstrating the most promising production methods through pilot schemes, (2) To develop and demonstrate 3 - 4 new pieces of equipment or methods connected with handling and using bioenergy, (3) To produce basic information on conversion techniques and evaluate the quality, usability and environmental impacts of the products as well as the overall economy of the entire production chain and to create 2-3 conversion methods for follow-up development by industry. The principle research areas are (1) Development of production technology for wood-derived fuels, (2) Peat production, (3) The use of bioenergy and (4) Biomass conversion. This conference paper discusses the results obtained so far and reviews in some detail the activities of the programme. 3 figs., 3 tabs.

The CEC radon research programme

International Nuclear Information System (INIS)

Olast, M.

1990-01-01

Following a council decision of 20 June 1989, a CEC research and training programme in the field of radiation protection has been adopted for the period 1990-1991. The european research programme is divided into three main areas, one being 'Risks and Management of Radiation Exposure': this includes a section on 'Exposure to natural radioactivity and evaluation of parameters influencing these risks'. The importance given to this field led to an impressive number of research proposals. The proposals accepted are grouped in three large multinational contracts covering radon exposure, and in one multinational contract dealing with environmental radon epidemiology. (author)

Overview of recent results from a Alcator C-Mod tokamak

International Nuclear Information System (INIS)

Marmar, E.; Batishchev, O.; Acedo, P.

1999-01-01

Recent results from the compact, high field, Alcator C-Mod tokamak program are summarized. H-mode threshold studies have demonstrated that the threshold appears to be closely related to local edge plasma parameters: for fixed field and plasma current, T e (ψ 95 ) takes on a density independent value at the transition. The Enhanced D-Alpha H-Mode (EDA) regime has been investigated. EDA is distinct from ELM free H-mode, in that there is no accumulation of impurities, and at the same time EDA does not exhibit large discrete ELMs. The energy confinement is degraded by only about 10%, compared to ELM free. Comparisons for EDA with ELMy H-Mode database scalings indicate τ EDA ∼1.2 τ ITER97H . Strong toroidal rotation is observed in ICRF-only auxiliary heated plasmas; the rotation increases with plasma pressure, and decreases with increasing plasma current. The inferred radial electric field reaches the order of 30 kV/m near the center of the plasma. Through feedback controlled nitrogen impurity puffing, steady state detached EDA H-Modes have been achieved with Z eff E is reduced by about 10% in the detached case, compared to the confinement before the N 2 puff begins. The heat load to the divertor is reduced by a factor of 4. Volume recombination rates are measured in the divertor, using 2-d tomography of Balmer series TV movies. Volume recombination can be a significant contributor to the overall reduction in ion current to the divertor plates which occurs in detachment. Particle balance measurements indicate that the divertor and main chamber plasmas are largely isolated from one another, at least with regard to particle recycling, with most of the main chamber (core plus scrape-off) fueling coming from neutrals in the main chamber volume. With the addition of Lower Hybrid Current Drive, C-Mod would be an ideal vehicle for investigation of advanced tokamak operation with fully relaxed current profiles. Detailed modeling indicates that discharges approaching the �

Overview of recent results from the Alcator C-Mod tokamak

International Nuclear Information System (INIS)

Marmar, E.; Batishchev, O.; Acedo, P.

2001-01-01

Recent results from the compact, high field, Alcator C-Mod tokamak program are summarized. H-mode threshold studies have demonstrated that the threshold appears to be closely related to local edge plasma parameters: for fixed field and plasma current, T e (ψ 95 ) takes on a density independent value at the transition. The Enhanced D-Alpha H-Mode (EDA) regime has been investigated. EDA is distinct from ELM free H mode, in that there is no accumulation of impurities, and at the same time EDA does not exhibit large discrete ELMs. The energy confinement is degraded by only about 10%, compared to ELM free. Comparisons for EDA with ELMy H-Mode database scalings indicate τEDA ∼ 1.2τ ITER97H . Strong toroidal rotation is observed in ICRF-only auxiliary heated plasmas; the rotation increases with plasma pressure, and decreases with increasing plasma current. The inferred radial electric field reaches the order of 30kV/m near the center of the plasma. Through feedback controlled nitrogen impurity puffing, steady state detached EDA H-Modes have been achieved with Z eff E is reduced by about 10% in the detached case, compared to the confinement before the N 2 puff begins. The heat load to the divertor is reduced by a factor of 4. Volume recombination rates are measured in the divertor, using 2-d tomography of Balmer series TV movies. Volume recombination can be a significant contributor to the overall reduction in ion current to the divertor plates which occurs in detachment. Particle balance measurements indicate that the divertor and main chamber plasmas are largely isolated from one another, at least with regard to particle recycling, with most of the main chamber (core plus scrape-off) fueling coming from neutrals in the main chamber volume. With the addition of Lower Hybrid Current Drive, C-Mod would be an ideal vehicle for investigation of advanced tokamak operation with fully relaxed current profiles. Detailed modeling indicates that discharges approaching the �

Neutral Transport Simulations of Gas Puff Imaging Experiments on Alcator C-Mod

International Nuclear Information System (INIS)

Stotler, D.P.; LaBombard, B.; Terry, J.L.; Zweben, S.J.

2002-01-01

Visible imaging of gas puffs has been used on the Alcator C-Mod tokamak to characterize edge plasma turbulence, yielding data that can be compared with plasma turbulence codes. Simulations of these experiments with the DEGAS 2 Monte Carlo neutral transport code have been carried out to explore the relationship between the plasma fluctuations and the observed light emission. By imposing two-dimensional modulations on the measured time-average plasma density and temperature profiles, we demonstrate that the spatial structure of the emission cloud reflects that of the underlying turbulence. However, the photon emission rate depends on the plasma density and temperature in a complicated way, and no simple scheme for inferring the plasma parameters directly from the light emission patterns is apparent. The simulations indicate that excited atoms generated by molecular dissociation are a significant source of photons, further complicating interpretation of the gas puff imaging results.Visibl e imaging of gas puffs has been used on the Alcator C-Mod tokamak to characterize edge plasma turbulence, yielding data that can be compared with plasma turbulence codes. Simulations of these experiments with the DEGAS 2 Monte Carlo neutral transport code have been carried out to explore the relationship between the plasma fluctuations and the observed light emission. By imposing two-dimensional modulations on the measured time-average plasma density and temperature profiles, we demonstrate that the spatial structure of the emission cloud reflects that of the underlying turbulence. However, the photon emission rate depends on the plasma density and temperature in a complicated way, and no simple scheme for inferring the plasma parameters directly from the light emission patterns is apparent. The simulations indicate that excited atoms generated by molecular dissociation are a significant source of photons, further complicating interpretation of the gas puff imaging results

ICRF-enhanced plasma potentials in the SOL of Alcator C-Mod

Energy Technology Data Exchange (ETDEWEB)

Ochoukov, R.; Whyte, D. G.; Brunner, D.; LaBombard, B.; Lipschultz, B.; Terry, J. L.; Wukitch, S. J. [PSFC MIT, NW17, 175 Albany Street, Cambridge, MA 02139 (United States); D' Ippolito, D. A.; Myra, J. R. [Lodestar Research Corporation, 2400 Central Avenue, Boulder, Colorado 80301 (United States)

2014-02-12

We performed an extensive survey of the plasma potential in the scrape-off layer (SOL) of Ion Cyclotron Range-of Frequencies (ICRF)-heated discharges on Alcator C-Mod. Our results show that plasma potentials are enhanced in the presence of ICRF power and plasma potential values of >100 V are often observed. Such potentials are high enough to induce sputtering of high-Z molybdenum (Mo) plasma facing components by deuterium ions on C-Mod. For comparison, the plasma potential in Ohmic discharges is typically less than 10 V, well below the threshold needed to induce Mo sputtering by deuterium ions. ICRF-enhanced plasma potentials are observed in the SOL regions that both magnetically map and do not map to active ICRF antennas. Regions that magnetically map to active ICRF antennas are accessible to slow waves directly launched by the antennas and these regions experience plasma potential enhancement that is partially consistent with the slow wave rectification mechanism. One of the most defining features of the slow wave rectification is a threshold appearance of significant plasma potentials (>100 V) when the dimensionless rectification parameter Λ{sub −o} is above unity and this trend is observed experimentally. We also observe ICRF-enhanced plasma potentials >100 V in regions that do not magnetically map to the active antennas and, hence, are not accessible for slow waves launched directly by the active antennas. However, unabsorbed fast waves can reach these regions. The general trend that we observe in these 'un-mapped' regions is that the plasma potential scales with the strength of the local RF wave fields with the fast wave polarization and the highest plasma potentials are observed in discharges with the highest levels of unabsorbed ICRF power. Similarly, we find that core Mo levels scale with the level of unabsorbed ICRF power suggesting a link between plasma potentials in the SOL and the strength of the impurity source.

Foresight and strategy in national research councils and research programmes

DEFF Research Database (Denmark)

Andersen, Per Dannemand; Borup, Mads

2009-01-01

This paper addresses the issue of foresight and strategy processes of national research councils and research programmes. It is based on a study of strategy processes in national research councils and programmes and the challenges faced by their strategy activities. We analysed the strategy...... processes of two organisations: the Danish Technical Research Council and the Danish Energy Research Programme. We analysed the mechanisms of the strategy processes and studied the actors involved. The actors’ understanding of strategy was also included in the analysis. Based on these analyses we argue...... that the impact of foresight exercises can be improved if we have a better understanding of the traditions and new challenges faced by the research councils. We also argue that a more formal use of foresight elements might improve the legitimacy and impact of the strategic considerations of research councils...

Scaling of H-mode pedestal characteristics in DIII-D and C-Mod

International Nuclear Information System (INIS)

Granetz, R.S.; Boivin, R.L.; Osborne, T.H.

1999-01-01

Since the H-mode edge pedestal effectively sets the boundary conditions for energy transport throughout the core, a better understanding of the pedestal region is necessary in order to fully predict H-mode performance. Pedestal characteristics in the DIII-D and Alcator C-Mod tokamaks are described, and scalings of the pedestal width with various plasma parameters are shown. The pedestal width in both tokamaks varies in an inverse sense with plasma current, and is independent of toroidal field. Other similarities, as well as differences, are discussed. It is also found that the pedestal widths of the various physical quantities involved (T e , T i , n e , n i ) may be different. (author)

TC-13 Mod 0 and Mod 2 Steam Catapult Test Site

Data.gov (United States)

Federal Laboratory Consortium — Located on 11,000 feet of test runway, the TC-13 Mod 0 and Mod 2 Steam Catapult Test Site has in-ground catapults identical to those aboard carriers. This test site...

Edge turbulence imaging in the Alcator C-Mod tokamak

International Nuclear Information System (INIS)

Zweben, S.J.; Stotler, D.P.; Terry, J.L.; La Bombard, B.; Greenwald, M.; Muterspaugh, M.; Pitcher, C.S.; Hallatschek, K.; Maqueda, R.J.; Rogers, B.; Lowrance, J.L.; Mastrocola, V.J.; Renda, G.F.

2002-01-01

The two-dimensional (2D) radial vs poloidal structure of edge turbulence in the Alcator C-Mod tokamak [I. H. Hutchinson, R. Boivin, P. T. Bonoli et al., Nucl. Fusion 41, 1391 (2001)] was measured using fast cameras and compared with three-dimensional numerical simulations of edge plasma turbulence. The main diagnostic is gas puff imaging, in which the visible D α emission from a localized D 2 gas puff is viewed along a local magnetic field line. The observed D α fluctuations have a typical radial and poloidal scale of ≅1 cm, and often have strong local maxima ('blobs') in the scrape-off layer. The motion of this 2D structure motion has also been measured using an ultrafast framing camera with 12 frames taken at 250 000 frames/s. Numerical simulations produce turbulent structures with roughly similar spatial and temporal scales and transport levels as that observed in the experiment; however, some differences are also noted, perhaps requiring diagnostic improvement and/or additional physics in the numerical model

Finnish Research Programme on Nuclear Waste Management (KYT). Framework Programme for 2002-2005

International Nuclear Information System (INIS)

Rasilainen, K.

2002-12-01

The new Finnish research programme on nuclear waste management (KYT) will be conducted in 2002 - 2005. This framework programme describes the starting point, the basic aims and the organisation of the research programme. The starting point of the KYT programme is derived from the present state and future challenges of Finnish nuclear waste management. The research programme is funded mainly by the Ministry of Trade and Industry (KTM), the Radiation and Nuclear Safety Authority (STUK), Posiva Oy, Fortum Oyj, Teollisuuden Voima Oy (TVO), and the National Technology Agency (Tekes). As both regulators and implementors are involved, the research programme concentrates on neutral research topics that must be studied in any case. Methods and tools for experimental and theoretical studies fall in this category. State of the art -reviews on relevant topics also create national know-how. Topics that directly belong to licensing activities of nuclear waste management are excluded from the research programme. KYT carries out technical studies that increase national know-how in the area of nuclear waste management. The aim is to maintain and develop basic expertise needed in the operations derived from the national nuclear waste management plan. The studies have been divided into strategic studies and studies enhancing the long-term safety of spent nuclear fuel disposal. Strategic studies support the overall feasibility of Finnish nuclear waste management. These studies include basic options and overall safety principles related to nuclear fuel cycle and nuclear waste management. In addition, general cost estimates as well as general safety considerations related to transportations, low- and medium level wastes, and decommissioning are included in strategic studies. Studies supporting the long-term safety of spent fuel disposal include issues related to performance assessment methodology, release of radionuclides from the repository, behaviour of bedrock and groundwater

Apo and ligand-bound structures of ModA from the archaeon Methanosarcina acetivorans.

Science.gov (United States)

Chan, Sum; Giuroiu, Iulia; Chernishof, Irina; Sawaya, Michael R; Chiang, Janet; Gunsalus, Robert P; Arbing, Mark A; Perry, L Jeanne

2010-03-01

The trace-element oxyanion molybdate, which is required for the growth of many bacterial and archaeal species, is transported into the cell by an ATP-binding cassette (ABC) transporter superfamily uptake system called ModABC. ModABC consists of the ModA periplasmic solute-binding protein, the integral membrane-transport protein ModB and the ATP-binding and hydrolysis cassette protein ModC. In this study, X-ray crystal structures of ModA from the archaeon Methanosarcina acetivorans (MaModA) have been determined in the apoprotein conformation at 1.95 and 1.69 A resolution and in the molybdate-bound conformation at 2.25 and 2.45 A resolution. The overall domain structure of MaModA is similar to other ModA proteins in that it has a bilobal structure in which two mixed alpha/beta domains are linked by a hinge region. The apo MaModA is the first unliganded archaeal ModA structure to be determined: it exhibits a deep cleft between the two domains and confirms that upon binding ligand one domain is rotated towards the other by a hinge-bending motion, which is consistent with the 'Venus flytrap' model seen for bacterial-type periplasmic binding proteins. In contrast to the bacterial ModA structures, which have tetrahedral coordination of their metal substrates, molybdate-bound MaModA employs octahedral coordination of its substrate like other archaeal ModA proteins.

Apo and ligand-bound structures of ModA from the archaeon Methanosarcina acetivorans

International Nuclear Information System (INIS)

Chan, Sum; Giuroiu, Iulia; Chernishof, Irina; Sawaya, Michael R.; Chiang, Janet; Gunsalus, Robert P.; Arbing, Mark A.; Perry, L. Jeanne

2010-01-01

Crystal structures of ModA from M. acetivorans in the apo and ligand-bound conformations confirm domain rotation upon ligand binding. The trace-element oxyanion molybdate, which is required for the growth of many bacterial and archaeal species, is transported into the cell by an ATP-binding cassette (ABC) transporter superfamily uptake system called ModABC. ModABC consists of the ModA periplasmic solute-binding protein, the integral membrane-transport protein ModB and the ATP-binding and hydrolysis cassette protein ModC. In this study, X-ray crystal structures of ModA from the archaeon Methanosarcina acetivorans (MaModA) have been determined in the apoprotein conformation at 1.95 and 1.69 Å resolution and in the molybdate-bound conformation at 2.25 and 2.45 Å resolution. The overall domain structure of MaModA is similar to other ModA proteins in that it has a bilobal structure in which two mixed α/β domains are linked by a hinge region. The apo MaModA is the first unliganded archaeal ModA structure to be determined: it exhibits a deep cleft between the two domains and confirms that upon binding ligand one domain is rotated towards the other by a hinge-bending motion, which is consistent with the ‘Venus flytrap’ model seen for bacterial-type periplasmic binding proteins. In contrast to the bacterial ModA structures, which have tetrahedral coordination of their metal substrates, molybdate-bound MaModA employs octahedral coordination of its substrate like other archaeal ModA proteins

Microturbulent drift mode suppression as a trigger mechanism for internal transport barriers on Alcator C-Mod

International Nuclear Information System (INIS)

Zhurovich, K.; Fiore, C.L.; Ernst, D.R.; Bonoli, P.T.; Greenwald, M.J.; Hubbard, A.E.; Hughes, J.W.; Marmar, E.S.; Mikkelsen, D.R.; Phillips, P.; Rice, J.E.

2007-01-01

Internal transport barriers (ITBs) can be routinely produced in enhanced D α (EDA) H-mode discharges on the Alcator C-Mod tokamak by putting the minority ion cyclotron resonance layer at vertical bar r/a vertical bar ≥ 0.5 during the current flat top phase of the discharge. These ITBs are characterized by density peaking at constant temperature and are therefore both particle and energy transport barriers. The ITB formation appears to result from widening the region near the magnetic axis in which toroidal drift modes are stable, allowing the Ware pinch to peak the density profile. Experimental evidence shows that shifting the ICRF resonance off-axis results in a local flattening of ion and electron temperature profiles. TRANSP calculations of ion temperature profiles support this experimentally observed trend. Stability analysis of ion temperature gradient (ITG) and electron temperature gradient modes at times before ITB formation is done using the linear gyrokinetic code GS2. These gyrokinetic calculations find that the most unstable modes in the C-Mod EDA H-mode core, prior to ITB onset, are the toroidal ITG driven type. These modes are suppressed in the ITB region through a temperature gradient reduction when the ICRF resonance is shifted off-axis

Advances in measurement and modeling of the high-confinement-mode pedestal on the Alcator C-Mod tokamak

International Nuclear Information System (INIS)

Hughes, J.W.; LaBombard, B.; Mossessian, D.A.; Hubbard, A.E.; Terry, J.; Biewer, T.

2006-01-01

Edge transport barrier (ETB) studies on the Alcator C-Mod tokamak [Phys. Plasmas 1, 1511 (1994)] investigate pedestal scalings and the radial transport of plasma and neutrals. Pedestal profiles show trends with plasma operational parameters such as total current I P . A ballooning-like I P 2 dependence is seen in the pressure gradient, despite calculated stability to ideal ballooning modes. A similar scaling is seen in the near scrape-off layer for both low-confinement (L-mode) and H-mode discharges, possibly due to electromagnetic fluid drift turbulence setting transport near the separatrix. Neutral density diagnosis allows an examination of D 0 fueling in H-modes, yielding profiles of effective particle diffusivity in the ETB, which vary as I P is changed. Edge neutral transport is studied using a one-dimensional kinetic treatment. In both experiment and modeling, the C-Mod density pedestal exhibits a weakly increasing pedestal density and a nearly invariant density pedestal width as the D 0 source rate increases. Identical modeling performed on pedestal profiles typical of DIII-D [Nucl. Fusion 42, 614 (2002)] reveal differences in pedestal scalings qualitatively similar to experimental results

The National Institute for Health Research Leadership Programme

Science.gov (United States)

Jones, Molly Morgan; Wamae, Watu; Fry, Caroline Viola; Kennie, Tom; Chataway, Joanna

2012-01-01

Abstract RAND Europe evaluated the National Institute for Health Research (NIHR) Leadership Programme in an effort to help the English Department of Health consider the extent to which the programme has helped to foster NIHR's aims, extract lessons for the future, and develop plans for the next phase of the leadership programme. Successful delivery of high-quality health research requires not only an effective research base, but also a system of leadership supporting it. However, research leaders are not often given the opportunity, nor do they have the time, to attend formal leadership or management training programmes. This is unfortunate because research has shown that leadership training can have a hugely beneficial effect on an organisation. Therefore, the evaluation has a particular interest in understanding the role of the programme as a science policy intervention and will use its expertise in science policy analysis to consider this element alongside other, more traditional, measures of evaluation. PMID:28083231

Public sector's research programme on nuclear waste management

International Nuclear Information System (INIS)

Vuori, S.

2000-06-01

According to the Finnish nuclear energy legislation, each producer of nuclear waste is responsible for the safe handling, management and disposal of the waste as well as for the arising costs. Authorities supervise and control the implementation of the national waste management programme and set the necessary safety and other requirements. In these tasks the authorities are supported by a research programme on nuclear waste management that is independent of the implementing organisations and power companies. The main objective of the research programme has been to provide the authorities with information and research results relevant for the safety of nuclear waste management. The main emphasis in this research programme has been devoted to the final disposal of spent fuel. The whole area of the research programme has been subdivided into the following main topic areas: (1) Behaviour of bedrock (2) Geohydrology and geochemistry, (3) Release of radionuclides from repository and subsequent transport in bedrock, (4) Engineered safety barriers of the repository, system, (5) Performance and safety assessment of spent fuel disposal facilities, (6) Waste management technology and costs (7) Evaluation of the contents and scope of and observation of the realisation of the environmental impact assessment procedure for the siting of spent nuclear fuel disposal facility, and research on other societal and sociopolitical issues, and (8) Public information, attitude, and image issues for waste management facilities. The research programme has generated considerably increased information on the behaviour of the natural and technical release barriers of the disposal system and thereby contributed to building of confidence on the long-term safety of geological disposal of spent fuel. Furthermore, increased confidence among the public in the affected candidate municipalities has probably been achieved by the complementary studies conducted within the research programme on topics

The European structural integrity research programme

International Nuclear Information System (INIS)

Townley, C.H.A.; Acker, D.; Laue, H.

1990-01-01

A thermal hydraulics evaluation of the European Fast Reactor (EFR) design followed by structural analysis is presented in this article to assess the structural integrity research programme to date. Improved design methods are being achieved as a result of the structural integrity programme for the EFR. Excellent collaboration between the nationally based research organizations and the design and construction companies has been important in achieving these improvements. (UK)

SANCOR marine pollution research programme 1986-1990

CSIR Research Space (South Africa)

SANCOR

1985-01-01

Full Text Available The Marine Pollution Research Programme is one of the series of SANCOR Programmes. Up to 1985 research into these aspects of oil pollution covered by the Prevention and combating of Pollution of the Sea by Oil Act (no. 6 of 1981) has been...

Analysis of C-MOD molybdenum divertor erosion and code/data comparison

Energy Technology Data Exchange (ETDEWEB)

Brooks, J.N., E-mail: brooksjn@purdue.edu [Purdue University, West Lafayette, IN (United States); Allain, J.P. [Purdue University, West Lafayette, IN (United States); Whyte, D.G.; Ochoukov, R.; Lipschultz, B. [Massachusetts Institute of Technology, Cambridge, MA (United States)

2011-08-01

We analyze an important 15 year old Alcator C-MOD study of campaign-integrated molybdenum divertor erosion in which the measured net erosion was significantly higher ({approx}X3) than originally predicted by a simple model . We perform full process sputtering erosion/redeposition computational analysis including the effect of a possible RF induced sheath. The simulations show that most sputtered Mo atoms are ionized close to the surface and strongly redeposited, via Lorentz force motion and collisional friction with the high density incoming plasma. The predicted gross erosion profile is a reasonable match to MoI influx data, however, the critically important net erosion comparison with post-exposure Mo tile analysis is poor, with {approx}X10 higher peak erosion measured than computed. An RF sheath increases predicted erosion by {approx}45%, thus being significant but not fundamental. We plan future analysis.

Functional characterization of the Bradyrhizobium japonicum modA and modB genes involved in molybdenum transport.

Science.gov (United States)

Delgado, María J; Tresierra-Ayala, Alvaro; Talbi, Chouhra; Bedmar, Eulogio J

2006-01-01

A modABC gene cluster that encodes an ABC-type, high-affinity molybdate transporter from Bradyrhizobium japonicum has been isolated and characterized. B. japonicum modA and modB mutant strains were unable to grow aerobically or anaerobically with nitrate as nitrogen source or as respiratory substrate, respectively, and lacked nitrate reductase activity. The nitrogen-fixing ability of the mod mutants in symbiotic association with soybean plants grown in a Mo-deficient mineral solution was severely impaired. Addition of molybdate to the bacterial growth medium or to the plant mineral solution fully restored the wild-type phenotype. Because the amount of molybdate required for suppression of the mutant phenotype either under free-living or under symbiotic conditions was dependent on sulphate concentration, it is likely that a sulphate transporter is also involved in Mo uptake in B. japonicum. The promoter region of the modABC genes has been characterized by primer extension. Reverse transcription and expression of a transcriptional fusion, P(modA)-lacZ, was detected only in a B. japonicum modA mutant grown in a medium without molybdate supplementation. These findings indicate that transcription of the B. japonicum modABC genes is repressed by molybdate.

Simulation of channel blockage for the IEA-R1 research reactor using RELAP/MOD 3

International Nuclear Information System (INIS)

Oliveira, Eduardo C.F. de; Castrillo, Lazara Silveira

2015-01-01

Research reactors have great importance in the area of nuclear technology, such as radioisotope production, research in nuclear physics, development of new technologies and staff training for reactor operation. The IEA-R1 is a Brazilian research reactor type pool, located at the IPEN (Instituto de Pesquisas Energeticas e Nucleares). In this work is simulated with computer code RELAP5 / MOD 3.3.2 gamma, the effect caused by partial and complete blockage of a channel in MTR fuel element of the IEA-R1 core, in order to analyzed the thermal hydraulic parameters on adjacent channels. (author)

Simulation of channel blockage for the IEA-R1 research reactor using RELAP/MOD 3

Energy Technology Data Exchange (ETDEWEB)

Oliveira, Eduardo C.F. de; Castrillo, Lazara Silveira, E-mail: ecfoliveira@hotmail.com, E-mail: lazara.castrillo@upe.br [Universidade de Pernambuco (UPE), Recife, PE (Brazil). Escola Politecnica de Pernambuco

2015-07-01

Research reactors have great importance in the area of nuclear technology, such as radioisotope production, research in nuclear physics, development of new technologies and staff training for reactor operation. The IEA-R1 is a Brazilian research reactor type pool, located at the IPEN (Instituto de Pesquisas Energeticas e Nucleares). In this work is simulated with computer code RELAP5 / MOD 3.3.2 gamma, the effect caused by partial and complete blockage of a channel in MTR fuel element of the IEA-R1 core, in order to analyzed the thermal hydraulic parameters on adjacent channels. (author)

Who owns the mods?

OpenAIRE

Kow, Yong Ming; Nardi, Bonnie

2010-01-01

Modding, the development of end user software extensions to commercial products, is popular among video gamers. Modders form communities to help each other. Mods can shape software products by weaving in contributions from users themselves based on their own experience of a product. The purpose of this paper is to investigate a conflict between a modding community and a gaming company which reveals contested issues of ownership and governance. We studied an online game, World of Warcraft, a l...

Finnish research programmes on nuclear power plant safety

International Nuclear Information System (INIS)

Puska, E. K.

2010-01-01

The current Finnish national research programme on nuclear power plant safety SAFIR2010 for the years 2007-2010 as well as the coming SAFIR2014 programme for the years 2011-2014 are based on the chapter 7a, 'Ensuring expertise', of the Finnish Nuclear Energy Act. The objective of this chapter is realised in the research work and education of experts in the projects of these research programmes. SAFIR2010 research programme is divided in eight research areas that are Organisation and human, Automation and control room, Fuel and reactor physics, Thermal hydraulics, Severe accidents, Structural safety of reactor circuit, Construction safety, and Probabilistic Safety Analysis (PSA). All the research areas include both projects in their own area and interdisciplinary co-operational projects. Research projects of the programme are chosen on the basis of annual call for proposals. In 2010 research is carried out in 33 projects in SAFIR2010. VTT is the responsible research organisation in 26 of these projects and VTT is also the coordination unit of SAFIR2010 and SAFIR2014. In 2007-2009 SAFIR2010 produced 497 Specified research results (Deliverables), 618 Publications, and 33 Academic degrees. SAFIR2010 programme covers approximately half of the reactor safety research volume in Finland currently. In 2010 the programme volume is EUR 7.1 million and 47 person years. The major funding partners are VYR with EUR 2.96 million, VTT with EUR 2.66 million, Fortum with EUR 0.28 million, TVO with EUR 0.19 million, NKS with EUR 0.15 million, EU with only EUR 0.03 million and other partners with EUR 0.85 million. The new decisions-in-principle on Olkiluoto unit 4 for Teollisuuden Voima and new nuclear power plant for Fennovoima ratified by the Finnish Parliament on 1 July 2010 increase the annual funding collected according to the Finnish Nuclear Energy Act from Fennovoima, Fortum and Teollisuuden Voima for the SAFIR2014 programme to EUR 5.2 million from the current level of EUR 3

The Finnish research programme on climate change. Final report

Energy Technology Data Exchange (ETDEWEB)

Roos, J [ed.

1997-12-31

This is the final report of the Finnish Research Programme on Climate Change (SILMU). This report includes the final results and conclusions made by the individual research groups. The aim of this report is to lay out the research work, and to present the main results and conclusions obtained during the six-year work. The Finnish Research Programme on Climate Change (SILMU) was a multidisciplinary national research programme on climate and global change. The principal goals of SILMU were: (1) to increase our knowledge on climate change, its causes, mechanisms and consequences, (2) to strengthen the research on climate change in Finland, (3) to increase the participation of Finnish researchers in international research programmes, and (4) to prepare and disseminate information for policy makers on adaptation and mitigation. The key areas of the research were: (1) quantification of the greenhouse effect and the magnitude of anticipated climatic changes,(2) assessment of the effects of changing climate on ecosystems, and (3) development of mitigation and adaptation strategies. The research programme started in June 1990, and it comprised more than 80 individual research projects, ranging from atmospheric chemistry to economics. There were approximately two hundred scientists working within the programme in seven universities and eleven research institutions. The research activities that comprise SILMU were grouped into four interdisciplinary subprogrammes: atmosphere, waters, terrestrial ecosystems and integration and human interactions

The Finnish research programme on climate change. Final report

Energy Technology Data Exchange (ETDEWEB)

Roos, J. [ed.

1996-12-31

This is the final report of the Finnish Research Programme on Climate Change (SILMU). This report includes the final results and conclusions made by the individual research groups. The aim of this report is to lay out the research work, and to present the main results and conclusions obtained during the six-year work. The Finnish Research Programme on Climate Change (SILMU) was a multidisciplinary national research programme on climate and global change. The principal goals of SILMU were: (1) to increase our knowledge on climate change, its causes, mechanisms and consequences, (2) to strengthen the research on climate change in Finland, (3) to increase the participation of Finnish researchers in international research programmes, and (4) to prepare and disseminate information for policy makers on adaptation and mitigation. The key areas of the research were: (1) quantification of the greenhouse effect and the magnitude of anticipated climatic changes,(2) assessment of the effects of changing climate on ecosystems, and (3) development of mitigation and adaptation strategies. The research programme started in June 1990, and it comprised more than 80 individual research projects, ranging from atmospheric chemistry to economics. There were approximately two hundred scientists working within the programme in seven universities and eleven research institutions. The research activities that comprise SILMU were grouped into four interdisciplinary subprogrammes: atmosphere, waters, terrestrial ecosystems and integration and human interactions

H-mode edge stability of Alcator C-mod plasmas

International Nuclear Information System (INIS)

Mossessian, D.A.; Hubbard, A.; Hughes, J.W.; Greenwald, M.; LaBombard, B.; Snipes, J.A.; Wolfe, S.; Snyder, P.; Wilson, H.; Xu, X.; Nevins, W.

2003-01-01

For steady state H-mode operation, a relaxation mechanism is required to limit build-up of the edge gradient and impurity content. C-Mod sees two such mechanisms - EDA and grassy ELMs, but not large type I ELMs. In EDA the edge relaxation is provided by an edge localized quasi coherent electromagnetic mode that exists at moderate pedestal temperature T 3.5 and does not limit the build up of the edge pressure gradient. The mode is not observed in the ideal MHD stability analysis, but is recorded in the nonlinear real geometry fluctuations modeling based on fluid equations and is thus tentatively identified as a resistive ballooning mode. At high edge pressure gradients and temperatures the mode is replaced by broadband fluctuations (f< 50 kHz) and small irregular ELMs are observed. Based on ideal MHD calculations that include the effects of edge bootstrap current, these ELMs are identified as medium n (10 < n < 50) coupled peeling/ballooning modes. The stability thresholds, its dependence on the plasma shape and the modes structure are studied experimentally and with the linear MHD stability code ELITE. (author)

Helium experiments on Alcator C-Mod in support of ITER early operations

Science.gov (United States)

Kessel, C. E.; Wolfe, S. M.; Reinke, M. L.; Hughes, J. W.; Lin, Y.; Wukitch, S. J.; Baek, S. G.; Bonoli, P. T.; Chilenski, M.; Diallo, A.; the Alcator C-Mod Team

2018-05-01

Helium majority experiments on Alcator C-Mod were performed to compare with deuterium discharges, and inform ITER early operations. ELMy H-modes were produced with a special plasma shape at B T  =  5.3 T, I P  =  0.9 MA, at q 95 ~ 3.8. The He fraction ranged over, n He,L/n L  =  0.2-0.4, with n D,L/n L  =  0.15-0.26, compared to D plasmas with n D,L/n L  =  0.85-0.97. The power to enter the H-mode in He was found to be greater than ~2 times that for D discharges, in the low density region  operation in ITER.

Swiss breeder research programme

International Nuclear Information System (INIS)

1992-01-01

A new initiative for a Swiss Fast Breeder Research Program has been started during 1991. This was partly the consequence of a vote in Fall 1990, when the Swiss public voted for maintaining nuclear reactors in operation, but also for a moratorium of 10 years, within which period no new reactor project should be proposed. On the other hand the Swiss government decided to keep the option 'atomic reactors' open and therefore it was essential to have programmes which guaranteed that the knowledge of reactor technology could be maintained in the industry and the relevant research organisations. There is also motivation to support a Swiss Breeder Research Program on the part of the utilities, the licensing authorities and the Paul Scherrer Institute (PSI). The utilities recognise the breeder reactor as an advanced reactor system which has to be developed further and might be a candidate, somewhere in the future, for electricity production. In so far they have great interest that a know-how base is maintained in our country, with easy access for technical questions and close attention to the development of this reactor type. The licensing authorities have a legitimate interest that an adequate knowledge of the breeder reactor type and its functions is kept at their disposal. PSI and the former EIR have had for many years a very successful basic research programme concerning breeder reactors, and were in close cooperation with EFR. The activities within this programme had to be terminated owing to limitations in personnel and financial resources. The new PSI research programme is based upon two main areas, reactor physics and reactor thermal hydraulics. In both areas relatively small but valuable basic research tasks, the results of which are of interest to the breeder community, will be carried out. The lack of support of the former Breeder Programme led to capacity problems and finally to a total termination. Therefore one of the problems which had to be solved first was

Measurement of impurity ion densities and energies in the divertor and edge regions of Alcator C-Mod tokamak

International Nuclear Information System (INIS)

Griem, H.R.; Moreno, J.; Welch, B.L.

1992-01-01

A study to investigate impurity production and transport in the divertor and edge regions of the Alcator C-Mod tokamak through spectroscopic techniques is described. A 0.75-meter Czerny-Turner spectrometer with a 1200-g/mm grating and a 35-meter quartz optic bundle transmission line were tested. A high-resolution 2-meter spectrometer will be ordered. Data acquisition considerations are being addressed

Development through science: The IAEA research contract programme

International Nuclear Information System (INIS)

Benson Wiltschegg, T.; Gillen, V.

1991-01-01

The IAEA strives to stimulate the growth of science in developing countries by assuring that the IAEA and the scientific communities of developed and developing countries share their knowledge and experience. If the assistance provided is well organized and in keeping with the needs of developing countries it can make the crucial difference in sustainable development. This booklet provides a survey of the historical development of the IAEA's Research Contract Programme and outlines the aims and achievements of selected Co-ordinated Research Programmes. A complete listing of Co-ordinated Research Programmes is provided

Planning and implementation of nuclear research programmes

International Nuclear Information System (INIS)

Lopes, J.L.

1986-01-01

The planning and implementation of nuclear research programmes in developed and developing countries is discussed. The main aspects of these programmes in USA, France, Japan, India and Brazil are reported. (M.W.O.) [pt

Modding a free and open source software video game: "Play testing is hard work"

Directory of Open Access Journals (Sweden)

Giacomo Poderi

2014-03-01

Full Text Available Video game modding is a form of fan productivity in contemporary participatory culture. We see modding as an important way in which modders experience and conceptualize their work. By focusing on modding in a free and open source software video game, we analyze the practice of modding and the way it changes modders' relationship with their object of interest. The modders' involvement is not always associated with fun and creativity. Indeed, activities such as play testing often undermine these dimensions of modding. We present a case study of modding that is based on ethnographic research done for The Battle for Wesnoth, a free and open source software strategy video game entirely developed by a community of volunteers.

GeoMod 2014 - Modelling in geoscience

Science.gov (United States)

Leever, Karen; Oncken, Onno

2016-08-01

GeoMod is a biennial conference to review and discuss latest developments in analogue and numerical modelling of lithospheric and mantle deformation. GeoMod2014 took place at the GFZ German Research Centre for Geosciences in Potsdam, Germany. Its focus was on rheology and deformation at a wide range of temporal and spatial scales: from earthquakes to long-term deformation, from micro-structures to orogens and subduction systems. It also addressed volcanotectonics and the interaction between tectonics and surface processes (Elger et al., 2014). The conference was followed by a 2-day short course on "Constitutive Laws: from Observation to Implementation in Models" and a 1-day hands-on tutorial on the ASPECT numerical modelling software.

American Legal Realism: Research Programme and Policy Impact

Directory of Open Access Journals (Sweden)

Frans L. Leeuw

2017-12-01

Full Text Available The article addresses two questions:1. Can Legal Realism be seen as a scientific research programme enabling growth of knowledge? To answer that question, the author uses Lakatos’s  work on the methodology of scientific research programmes as a frame of reference.2. What has been the role of American Legal Realism during the first part of the 20th century in helping to develop and implement the New Deal policy vis-à-vis its scientific work?After outlining some characteristics of American Legal Realism and Lakatos’s concept, the author studies LR from this perspective and concludes that LR can at the maximum be seen as a research programme of a very rudimentary nature with largely only a focus on procedures/methods. Despite this conclusion, LR has been important in stimulating questions in which social science research and law came together. Next, the professor-realist-relationship that helped President Roosevelt to have his New Deal developed and implemented is also discussed. A downside of this ‘professor-realist-advisor-partnership’ may have been that a LR scientific research programme has not been developed. Given the increased visibility of New Legal Realism, the paper finally stresses the relevance of working with scientific research programmes and the importance of being on the alert when linking research to (legal policies.

JYT - Publicly financed nuclear waste management research programme

International Nuclear Information System (INIS)

Vuori, S.

1992-07-01

The nuclear waste management research in Finland is funded both by the state and the utilities (represented in cooperation by the Nuclear Waste Commission of the Finnish power companies). A coordinated research programme (JYT) comprising the publicly financed waste management studies was started in 1989 and continues until 1993. The utilities continue to carry out a parallel research programme according to their main financial and operational responsibility for nuclear waste management. The research programme covers the following main topic areas: (1) Bedrock characteristics, groundwater and repository, (2) Release and transport of radionuclides, (3) Performance and safety assessment of repositories, and (4) Waste management technology and costs

JYT - Publicly financed nuclear waste management research programme

International Nuclear Information System (INIS)

Vuori, S.

1993-06-01

The nuclear waste management research in Finland is funded both by the state and the utilities (represented in cooperation by the Nuclear Waste Commission of the Finnish power companies). A coordinated research programme (JYT) comprising the publicly financed waste management studies was started in 1989 and continues until 1993. The utilities continue to carry out a parallel research programme according to their main financial and operational responsibility for nuclear waste management. The research programme covers the following main topic areas: (1) Bedrock characteristics, groundwater and repository, (2) Release and transport of radionuclides, (3) Performance and safety assessment of repositories, and (4) Waste management technology and costs

JYT - Publicly financed nuclear waste management research programme

International Nuclear Information System (INIS)

Vuori, S.

1991-07-01

The nuclear waste management research in Finland is funded both by the state and the utilities (represented in cooperation by the Nuclear Waste Commission of the Finnish power companies). A coordinated research programme (JYT) comprising the publicly financed waste management studies was started in 1989 and continues until 1993. The utilities continue to carry out a parallel research programme according to their main financial and operational responsibility for nuclear waste management. The research programme covers the following main topic areas: (1) Bedrock characteristics, groundwater and repository, (2) Release and transport of radionuclides, (3) Performance and safety assessment of repositories, and (4) Waste management technology and costs

Évolution des contraintes résiduelles dans la couche de diffusion d’un acier modèle Fe-Cr-C nitruré

DEFF Research Database (Denmark)

Jegou, Sébastien; Barrallier, Laurent; Somers, Marcel A. J.

2011-01-01

Limiter la fatigue et la corrosion des pièces est possible grâce à une nitruration. Des contraintes résiduelles en découlent. Le rôle de la diffusion du carbone sur le développement de ces contraintes a été étudié sur un acier modèle Fe-3%m.Cr-0.35%m.C.......Limiter la fatigue et la corrosion des pièces est possible grâce à une nitruration. Des contraintes résiduelles en découlent. Le rôle de la diffusion du carbone sur le développement de ces contraintes a été étudié sur un acier modèle Fe-3%m.Cr-0.35%m.C....

Molybdate binding by ModA, the periplasmic component of the Escherichia coli mod molybdate transport system.

Science.gov (United States)

Imperial, J; Hadi, M; Amy, N K

1998-03-13

ModA, the periplasmic-binding protein of the Escherichia coli mod transport system was overexpressed and purified. Binding of molybdate and tungstate to ModA was found to modify the UV absorption and fluorescence emission spectra of the protein. Titration of these changes showed that ModA binds molybdate and tungstate in a 1:1 molar ratio. ModA showed an intrinsic fluorescence emission spectrum attributable to its three tryptophanyl residues. Molybdate binding caused a conformational change in the protein characterized by: (i) a shift of tryptophanyl groups to a more hydrophobic environment; (ii) a quenching (at pH 5.0) or enhancement (at pH 7.8) of fluorescence; and (iii) a higher availability of tryptophanyl groups to the polar quencher acrylamide. The tight binding of molybdate did not allow an accurate estimation of the binding constants by these indirect methods. An isotopic binding method with 99MoO42- was used for accurate determination of KD (20 nM) and stoichiometry (1:1 molar ratio). ModA bound tungstate with approximately the same affinity, but did not bind sulfate or phosphate. These KDs are 150- to 250-fold lower than those previously reported, and compatible with the high molybdate transport affinity of the mod system. The affinity of ModA for molybdate was also determined in vivo and found to be similar to that determined in vitro. Copyright 1998 Elsevier Science B.V.

South African Antarctic earth science research programme

CSIR Research Space (South Africa)

SASCAR

1984-02-01

Full Text Available This document describes the past, current and planned future South African earth science research programme in the Antarctic, Southern Ocean and subantarctic regions. The scientific programme comprises five components into which present and future...

Analysis of 4-strap ICRF Antenna Performance in Alcator C-Mod

International Nuclear Information System (INIS)

Schilling, G.; Wukitch, S.J.; Boivin, R.L.; Goetz, J.A.; Hosea, J.C.; Irby, J.H.; Lin, Y.; Parisot, A.; Porkolab, M.; Wilson, J.R.

2003-01-01

A 4-strap ICRF antenna was designed and fabricated for plasma heating and current drive in the Alcator C-Mod tokamak. Initial upgrades were carried out in 2000 and 2001, which eliminated surface arcing between the metallic protection tiles and reduced plasma-wall interactions at the antenna front surface. A boron nitride septum was added at the antenna midplane to intersect electric fields resulting from radio-frequency sheath rectification, which eliminated antenna corner heating at high power levels. The current feeds to the radiating straps were reoriented from an E||B to E parallel B geometry, avoiding the empirically observed ∼15 kV/cm field limit and raising antenna voltage holding capability. Further modifications were carried out in 2002 and 2003. These included changes to the antenna current strap, the boron nitride tile mounting geometry, and shielding the BN-metal interface from the plasma. The antenna heating efficiency, power, and voltage characteristics under these various configurations will be presented

The multi-spectral line-polarization MSE system on Alcator C-Mod

Energy Technology Data Exchange (ETDEWEB)

Mumgaard, R. T., E-mail: mumgaard@psfc.mit.edu; Khoury, M. [Plasma Science and Fusion Center, Massachusetts Institute of Technology, Cambridge, Massachusetts 02139 (United States); Scott, S. D. [Princeton Plasma Physics Laboratory, Princeton, New Jersey 08540 (United States)

2016-11-15

A multi-spectral line-polarization motional Stark effect (MSE-MSLP) diagnostic has been developed for the Alcator C-Mod tokamak wherein the Stokes vector is measured in multiple wavelength bands simultaneously on the same sightline to enable better polarized background subtraction. A ten-sightline, four wavelength MSE-MSLP detector system was designed, constructed, and qualified. This system consists of a high-throughput polychromator for each sightline designed to provide large étendue and precise spectral filtering in a cost-effective manner. Each polychromator utilizes four narrow bandpass interference filters and four custom large diameter avalanche photodiode detectors. Two filters collect light to the red and blue of the MSE emission spectrum while the remaining two filters collect the beam pi and sigma emission generated at the same viewing volume. The filter wavelengths are temperature tuned using custom ovens in an automated manner. All system functions are remote controllable and the system can be easily retrofitted to existing single-wavelength line-polarization MSE systems.

The multi-spectral line-polarization MSE system on Alcator C-Mod

International Nuclear Information System (INIS)

Mumgaard, R. T.; Khoury, M.; Scott, S. D.

2016-01-01

A multi-spectral line-polarization motional Stark effect (MSE-MSLP) diagnostic has been developed for the Alcator C-Mod tokamak wherein the Stokes vector is measured in multiple wavelength bands simultaneously on the same sightline to enable better polarized background subtraction. A ten-sightline, four wavelength MSE-MSLP detector system was designed, constructed, and qualified. This system consists of a high-throughput polychromator for each sightline designed to provide large étendue and precise spectral filtering in a cost-effective manner. Each polychromator utilizes four narrow bandpass interference filters and four custom large diameter avalanche photodiode detectors. Two filters collect light to the red and blue of the MSE emission spectrum while the remaining two filters collect the beam pi and sigma emission generated at the same viewing volume. The filter wavelengths are temperature tuned using custom ovens in an automated manner. All system functions are remote controllable and the system can be easily retrofitted to existing single-wavelength line-polarization MSE systems.

Density limit and cross-field edge transport scaling in Alcator C-Mod

International Nuclear Information System (INIS)

LaBombard, B.; Greenwald, M.; Hughes, J.W.; Lipschultz, B.; Mossessian, D.; Terry, J.L.; Boivin, R.L.; Carreras, B.A.; Pitcher, C.S.; Zweben, S.J.

2003-01-01

Recent experiments in Alcator C-Mod have uncovered a direct link between the character and scaling of cross-field particle transport in the edge plasma and the density limit, n G . As n-bar e /n G is increased from low values to values approaching ∼1, an ordered progression in the cross-field edge transport physics occurs: first benign cross-field heat convection, then cross-field heat convection impacting the scrape-off layer (SOL) power loss channels and reducing the separatrix electron temperature, and finally 'bursty' transport (normally associated with the far SOL) invading into closed flux surface regions and carrying a convective power loss that impacts the power balance of the discharge. These observations suggest that SOL transport and its scaling with plasma conditions plays a key role in setting the empirically observed density limit scaling law. (author)

Field Programmable Gate Array-based I and C Safety System

International Nuclear Information System (INIS)

Kim, Hyun Jeong; Kim, Koh Eun; Kim, Young Geul; Kwon, Jong Soo

2014-01-01

Programmable Logic Controller (PLC)-based I and C safety system used in the operating nuclear power plants has the disadvantages of the Common Cause Failure (CCF), high maintenance costs and quick obsolescence, and then it is necessary to develop the other platform to replace the PLC. The Field Programmable Gate Array (FPGA)-based Instrument and Control (I and C) safety system is safer and more economical than Programmable Logic Controller (PLC)-based I and C safety system. Therefore, in the future, FPGA-based I and C safety system will be able to replace the PLC-based I and C safety system in the operating and the new nuclear power plants to get benefited from its safety and economic advantage. FPGA-based I and C safety system shall be implemented and verified by applying the related requirements to perform the safety function

Field Programmable Gate Array-based I and C Safety System

Energy Technology Data Exchange (ETDEWEB)

Kim, Hyun Jeong; Kim, Koh Eun; Kim, Young Geul; Kwon, Jong Soo [KEPCO, Daejeon (Korea, Republic of)

2014-08-15

Programmable Logic Controller (PLC)-based I and C safety system used in the operating nuclear power plants has the disadvantages of the Common Cause Failure (CCF), high maintenance costs and quick obsolescence, and then it is necessary to develop the other platform to replace the PLC. The Field Programmable Gate Array (FPGA)-based Instrument and Control (I and C) safety system is safer and more economical than Programmable Logic Controller (PLC)-based I and C safety system. Therefore, in the future, FPGA-based I and C safety system will be able to replace the PLC-based I and C safety system in the operating and the new nuclear power plants to get benefited from its safety and economic advantage. FPGA-based I and C safety system shall be implemented and verified by applying the related requirements to perform the safety function.

Research and training programmes

Directory of Open Access Journals (Sweden)

Daksha Patel

2007-03-01

Full Text Available Research is defined in the Oxford English Dictionary as “a systematic investigation and study of materials and sources in order to establish facts and reach new conclusions.”Research is embedded in the curricula of most postgraduate training programmes; students are expected to complete some form of original work towards a dissertation. This often evokes a range of reactions: “What is the purpose of this exercise? Why do I have to do research when I just want to do a job? Shouldn’t research rather be left to experts? I can’t do the course; I have no research background!”

Multispecies density peaking in gyrokinetic turbulence simulations of low collisionality Alcator C-Mod plasmas

Energy Technology Data Exchange (ETDEWEB)

Mikkelsen, D. R., E-mail: dmikkelsen@pppl.gov; Bitter, M.; Delgado-Aparicio, L.; Hill, K. W. [Princeton Plasma Physics Laboratory, P.O. Box 451, Princeton, New Jersey 08543 (United States); Greenwald, M.; Howard, N. T.; Hughes, J. W.; Rice, J. E. [MIT Plasma Science and Fusion Center, 175 Albany St., Cambridge, Massachusetts 02139 (United States); Reinke, M. L. [MIT Plasma Science and Fusion Center, 175 Albany St., Cambridge, Massachusetts 02139 (United States); York Plasma Institute, Department of Physics, University of York, Heslington, York YO10 5DD (United Kingdom); Podpaly, Y. [MIT Plasma Science and Fusion Center, 175 Albany St., Cambridge, Massachusetts 02139 (United States); AAAS S and T Fellow placed in the Directorate for Engineering, NSF, 4201 Wilson Blvd., Arlington, Virginia 22230 (United States); Ma, Y. [MIT Plasma Science and Fusion Center, 175 Albany St., Cambridge, Massachusetts 02139 (United States); ITER Organization, Route de Vinon-sur-Verdon, CS 90 046, 13067 St Paul Lez Durance Cedex (France); Candy, J.; Waltz, R. E. [General Atomics, P.O. Box 85608, San Diego, California 92186-5608 (United States)

2015-06-15

Peaked density profiles in low-collisionality AUG and JET H-mode plasmas are probably caused by a turbulently driven particle pinch, and Alcator C-Mod experiments confirmed that collisionality is a critical parameter. Density peaking in reactors could produce a number of important effects, some beneficial, such as enhanced fusion power and transport of fuel ions from the edge to the core, while others are undesirable, such as lower beta limits, reduced radiation from the plasma edge, and consequently higher divertor heat loads. Fundamental understanding of the pinch will enable planning to optimize these impacts. We show that density peaking is predicted by nonlinear gyrokinetic turbulence simulations based on measured profile data from low collisionality H-mode plasma in Alcator C-Mod. Multiple ion species are included to determine whether hydrogenic density peaking has an isotope dependence or is influenced by typical levels of low-Z impurities, and whether impurity density peaking depends on the species. We find that the deuterium density profile is slightly more peaked than that of hydrogen, and that experimentally relevant levels of boron have no appreciable effect on hydrogenic density peaking. The ratio of density at r/a = 0.44 to that at r/a = 0.74 is 1.2 for the majority D and minority H ions (and for electrons), and increases with impurity Z: 1.1 for helium, 1.15 for boron, 1.3 for neon, 1.4 for argon, and 1.5 for molybdenum. The ion temperature profile is varied to match better the predicted heat flux with the experimental transport analysis, but the resulting factor of two change in heat transport has only a weak effect on the predicted density peaking.

Graduate nuclear engineering programmes motivate educational and research activities

International Nuclear Information System (INIS)

Mavko, B.

2000-01-01

Some fifteen years ago the University of Ljubljana, Faculty for Mathematics and Physics together with the national research organisation the J. Stefan jointly established a Graduate programme of Nuclear Engineering. From the onset, the programme focused on nuclear technology, nuclear safety, and reactor physics and environment protection. Over the years this graduate programme has became the focal point of nuclear related, research and educational activities in Slovenia. It has grown into a meeting ground for recognised national and distinguished foreign educators and experienced professionals from the industry. In conjunction with an important national project, supported by the Slovenian government, entitled 'Jung Researcher' it also enhances the knowledge transfer to the next generation. Since the programme was introduced, the interest for this programme has been steadily growing. Accordingly, a number of PhD and MS degrees in NE have been awarded. The graduates of this programme have encountered very good job opportunities in nuclear as well as in non-nuclear sector. (author)

Safety analysis of loss of flow transients in a typical research reactor by RELAP5/MOD3.3

International Nuclear Information System (INIS)

Di Maro, B.; Pierro, F.; Adorni, M.; Bousbia Salah, A.; D'Auria, F.

2003-01-01

The main aim of the following study is to assess the RELAP5/MOD3.3 code capability in simulating transient dynamic behaviour in nuclear research reactors. For this purpose typical loss of flow transient in a representative MTR (Metal Test Reactor) fuel type Research Reactor is considered. The transient herein considered is a sudden pump trip followed by the opening of a safety valve in order to allow passive decay heat removal by natural convection. During such transient the coolant flow decay, originally downward, leads to a flow reversal and the cooling process of the core passes from forced, mixed and finally to natural circulation. This fact makes it suitable for evaluating the new features of RELAP5 to simulate such specific operating conditions. The instantaneous reactor power is derived through the point kinetic calculation, both protected and unprotected cases are considered (with and without Scram). The results obtained from this analysis were also compared with previous results obtained by old version RELAP5/MOD2 code. (author)

Overexpression, purification, and partial characterization of ADP-ribosyltransferases modA and modB of bacteriophage T4.

Science.gov (United States)

Tiemann, B; Depping, R; Rüger, W

1999-01-01

There is increasing experimental evidence that ADP-ribosylation of host proteins is an important means to regulate gene expression of bacteriophage T4. Surprisingly, this phage codes for three different ADP-ribosyltransferases, gene products Alt, ModA, and ModB, modifying partially overlapping sets of host proteins. While gene product Alt already has been isolated as a recombinant protein and its action on host RNA polymerases and transcription regulation have been studied, the nucleotide sequences of the two mod genes was published only recently. Their mode of action in the course of the infection cycle and the consequences of the ADP-ribosylations catalyzed by these enzymes remain to be investigated. Here we describe the cloning of the genes, the overexpression, purification, and partial characterization of ADP-ribosyltransferases ModA and ModB. Both proteins seem to act independently, and the ADP-ribosyl moieties are transferred to different sets of host proteins. While gene product ModA, similarly to the Alt protein, acts also on the alpha-subunit of host RNA polymerase, the ModB activity serves another set of proteins, one of which was identified as the S1 protein associated with the 30S subunit of the E. coli ribosomes.

Research capacity building in midwifery: Case study of an Australian Graduate Midwifery Research Intern Programme.

Science.gov (United States)

Hauck, Yvonne L; Lewis, Lucy; Bayes, Sara; Keyes, Louise

2015-09-01

Having the research capacity to identify problems, create new knowledge and most importantly translate this knowledge into practice is essential within health care. Midwifery, as well as other health professions in Australia, is challenged in building its research capacity to contribute evidence to inform clinical practice. The aim of this project was to evaluate an innovative Graduate Midwifery Research Intern Programme offered at a tertiary obstetric hospital in Western Australia, to determine what was working well and how the programme could be improved. A case study approach was used to gain feedback from graduate midwives within a Graduate Research Intern (GRI) Programme. In addition outcomes were compiled of all projects the GRI midwives contributed to. Six GRI midwives participated in a survey comprising of four open ended questions to provide feedback about the programme. Findings confirm that the GRI programme increased the graduates understanding of how research works, its capacity to define a problem, generate new knowledge and inform clinical practice. The GRI midwives' feedback suggested the programme opened their thinking to future study and gave them enhanced insight into women's experiences around childbirth. To grow our knowledge as a professional group, midwives must develop and promote programmes to build our pool of research capable midwives. By sharing our programme evaluation we hope to entice other clinical settings to consider the value in replicating such a programme within their context. Copyright © 2015 Australian College of Midwives. Published by Elsevier Ltd. All rights reserved.

A Computational Architecture for Programmable Automation Research

Science.gov (United States)

Taylor, Russell H.; Korein, James U.; Maier, Georg E.; Durfee, Lawrence F.

1987-03-01

This short paper describes recent work at the IBM T. J. Watson Research Center directed at developing a highly flexible computational architecture for research on sensor-based programmable automation. The system described here has been designed with a focus on dynamic configurability, layered user inter-faces and incorporation of sensor-based real time operations into new commands. It is these features which distinguish it from earlier work. The system is cur-rently being implemented at IBM for research purposes and internal use and is an outgrowth of programmable automation research which has been ongoing since 1972 [e.g., 1, 2, 3, 4, 5, 6] .

African Primary Care Research: Performing a programme evaluation

OpenAIRE

Dudley, Lilian

2014-01-01

Abstract This article is part of a series on Primary Care Research in the African context and focuses on programme evaluation. Different types of programme evaluation are outlined: developmental, process, outcome and impact. Eight steps to follow in designing your programme evaluation are then described in some detail: engage stakeholders; establish what is known; describe the programme; define the evaluation and select a study design; define the indicators; plan and manage data collection an...

Quick look report for semiscale MOD-2C Test S-FS-11

International Nuclear Information System (INIS)

Plessinger, M.P.

1985-11-01

Results of a preliminary analysis of the fifth test performed in the Semiscale MOD-2C Steam Generator Feedwater and Steam Line Break (FS) experiment series are presented. Test S-FS-11 simulated a pressurized water reactor transient initiated by a 50% break in a steam generator bottom feedwater line downstream of the check valve. With the exception of primary pressure, the initial conditions represented the initial conditions used for the C-E System 80 Final Safety Analysis Report (FSAR) Appendix 15B calculations. The transient included an initial 600 s period in which only automatic plant protection systems responded to the initiating event. This period was followed by a series of operator actions necessary to stabilize the plant followed by break isolation and affected loop steam generator refill with auxiliary feedwater. The test results provided a measured evaluation of the effectiveness of the automatic responses in minimizing primary system overpressurization and operator actions in stabilizing the plant. Test data also provided a basis for comparison with other tests in the series of the effects of break size on primary overpressurization and primary-to-secondary heat transfer. 64 figs

Validation of neutral point on JT-60U, Alcator C-Mod and ASDEX-Upgrade tokamaks

International Nuclear Information System (INIS)

Nakamura, Yukiharu; Yoshino, Ryuji; Pautasso, Gabriella; Gruber, Otto; Jardin, Stephen

2002-01-01

Validation studies of a neutrally balanced vertical plasma position, so-called ''neutral point'', have been carried out by computational simulations and experiments under trilateral Japan-US-EU collaborations. It was clarified that the neutral point, where VDEs (Vertical Displacement Events) are hardly occurred, does exit in the Alcator C-Mod and ASDEX-Upgrade tokamaks as well as the JT-60U, consistent with the simulations. Meanwhile, precise details of the VDE behavior exhibit their own characters according to the individual of the tokamaks such as an up-down asymmetry of plasma shape. Sensitivity of the neutral point to the plasma shape and current profile was also addressed in detail. (author)

South African antarctic biological research programme

CSIR Research Space (South Africa)

SASCAR

1981-07-01

Full Text Available This document provides a description of the past, current and planned South African biological research activities in the sub-Antarctic and Antarctic regions. Future activities will fall under one of the five components of the research programme...

Investigation of an inventory calculation model for a solvent extraction system and the development of its computer programme - SEPHIS-J

International Nuclear Information System (INIS)

Ihara, Hitoshi; Nishimura, Hideo; Ikawa, Koji; Ido, Masaru.

1986-11-01

In order to improve the applicability of near-real-time materials accountancy (N.R.T.MA) to a reprocessing plant, it is necessary to develop an estimation method for the nuclear material inventory at a solvent extraction system under operation. For designing the solvent extraction system, such computer codes as SEPHIS, SOLVEX and TRANSIENTS had been used. Accuracy of these codes in tracing operations and predicting inventories in the extraction system had been discussed. Then, much better codes, e.g., SEPHIS Mod4 and PUBG, were developed. Unfortunately, SEPHIS Mod4 was not available in countries other than the USA and PUBG was not suitable for use with a mini-computer which would be practical as a field computer because of quite a lot of computing time needed. The authors investigated an inventory estimation model compatible with PUBG in functions and developed the corresponding computer programme, SEPHIS-J, based on the SEPHIS Mod3 code, resulting in a third of computing time compared with PUBG. They also validated the programme by calculating a static state as well as a dynamic one of the solvent extraction process and by comparing them among the programme, SEPHIS Mod3 and PUBG. Using the programme, it was shown that the inventory changes due to changes of feed flow and concentration were not so small that they might be neglected although the changes of feed flow and concentration were within measurement errors. (author)

European Association of Echocardiography: Research Grant Programme.

Science.gov (United States)

Gargani, Luna; Muraru, Denisa; Badano, Luigi P; Lancellotti, Patrizio; Sicari, Rosa

2012-01-01

The European Society of Cardiology (ESC) offers a variety of grants/fellowships to help young professionals in the field of cardiological training or research activities throughout Europe. The number of grants has significantly increased in recent years with contributions from the Associations, Working Groups and Councils of the ESC. The European Association of Echocardiography (EAE) is a registered branch of the ESC and actively takes part in this initiative. One of the aims of EAE is to promote excellence in research in cardiovascular ultrasound and other imaging modalities in Europe. Therefore, since 2008, the EAE offers a Research Grant Programme to help young doctors to obtain research experience in a high standard academic centre (or similar institution oriented to clinical or pre-clinical research) in an ESC member country other than their own. This programme can be considered as a valorization of the geographical mobility as well as cultural exchanges and professional practice in the field of cardiovascular imaging. The programme has been very successful so far, therefore in 2012 the EAE has increased its offer to two grants of 25,000 euros per annum each.

Research on nuclear energy within the European Commission Research Framework Programme

International Nuclear Information System (INIS)

Forsstroem, H.

2000-01-01

The strategic goal of the 5 th EURATOM RTD Framework Programme (FP5) is to help exploit the full potential of nuclear energy in a sustainable manner, by making current technologies even safer and more economical and by exploring promising new concepts. The programme covers nuclear fusion, nuclear fission and radiation protection. Part of the programme on nuclear fission and radiation protection is being implemented through ''indirect actions'', i.e. research co-sponsored (up to 50% of total costs) and co-ordinated by DG RESEARCH of the European Commission (EC) but carried out by external public and private organisations as multi-partner projects. The budget available for these indirect actions during FP5 (1998-2002) is 191 MEuro. The programme covers four different areas: safety of existing reactors, including plant life management, severe accident management and development of evolutionary systems; safety of the fuel cycle, including radioactive waste management and disposal, partitioning and transmutation and decommissioning of nuclear installation; safety of future systems, including new or revisited reactor or fuel cycle concepts; radiation protection and radiological sciences, including both basic radiobiology and radiophysics and issues connected to the application of radiation protection. After the first calls for proposals of FP5, which were evaluated in 1999 about 140 research projects have been selected for funding and is now in the process of starting. In parallel the research projects that were supported in the 4th Framework Programme (1994 - 1998) are coming to an end, and being reported, at the same time as the first thoughts on the 6 t h FP are discussed.An important new component for the future research in Europe is the concept of a European Research Area (ERA). The purpose of ERA is to create better overall framework conditions for research in Europe. Some of the concepts being discussed in this context are networking of centres of excellence, a

Modélisation environnementale de l'estuaire de la Seine

OpenAIRE

Bacq, Nicolas; Cugier, Philippe; Grasso, Florent; Le Gendre, Romain; Le Hir, Pierre; Lemoine, Jean-philippe; Riou, Philippe; Schulz, Elisabeth; Thouvenin, Benedicte; Verney, Romaric

2015-01-01

Dans le cadre du programme de recherche Seine-Aval 5, différentes stratégies de modélisation numérique sont mises en place pour aider à répondre aux questionnements scientifiques et sociétaux associés au fonctionnement physique, biologique, chimique et écologique de l'estuaire de la Seine (ex. projets RESET et HYMOSED). Les forçages météo-marins (vent, vague, marée) et hydrologique (débit) contrôlent le fonctionnement hydro-morpho-sédimentaire et biogéochimique de l'estuaire, modifiant ainsi ...

Assessment of RELAP5/MOD2 and RELAP5/MOD1-EUR codes on the basis of LOBI-MOD2 test results

International Nuclear Information System (INIS)

D'Auria, F.; Mazzini, M.; Oriolo, F.; Galassi, G.M.

1989-10-01

The present report deals with an overview of the application of RELAP5/MOD2 and RELAP5/MOD1-EUR codes to tests performed in the LOBI/MOD2 facility. The work has been carried out in the frame of a contract between Dipartimento di Costruzioni Meccaniche e Nucleari (DCMN) of Pisa University and CEC. The Universities of Roma, Pisa, Bologna and Palermo and the Polytechnic of Torino performed the post-test analysis of the LOBI experiment under the supervision of DCMN. In the report the main outcomes from the analysis of the LOBI experiments are given with the attempt to identify deficiencies in the modelling capabilities of the used codes

Upgrades to the 4-strap ICRF Antenna in Alcator C-Mod

International Nuclear Information System (INIS)

G. Schilling; J.C. Hosea; J.R. Wilson; W. Beck; R.L. Boivin; P.T. Bonoli; D. Gwinn; W.D. Lee; E. Nelson-Melby; M. Porkolab; R. Vieira; S.J. Wukitch; J.A. Goetz

2001-01-01

A 4-strap ICRF antenna suitable for plasma heating and current drive has been designed and fabricated for the Alcator C-Mod tokamak. Initial operation in plasma was limited by high metallic impurity injection resulting from front surface arcing between protection tiles and from current straps to Faraday shields. Antenna modifications were made in February 2000, resulting in impurity reduction, but low-heating efficiency was observed when the antenna was operated in its 4-strap rather than a 2-strap configuration. Further modifications were made in July 2000, with the installation of BN plasma-facing tiles and radio- frequency bypassing of the antenna backplane edges and ends to reduce potential leakage coupling to plasma surface modes. Good heating efficiency was now observed in both heating configurations, but coupled power was limited to 2.5 MW in H-mode, 3 MW in L-mode, by plasma-wall interactions. Additional modifications were started in February 2001 and will be completed by this meeting. All the above upgrades and their effect on antenna performance will be presented

Impurity toroidal rotation and transport in Alcator C-Mod ohmic high confinement mode plasmas

International Nuclear Information System (INIS)

Rice, J. E.; Goetz, J. A.; Granetz, R. S.; Greenwald, M. J.; Hubbard, A. E.; Hutchinson, I. H.; Marmar, E. S.; Mossessian, D.; Pedersen, T. Sunn; Snipes, J. A.

2000-01-01

Central toroidal rotation and impurity transport coefficients have been determined in Alcator C-Mod [I. H. Hutchinson et al., Phys. Plasmas 1, 1511 (1994)] Ohmic high confinement mode (H-mode) plasmas from observations of x-ray emission following impurity injection. Rotation velocities up to 3x10 4 m/sec in the co-current direction have been observed in the center of the best Ohmic H-mode plasmas. Purely ohmic H-mode plasmas display many characteristics similar to ion cyclotron range of frequencies (ICRF) heated H-mode plasmas, including the scaling of the rotation velocity with plasma parameters and the formation of edge pedestals in the electron density and temperature profiles. Very long impurity confinement times (∼1 sec) are seen in edge localized mode-free (ELM-free) Ohmic H-modes and the inward impurity convection velocity profile has been determined to be close to the calculated neoclassical profile. (c) 2000 American Institute of Physics

Publicly administrated nuclear waste management research programme 1994-1996. General plan for the research programme and research plan for 1994

International Nuclear Information System (INIS)

1994-01-01

The nuclear energy legislation of Finland includes detailed stipulations concerning nuclear waste management. Each producer of nuclear waste is responsible for the safe handling, management and disposal of the waste, and for the financing of these operations. The authorities supervise and control the implementation of the national waste management programme and set the necessary safety and other requirements. The principal goal of the JYT programme is to provide the authorities with information and research results relevant for the safety of nuclear waste management in order to support the various activities of the authorities. The whole field of the research programme is subdivided into the following main topic areas: (1) bedrock structure and stability, rock investigation methods, and characteristics and flow of groundwater, (2) release of radionuclides from a repository and subsequent migration in the bedrock, (3) performance and safety assessment of repositories and other phases of nuclear waste management (4) natural analogue studies, (5) waste management technology and costs and (6) sociopolitical and other societal issues and environmental impact assessment

Quick Look Report for Semiscale MOD-2C Test S-FS-2

International Nuclear Information System (INIS)

Boucher, T.J.; Chen, T.H.

1985-01-01

Results of a preliminary analysis of the first test performed in the Semiscale MOD-2C Steam Generator Feedwater and Steam Line Break (FS) experiment series are presented. Test S-FS-2 simulated a pressurized water reactor transient initiated by a double-ended offset shear of a steam generator main steam line upstream of the flow restrictor. Initial conditions represented normal ''hot-standby'' operation. The transient included an initial 600-s period in which only automatic plant protection systems responded to the initiating event. This period was followed by a series of operator actions necessary to stabilize the plant at conditions required to allow a natural circulation cooldown. The test results provided a measured evaluation of the effectiveness of the automatic responses in minimizing primary system overcooling and operator actions in stabilizing the plant. Test data also provided a basis for comparison with other tests in the series of the effects of break size on primary overcooling and primary-to-secondary heat transfer. 57 figs., 3 tabs

Marine line fish research programme

CSIR Research Space (South Africa)

SANCOR

1979-04-01

Full Text Available This report outlines the framework for a marine line fish programme under the aegis of the South African National Committee for Oceanographic Research (SANCOR). An attempt is made to assess the state of knowledge about South African marine line...

Utilisation d'un modèle distribué sur un petit bassin versant de savane (Booro-Borotou, Côte d'Ivoire)

OpenAIRE

Chevallier, Pierre; Girard, Georges

1990-01-01

Le programme Hyperbav a pour cadre un petit bassin versant du Nord-Ouest de la Côte d'Ivoire. Sur une superficie de 136 hectares des observations fines ont été conduites de 1984 à 1988 sur toutes les grandeurs intéressant le fonctionnement hydrique (hydrologie, climatologie, pédologie, hydrogéologie, botanique, agronomie). Il est intéressant de tenter d'intégrer ces informnations dans une représentation modéliste des échanges hydriques superficiels et internes. Le "modèle couplé" développé co...

Summer Research Fellowship Programme – 2015

Indian Academy of Sciences (India)

IAS Admin

2014-11-20

Nov 20, 2014 ... Jawaharlal Nehru Centre for Advanced Scientific Research invites applications for its Summer. Research Fellowship Programme – 2015, for motivated and talented Indian students in Science and Engineering. Detailed information and application form can be downloaded from http://www.jncasr.ac.in/fe/srfp.

Start of new Research and Innovation Programme, Horizon 2020

CERN Multimedia

2013-01-01

The overall EU budget for 2014-2020 was approved on 20 November, with €79 billion allocated for the Horizon 2020 Research and Innovation programme.   The first calls and final work programmes in Horizon 2020 will be published on 11 December 2013 and the programme will officially start on 1 January 2014. In preparation for the next major programme, the CERN EU Projects Office has launched a redesigned website to keep you informed and to alert you to opportunities in Horizon 2020: cerneu.web.cern.ch. Organised by Euresearch, the Swiss launch event will take place from 14 to 17 January 2014. This four-day conference will offer the possibility to discover the new European Framework Programme for Research and Innovation. The event is open for registration: www.launch-h2020.ch.

The Nirex safety assessment research programme

International Nuclear Information System (INIS)

Cooper, M.J.

1988-07-01

This report describes progress on the Nirex Safety Assessment Research Programme in 1987/88. The programme is concerned with research into the disposal of low-level waste (LLW) and intermediate-level waste (ILW) into underground repositories. At the beginning of 1987/88 a range of techniques for measuring and modelling far-field phenomena were being applied to near-surface disposal of low-level waste in clay. However, during the year the far-field studies were redirected to consider generic geological materials of interest for deep disposal of low and intermediate-level waste, which is now the preferred option in the UK. A substantial part of the programme is concerned with the effectiveness of near-field barriers to water-borne leakage of radionuclides from cementitious repositories. Considerable progress has been made in quantifying this and laying the foundations for robust and reliable radiological assessments to be made with appropriate models. New projects have also been initiated to study the evolution and migration of gases from an underground repository and to consider the contribution of the biosphere to the retardation of radionuclides. (author)

Parallel transport studies of high-Z impurities in the core of Alcator C-Mod plasmas

Energy Technology Data Exchange (ETDEWEB)

Reinke, M. L.; Hutchinson, I. H.; Rice, J. E.; Greenwald, M.; Howard, N. T.; Hubbard, A.; Hughes, J. W.; Terry, J. L.; Wolfe, S. M. [MIT-Plasma Science and Fusion Center Cambridge, Massachusetts 02139 (United States)

2013-05-15

Measurements of poloidal variation, ñ{sub z}/, in high-Z impurity density have been made using photodiode arrays sensitive to vacuum ultraviolet and soft x-ray emission in Alcator C-Mod plasmas. In/out asymmetries in the range of −0.2<0.3 are observed for r/a<0.8, and accumulation on both the high-field side, n{sub z,cos}<0, and low-field side, n{sub z,cos}>0, of a flux surface is found to be well described by a combination of centrifugal, poloidal electric field, and ion-impurity friction effects. Up/down asymmetries, −0.05<0.10, are observed over 0.50 corresponding to accumulation opposite the ion ∇B drift direction. Measurements of the up/down asymmetry of molybdenum are found to disagree with predictions from recent neoclassical theory in the trace limit, n{sub z}Z{sup 2}/n{sub i}≪1. Non-trace levels of impurities are expected to modify the main-ion poloidal flow and thus change friction-driven impurity density asymmetries and impurity poloidal rotation, v{sub θ,z}. Artificially modifying main-ion flow in parallel transport simulations is shown to impact both ñ{sub z}/ and v{sub θ,z}, but simultaneous agreement between measured and predicted up/down and in/out asymmetry as well as impurity poloidal rotation is not possible for these C-Mod data. This link between poloidal flow and poloidal impurity density variation outlines a more stringent test for parallel neoclassical transport theory than has previously been performed. Measurement and computational techniques specific to the study of poloidal impurity asymmetry physics are discussed as well.

Expression, purification and DNA-binding activities of two putative ModE proteins of Herbaspirillum seropedicae (Burkholderiales, Oxalobacteraceae

Directory of Open Access Journals (Sweden)

André L.F. Souza

2008-01-01

Full Text Available In prokaryotes molybdenum is taken up by a high-affinity ABC-type transporter system encoded by the modABC genes. The endophyte β-Proteobacterium Herbaspirillum seropedicae has two modABC gene clusters and two genes encoding putative Mo-dependent regulator proteins (ModE1 and ModE2. Analysis of the amino acid sequence of the ModE1 protein of H. seropedicae revealed the presence of an N-terminal domain containing a DNA-binding helix-turn-helix motif (HTH and a C-terminal domain with a molybdate-binding motif. The second putative regulator protein, ModE2, contains only the helix-turn-helix motif, similar to that observed in some sequenced genomes. We cloned the modE1 (810 bp and modE2 (372 bp genes and expressed them in Escherichia coli as His-tagged fusion proteins, which we subsequently purified. The over-expressed recombinant His-ModE1 was insoluble and was purified after solubilization with urea and then on-column refolded during affinity chromatography. The His-ModE2 was expressed as a soluble protein and purified by affinity chromatography. These purified proteins were analyzed by DNA band-shift assays using the modA2 promoter region as probe. Our results indicate that His-ModE1 and His-ModE2 are able to bind to the modA2 promoter region, suggesting that both proteins may play a role in the regulation of molybdenum uptake and metabolism in H. seropedicae.

Nitrogen Research Programme STOP

International Nuclear Information System (INIS)

Erisman, J.W.; Van der Eerden, L.

2000-01-01

Nitrogen pollution is one of the main threats to the environment now in the Netherlands as well as other parts of Europe. In order to address the main gaps on the issues of nitrogen pollution related to the local scale, the Ministries of Housing, Physical Planning and Environment (VROM) and of Agriculture, Nature Management and Fisheries (LNV) have initiated a research programme, the Dutch Nitrogen Research Programme (STOP), which aims to provide a scientific basis to develop and implement policy on a local scale for the realisation and conservation of the EHS ('Dutch Mainframe of Natural Landscapes'). The results of the programme show that the description of emissions from manure in the field is difficult to describe and show large uncertainties. On the contrary, emissions from housings could be modelled well, if local actual data were available. The OPS model to describe the dispersion and deposition was evaluated with the measurements and the limitations were quantified. It appears that the model works well on the long term, whereas on the short term (hours) and short distance (tenths of meters) there is large uncertainty, especially in complex terrain. Critical loads for nitrogen for ecosystems were evaluated. Furthermore, the effect of management options was quantified. A method to determine critical loads as a function of soil conditions, such as acidification and water availability was derived. This resulted in a combination of the soil model SMART and the so-called 'nature planner' (Natuurplanner). It was concluded that the combination of SMART, the nature planner and OPS provide a good tool to develop and support policy on the local scale. 4 refs

Nurses' experiences of participation in a research and development programme

DEFF Research Database (Denmark)

Jensen, Kirsten Pryds; Bäck-Pettersson, Siv; Kýlén, Sven

2013-01-01

To describe clinical nurses' experience of participating in a Research and Development (R&D) programme and its influence on their research interest and ability to conduct and apply nursing research......To describe clinical nurses' experience of participating in a Research and Development (R&D) programme and its influence on their research interest and ability to conduct and apply nursing research...

R-HyMOD: an R-package for the hydrological model HyMOD

Science.gov (United States)

Baratti, Emanuele; Montanari, Alberto

2015-04-01

A software code for the implementation of the HyMOD hydrological model [1] is presented. HyMOD is a conceptual lumped rainfall-runoff model that is based on the probability-distributed soil storage capacity principle introduced by R. J. Moore 1985 [2]. The general idea behind this model is to describe the spatial variability of some process parameters as, for instance, the soil structure or the water storage capacities, through probability distribution functions. In HyMOD, the rainfall-runoff process is represented through a nonlinear tank connected with three identical linear tanks in parallel representing the surface flow and a slow-flow tank representing groundwater flow. The model requires the optimization of five parameters: Cmax (the maximum storage capacity within the watershed), β (the degree of spatial variability of the soil moisture capacity within the watershed), α (a factor for partitioning the flow between two series of tanks) and the two residence time parameters of quick-flow and slow-flow tanks, kquick and kslow respectively. Given its relatively simplicity but robustness, the model is widely used in the literature. The input data consist of precipitation and potential evapotranspiration at the given time scale. The R-HyMOD package is composed by a 'canonical' R-function of HyMOD and a fast FORTRAN implementation. The first one can be easily modified and can be used, for instance, for educational purposes; the second part combines the R user friendly interface with a fast processing unit. [1] Boyle D.P. (2000), Multicriteria calibration of hydrological models, Ph.D. dissertation, Dep. of Hydrol. and Water Resour., Univ of Arizona, Tucson. [2] Moore, R.J., (1985), The probability-distributed principle and runoff production at point and basin scale, Hydrol. Sci. J., 30(2), 273-297.

The Russian nuclear data research programme

International Nuclear Information System (INIS)

1995-11-01

The report contains the Russian programme of nuclear data research, approved by the Russian Nuclear Data Committee on 16 December 1994. It gives surveys on nuclear data needs, on the structure of nuclear data activities, on experimental facilities for nuclear data measurements at five Russian institutes, on theoretical model work, nuclear data evaluation, and nuclear data testing. It describes four Russian nuclear data centers and their relations to the International Nuclear Data Centres Network, and their holdings of nuclear data libraries of Russian and international origin. A summary of nuclear data applications in energy and non-energy fields is given. An appendix contains a detail nuclear data research programme for the years 1995 - 2005. (author). 16 refs, 1 fig., 6 tabs

The Community's research and development programme on radioactive waste management and storage

International Nuclear Information System (INIS)

Orlowski, S.; Gandolfo, J.M.

1988-01-01

This is the first annual progress report of the European Community's 1985-89 programme of research on radioactive waste management and disposal, carried out by public organizations and private firms in the Community under cost-sharing contracts with the Commission of the European Communities. The 1985-89 programme is aiming at perfecting and demonstrating a system for managing the radioactive waste produced by the nuclear industry, ensuring at the various stages the best possible protection of man and the environment. This first report describes the work to be carried out under the research contracts already concluded before end of 1986 as well as the initial work performed and the first results obtained. For each contract, paragraph C ''Progress of work and obtained results'' was prepared by the contractor under the responsibility of the project leader

Perspectives d’avenir du modèle autrichien

OpenAIRE

Neisser, Heinrich

2018-01-01

Plusieurs de ceux qui m’ont précédé ont déjà décrit des éléments de ce modèle autrichien qui suscite beaucoup d’intérêt à l’étranger, mais qui – et cela aussi a été signalé un certain nombre de fois – ne peut pas être transposé dans sa totalité à d’autres pays. De tels modèles concrets pour la solution de conflits sociaux naissent à partir d’un certain contexte historique. Ils se développent de manière pragmatique, c’est-à-dire pour résoudre, le mieux possible, des problèmes qui se posent à u...

Radiation protection research and training programme review radiation protection programme 1960-89 synopsis of results 1985-89

International Nuclear Information System (INIS)

1990-01-01

This document aims to trace the evolution of the CEC radiation protection programme over its 30 years of existence. During this time, research carried out in the framework of the Community programme has made major contributions to the scientific understanding of the action of ionizing radiation and the protection of man and his environment. This information was crucial for developing better radiation protection management for existing and new technologies and for providing the scientific basis for the regulatory activities of the Commission. One important feature of the programme was the success of bringing together scientists from different Member States to cooperate in the various fields of radiation protection and to integrate different areas of radiation protection research into a coherent approach. The structures thus developed within the programme have enabled research in radiation protection to be conducted in a cost-effective manner on behalf of the Member States. This document aims also to give a synopsis of the most important results of the 1985-89 radiation protection programme. This period was characterized by two challenges, the integration of two Member States into Community research and the impact of the Chernobyl accident. The programme has, in spite of reduced funding, continued to provide a high degree of expertise for the Community in the context of the needs in radiation protection. This has been explicity acknowledged in the evaluation of the 1980-89 programmes carried out by an independent panel

Present situation of researches on polar ionosphere by C.C.I.R

International Nuclear Information System (INIS)

Ishikawa, Saburo

1974-01-01

Various subjects of studies made by the sixth research committee of C.C.I.R. (International Radio Consultative Committee) are reported. The C.C.I.R. has not any definite study programme and question concerning polar ionosphere, because it studies and delivers opinion on the techniques and operation of radio communication especially in developing countries. The subjects of study programme by the sixth research committee are as follows: estimation of the intensity and transmission loss of space wave electric field in a zone between 1.5 and 40 MHz, observation of the ionosphere of oblique entrance, scattering propagation of ionosphere, back scattering, fading of signal transmitted through ionosphere, transmission of space waves in the zone between 150 and 1,500 kHz, and effect of ionosphere on space communication. In addition, the following fourteen reports are cited: confirmation of prodromal phenomena of ionosphere disturbances, observation of the ionosphere of oblique entrance, remote propagation with supermode, basic information on forecast, back scattering, side scattering from the ground surface and ionosphere, Esub(s) propagation, scattering propagation, Esub(s) forecast, fading, effect of ionosphere on the transmission between the earth and space, radio noise produced in and above ionosphere, and propagation of standard broadcast wave. (Iwakiri, K.)

Lower Hybrid Current Drive Experiments in Alcator C-Mod

International Nuclear Information System (INIS)

Wilson, J. R.; Bonoli, P.; Hubbard, A.; Parker, R.; Schmidt, A.; Wallace, G.; Wright, J.; Bernabei, S.

2007-01-01

A Lower Hybrid Current Drive (LHCD) system has been installed on the Alcator C-MOD tokamak at MIT. Twelve klystrons at 4.6 GHz feed a 4x22 waveguide array. This system was designed for maximum flexibility in the launched parallel wave-number spectrum. This flexibility allows tailoring of the lower hybrid deposition under a variety of plasma conditions. Power levels up to 900 kW have been injected into the tokomak. The parallel wave number has been varied over a wide range, n parallel ∼1.6-4. Driven currents have been inferred from magnetic measurements by extrapolating to zero loop voltage and by direct comparison to Fisch-Karney theory, yielding an efficiency of n 20 IR/P∼0.3. Modeling using the CQL3D code supports these efficiencies. Sawtooth oscillations vanish, accompanied with peaking of the electron temperature (T e0 rises from 2.8 to 3.8 keV). Central q is inferred to rise above unity from the collapse of the sawtooth inversion radius, indicating off-axis cd as expected. Measurements of non-thermal x-ray and electron cyclotron emission confirm the presence of a significant fast electron population that varies with phase and plasma density. The x-ray emission is observed to be radialy broader than that predicted by simple ray tracing codes. Possible explanations for this broader emission include fast electron diffusion or broader deposition than simple ray tracing predictions (perhaps due to diffractive effects)

The E.C.C. programme in the field of radioactive wastes

International Nuclear Information System (INIS)

Orlowski, S.

1976-01-01

After a description of the aims of the E.C.C. in the field of radioactive wastes, the contents and the structure of the programme developed for this purpose as well as its time schedule and financing, are presented. The state of work progress and the first results of the actions taken, whose application is marked by an active cooperation of numerous national experts are quoted [fr

Quantitative comparison of electron temperature fluctuations to nonlinear gyrokinetic simulations in C-Mod Ohmic L-mode discharges

Energy Technology Data Exchange (ETDEWEB)

Sung, C., E-mail: csung@physics.ucla.edu [University of California, Los Angeles, Los Angeles, California 90095 (United States); White, A. E.; Greenwald, M.; Howard, N. T. [Plasma Science and Fusion Center, Massachusetts Institute of Technology, Cambridge, Massachusetts 02139 (United States); Mikkelsen, D. R.; Churchill, R. [Princeton Plasma Physics Laboratory, Princeton, New Jersey 08543 (United States); Holland, C. [University of California, San Diego, La Jolla, California 92093 (United States); Theiler, C. [Ecole Polytechnique Fédérale de Lausanne, SPC, Lausanne 1015 (Switzerland)

2016-04-15

Long wavelength turbulent electron temperature fluctuations (k{sub y}ρ{sub s} < 0.3) are measured in the outer core region (r/a > 0.8) of Ohmic L-mode plasmas at Alcator C-Mod [E. S. Marmar et al., Nucl. Fusion 49, 104014 (2009)] with a correlation electron cyclotron emission diagnostic. The relative amplitude and frequency spectrum of the fluctuations are compared quantitatively with nonlinear gyrokinetic simulations using the GYRO code [J. Candy and R. E. Waltz, J. Comput. Phys. 186, 545 (2003)] in two different confinement regimes: linear Ohmic confinement (LOC) regime and saturated Ohmic confinement (SOC) regime. When comparing experiment with nonlinear simulations, it is found that local, electrostatic ion-scale simulations (k{sub y}ρ{sub s} ≲ 1.7) performed at r/a ∼ 0.85 reproduce the experimental ion heat flux levels, electron temperature fluctuation levels, and frequency spectra within experimental error bars. In contrast, the electron heat flux is robustly under-predicted and cannot be recovered by using scans of the simulation inputs within error bars or by using global simulations. If both the ion heat flux and the measured temperature fluctuations are attributed predominantly to long-wavelength turbulence, then under-prediction of electron heat flux strongly suggests that electron scale turbulence is important for transport in C-Mod Ohmic L-mode discharges. In addition, no evidence is found from linear or nonlinear simulations for a clear transition from trapped electron mode to ion temperature gradient turbulence across the LOC/SOC transition, and also there is no evidence in these Ohmic L-mode plasmas of the “Transport Shortfall” [C. Holland et al., Phys. Plasmas 16, 052301 (2009)].

Evaluation of the Community's nuclear reactor safety research programme

International Nuclear Information System (INIS)

Brandstetter, A.; Goedkoop, J.A.; Jaumotte, A.; Malhouitre, G.; Tomkins, B.; Zorzoli, G.B.

1986-01-01

This report describes an evaluation of the 1980-85 CEC reactor safety programme prepared, at the invitation of the Commission, by a panel of six independent experts by means of examining the relevant document and by holding hearings with the responsible CEC staff. It contains the recommendations made by the panel on the following topics: the need for the JRC to continue to make its competence in the reactor safety field available to the Community; the importance of continuity in the JRC and shared-cost action programmes; the difficulty of developing reactor safety research programmes which satisfy the needs of users with diverse needs; the monitoring of the utilization of the research results; the maintenance of the JRC computer codes used by the Member States; the spin-off from research results being made available to other industrial sectors; the continued contact between the JRC researchers and the national experts; the coordination of LWR safety research with that of the Member States; and, the JRC work on fast breeders to be planned with regard to the R and D programmes of the Fast Reactor European Consortium

Mentoring health researchers globally: Diverse experiences, programmes, challenges and responses.

Science.gov (United States)

Cole, Donald C; Johnson, Nancy; Mejia, Raul; McCullough, Hazel; Turcotte-Tremblay, Anne-Marie; Barnoya, Joaquin; Falabella Luco, María Soledad

2016-10-01

Mentoring experiences and programmes are becoming increasingly recognised as important by those engaged in capacity strengthening in global health research. Using a primarily qualitative study design, we studied three experiences of mentorship and eight mentorship programmes for early career global health researchers based in high-income and low- and middle-income countries. For the latter, we drew upon programme materials, existing unpublished data and more formal mixed-method evaluations, supplemented by individual email questionnaire responses. Research team members wrote stories, and the team assembled and analysed them for key themes. Across the diverse experiences and programmes, key emergent themes included: great mentors inspire others in an inter-generational cascade, mentorship is transformative in personal and professional development and involves reciprocity, and finding the right balance in mentoring relationships and programmes includes responding creatively to failure. Among the challenges encountered were: struggling for more level playing fields for new health researchers globally, changing mindsets in institutions that do not have a culture of mentorship and building collaboration not competition. Mentoring networks spanning institutions and countries using multiple virtual and face-to-face methods are a potential avenue for fostering organisational cultures supporting quality mentorship in global health research.

Radiative and three-body recombination in the Alcator C-Mod divertor

International Nuclear Information System (INIS)

Lumma, D.; Terry, J.L.; Lipschultz, B.

1997-01-01

Significant recombination of the majority ion species has been observed in the divertor region of Alcator C-Mod [I. H. Hutchinson et al., Phys. Plasmas 1, 1511 (1994)] under detached conditions. This determination is made by analysis of the visible spectrum from the divertor, in particular the Balmer series line emission and the observed recombination continuum, including an apparent recombination edge at ∼375 nm. The analysis shows that the electron temperature in the recombining plasma is 0.8 endash 1.5 eV. The measured volume recombination rate is comparable to the rate of ion collection at the divertor plates. The dominant recombination mechanism is three-body recombination into excited states (e+e+D + Right-arrow D 0 +e), although radiative recombination (e+D + Right-arrow D 0 +hν) contributes ∼5% to the total rate. Analysis of the Balmer series line intensities (from n upper =3 through 10) shows that the upper levels of these transitions are populated primarily by recombination. Thus the brightnesses of the Balmer series (and Lyman series) are directly related to the recombination rate. copyright 1997 American Institute of Physics

Analysis of Rotation and Transport Data in C-Mod ITB Plasmas

Science.gov (United States)

Fiore, C. L.; Rice, J. E.; Reinke, M. L.; Podpaly, Y.; Bespamyatnov, I. O.; Rowan, W. L.

2009-11-01

Internal transport barriers (ITBs) spontaneously form near the half radius of Alcator C-Mod plasmas when the EDA H-mode is sustained for several energy confinement times in either off-axis ICRF heated discharges or in purely ohmic heated plasmas. These plasmas exhibit strongly peaked density and pressure profiles, static or peaking temperature profiles, peaking impurity density profiles, and thermal transport coefficients that approach neoclassical values in the core. It has long been observed that the intrinsic central plasma rotation that is strongly co-current following the H-mode transition slows and often reverses as the density peaks as the ITB forms. Recent spatial measurements demonstrate that the rotation profile develops a well in the core region that decreases continuously as central density rises while the value outside of the core remains strongly co-current. This results in the formation of a steep potential gradient/strong electric field at the location of the foot of the ITB density profile. The resulting E X B shearing rate is also quite significant at the foot. These analyses and the implications for plasma transport and stability will be presented.

On mod 2 and higher elliptic genera

International Nuclear Information System (INIS)

Liu Kefeng

1992-01-01

In the first part of this paper, we construct mod 2 elliptic genera on manifolds of dimensions 8k+1, 8k+2 by mod 2 index formulas of Dirac operators. They are given by mod 2 modular forms or mod 2 automorphic functions. We also obtain an integral formula for the mod 2 index of the Dirac operator. As a by-product we find topological obstructions to group actions. In the second part, we construct higher elliptic genera and prove some of their rigidity properties under group actions. In the third part we write down characteristic series for all Witten genera by Jacobi theta-functions. The modular property and transformation formulas of elliptic genera then follow easily. We shall also prove that Krichever's genera, which come from integrable systems, can be written as indices of twisted Dirac operators for SU-manifolds. Some general discussions about elliptic genera are given. (orig.)

Nirex safety assessment research programme: 1987/88

International Nuclear Information System (INIS)

George, D.; Hodgkinson, D.P.

1987-01-01

The Nirex Safety Assessment Research programme's objective is to provide information for the radiological safety case for disposing low-level and intermediate-level radioactive wastes in underground repositories. The programme covers a wide range of experimental studies and mathematical modelling for the near and far field. It attempts to develop a quantitative understanding of events and processes which have an impact on the safety of radioactive waste disposal. (U.K.)

Science Academies' Summer Research Fellowship Programme

Indian Academy of Sciences (India)

Home; Journals; Resonance – Journal of Science Education; Volume 22; Issue 11. Science Academies' Summer Research Fellowship Programme for Students and Teachers - 2018. Information and Announcements Volume 22 Issue 11 November 2017 pp 1100-1100 ...

Understanding of Neutral Gas Transport in the Alcator C-Mod Tokamak Divertor

International Nuclear Information System (INIS)

Stotler, D.P.; Pitcher, C.S.; Boswell, C.J.; LaBombard, B.; Terry, J.L.; Elder, J.D.; Lisgo, S.

2002-01-01

A series of experiments on the effect of divertor baffling on the Alcator C-Mod tokamak provides stringent tests on models of neutral gas transport in and around the divertor region. One attractive feature of these experiments is that a trial description of the background plasma can be constructed from experimental measurements using a simple model, allowing the neutral gas transport to be studied with a stand-alone code. The neutral-ion and neutral-neutral elastic scattering processes recently added to the DEGAS 2 Monte Carlo neutral transport code permit the neutral gas flow rates between the divertor and main chamber to be simulated more realistically than before. Nonetheless, the simulated neutral pressures are too low and the deuterium Balmer-alpha emission profiles differ qualitatively from those measured, indicating an incomplete understanding of the physical processes involved in the experiment. Some potential explanations are examined and opportunities for future exploration a re highlighted. Improvements to atomic and surface physics data and models will play a role in the latter

Experimental and gyrokinetic investigation of core impurity transport in Alcator C-mod

Science.gov (United States)

Howard, N.; Greenwald, M.; Podpaly, Y.; Reinke, M. L.; Rice, J. E.; White, A. E.; Mikkelsen, D. R.; Puetterich, T.

2010-11-01

A new multiple pulse laser blow-off system coupled with an upgraded high resolution x-ray spectrometer with spatial resolution allow for the most detailed studies of impurity transport on Alcator C-mod to date. Trace impurity injections created by the laser blow-off technique were introduced into plasmas with a wide range of parameters and time evolving profiles of He-like calcium were measured. The unique measurement of a single charge state profile and line integrated emission measurements from spectroscopic diagnostics were compared with the simulated emission from the impurity transport code STRAHL. A nonlinear least squares fitting routine was coupled with STRAHL, allowing for core impurity transport coefficients with errors to be determined. With this method, experimental data from trace calcium injections were analyzed and radially dependent, core values (< r/a ˜.6) of the diffusive and convective components of the impurity flux were obtained. The STRAHL results are compared with linear and global, nonlinear simulations from the gyrokinetic code GYRO. Results of this comparison and an investigation of the underlying physics associated with turbulent impurity transport will be presented.

The role of turbulent suppression in the triggering ITBs on C-Mod

Science.gov (United States)

Zhurovich, K.; Fiore, C. L.; Ernst, D. R.; Bonoli, P. T.; Greenwald, M. J.; Hubbard, A. E.; Hughes, J. W.; Marmar, E. S.; Mikkelsen, D. R.; Phillips, P.; Rice, J. E.

2007-11-01

Internal transport barriers can be routinely produced in C-Mod steady EDA H-mode plasmas by applying ICRF at |r/a|>= 0.5. Access to the off-axis ICRF heated ITBs may be understood within the paradigm of marginal stability. Analysis of the Te profiles shows a decrease of R/LTe in the ITB region as the RF resonance is moved off axis. Ti profiles broaden as the ICRF power deposition changes from on-axis to off-axis. TRANSP calculations of the Ti profiles support this trend. Linear GS2 calculations do not reveal any difference in ETG growth rate profiles for ITB vs. non-ITB discharges. However, they do show that the region of stability to ITG modes widens as the ICRF resonance is moved outward. Non-linear simulations show that the outward turbulent particle flux exceeds the Ware pinch by factor of 2 in the outer plasma region. Reducing the temperature gradient significantly decreases the diffusive flux and allows the Ware pinch to peak the density profile. Details of these experiments and simulations will be presented.

Active MHD Spectroscopy of Alfvén Eigenmodes on Alcator C-Mod

Science.gov (United States)

Sears, J.; Snipes, J.; Burke, W.; Parker, R.; Fasoli, A.

2004-11-01

Alfvén eigenmode resonances are excited in a variety of plasma conditions in C-Mod with two moderate-n antennas positioned above and below the outboard midplane. Power amplifiers (≈ 3 kW) sweep the driving frequency over the audio range (< 30 kHz) or over a selected ± 50 kHz range from 100 kHz to 1 MHz. Logic circuitry that calculates the center frequency of the Toroidal Alfven Eigenmode gap, f_TAE=v_A/4π qR, in real-time from BT and e measurements is being developed to enable the antennas to track f_TAE. Simultaneous in-vessel phase calibration of the pick-up coils will be used to better identify toroidal mode numbers. Shot-to-shot elongation scans do not show the dependence of damping on edge shear that was seen in results at JET. Inner wall limited plasmas with moderate outer gaps show higher damping rates than diverted plasmas with low outer gaps. Low frequency experiments below 20kHz will also be presented.

Quality assurance programme for the LVR-15 nuclear research reactor

International Nuclear Information System (INIS)

1995-03-01

The document specifies all aspects of the quality assurance programme for the LVR-15 nuclear research reactor. The programme addresses the organization and responsibilities, basic quality assurance activities, and identification of management, planning, and working documents necessary to implement the programme. (P.A.)

A new formulation of the law of octic reciprocity for primes ≡±3(mod8 and its consequences

Directory of Open Access Journals (Sweden)

Richard H. Hudson

1982-01-01

Full Text Available Let p and q be odd primes with q≡±3(mod8, p≡1(mod8=a2+b2=c2+d2 and with the signs of a and c chosen so that a≡c≡1(mod4. In this paper we show step-by-step how to easily obtain for large q necessary and sufficient criteria to have (−1(q−1/2q(p−1/8≡(a−bd/acj(modp for j=1,…,8 (the cases with j odd have been treated only recently [3] in connection with the sign ambiguity in Jacobsthal sums of order 4. This is accomplished by breaking the formula of A.E. Western into three distinct parts involving two polynomials and a Legendre symbol; the latter condition restricts the validity of the method presented in section 2 to primes q≡3(mod8 and significant modification is needed to obtain similar results for q≡±1(mod8. Only recently the author has completely resolved the case q≡5(mod8, j=1,…,8 and a sketch of the method appears in the closing section of this paper.

Preliminary validation of RELAP5/Mod4.0 code for LBE cooled NACIE facility

Energy Technology Data Exchange (ETDEWEB)

Kumari, Indu; Khanna, Ashok, E-mail: akhanna@iitk.ac.in

2017-04-01

Highlights: • Detail discussion of thermo physical properties of Lead Bismuth Eutectic incorporated in the code RELAP5/Mod4.0 included. • Benchmarking of LBE properties in RELAP5/Mod4.0 against literature. • NACIE facility for three different power levels (10.8, 21.7 and 32.5 kW) under natural circulation considered for benchmarking. • Preliminary validation of the LBE properties against experimental data. • NACIE facility for power level 22.5 kW considered for validation. - Abstract: The one-dimensional thermal hydraulic computer code RELAP5 was developed for thermal hydraulic study of light water reactor as well as for nuclear research reactors. The purpose of this work is to evaluate the code RELAP5/Mod4.0 for analysis of research reactors. This paper consists of three major sections. The first section presents detailed discussions on thermo-physical properties of Lead Bismuth Eutectic (LBE) incorporated in RELAP5/Mod4.0 code. In the second section, benchmarking of RELAP5/Mod4.0 has been done with the Natural Circulation Experimental (NACIE) facility in comparison with Barone’s simulations using RELAP5/Mod3.3. Three different power levels (10.8 kW, 21.7 kW and 32.5 kW) under natural circulation conditions are considered. Results obtained for LBE temperatures, temperature difference across heat section, pin surface temperatures, mass flow rates and heat transfer coefficients in heat section heat exchanger are in agreement with Barone’s simulation results within 7% of average relative error. Third section presents validation of RELAP5/Mod4.0 against the experimental data of NACIE facility performed by Tarantino et al. test number 21 at power of 22.5 kW comparing the profiles of temperatures, mass flow rate and velocity of LBE. Simulation and experimental results agree within 7% of average relative error.

RDandD Programme 2010. Programme for research, development and demonstration of methods for the management and disposal of nuclear waste

International Nuclear Information System (INIS)

2010-09-01

RDandD Programme 2010 presents SKB's plans for research, development and demonstration during the period 2011-2016. SKB's activities are divided into two main areas: the programme for low- and intermediate-level waste (the LILW Programme) and the Nuclear Fuel Programme. Operation of the existing facilities takes place within the Operational Process. RDandD Programme 2010 consists of five parts: Part I Overall plan of action Part II The LILW Programme Part III The Nuclear Fuel Programme Part IV Research for assessment of long-term safety Part V Social science research RDandD Programme 2007 was mainly focused on development of technology to realize the final repository for spent nuclear fuel. The efforts described were aimed at gaining a greater knowledge of long-term safety and compiling technical supporting documentation for applications under the Nuclear Activities Act for the final repository for spent nuclear fuel and under the Environmental Code for the final repository system. Many important results from these efforts are reported in this programme. The integrated account of the results will be presented in applications submitted in early 2011. The regulatory review of RDandD Programme 2007 and its supplement called for clarifications of plans and programmes for the final repository for short-lived radioactive waste, SFR, and the final repository for long-lived waste, SFL. This RDandD Programme describes these plans more clearly

RDandD Programme 2010. Programme for research, development and demonstration of methods for the management and disposal of nuclear waste

Energy Technology Data Exchange (ETDEWEB)

2010-09-15

RDandD Programme 2010 presents SKB's plans for research, development and demonstration during the period 2011-2016. SKB's activities are divided into two main areas: the programme for low- and intermediate-level waste (the LILW Programme) and the Nuclear Fuel Programme. Operation of the existing facilities takes place within the Operational Process. RDandD Programme 2010 consists of five parts: Part I Overall plan of action Part II The LILW Programme Part III The Nuclear Fuel Programme Part IV Research for assessment of long-term safety Part V Social science research RDandD Programme 2007 was mainly focused on development of technology to realize the final repository for spent nuclear fuel. The efforts described were aimed at gaining a greater knowledge of long-term safety and compiling technical supporting documentation for applications under the Nuclear Activities Act for the final repository for spent nuclear fuel and under the Environmental Code for the final repository system. Many important results from these efforts are reported in this programme. The integrated account of the results will be presented in applications submitted in early 2011. The regulatory review of RDandD Programme 2007 and its supplement called for clarifications of plans and programmes for the final repository for short-lived radioactive waste, SFR, and the final repository for long-lived waste, SFL. This RDandD Programme describes these plans more clearly

RDandD Programme 2010. Programme for research, development and demonstration of methods for the management and disposal of nuclear waste

Energy Technology Data Exchange (ETDEWEB)

2010-09-15

RDandD Programme 2010 presents SKB's plans for research, development and demonstration during the period 2011-2016. SKB's activities are divided into two main areas: the programme for low- and intermediate-level waste (the LILW Programme) and the Nuclear Fuel Programme. Operation of the existing facilities takes place within the Operational Process. RDandD Programme 2010 consists of five parts: Part I Overall plan of action Part II The LILW Programme Part III The Nuclear Fuel Programme Part IV Research for assessment of long-term safety Part V Social science research RDandD Programme 2007 was mainly focused on development of technology to realize the final repository for spent nuclear fuel. The efforts described were aimed at gaining a greater knowledge of long-term safety and compiling technical supporting documentation for applications under the Nuclear Activities Act for the final repository for spent nuclear fuel and under the Environmental Code for the final repository system. Many important results from these efforts are reported in this programme. The integrated account of the results will be presented in applications submitted in early 2011. The regulatory review of RDandD Programme 2007 and its supplement called for clarifications of plans and programmes for the final repository for short-lived radioactive waste, SFR, and the final repository for long-lived waste, SFL. This RDandD Programme describes these plans more clearly

ModA and ModB, two ADP-ribosyltransferases encoded by bacteriophage T4: catalytic properties and mutation analysis.

Science.gov (United States)

Tiemann, Bernd; Depping, Reinhard; Gineikiene, Egle; Kaliniene, Laura; Nivinskas, Rimas; Rüger, Wolfgang

2004-11-01

Bacteriophage T4 encodes three ADP-ribosyltransferases, Alt, ModA, and ModB. These enzymes participate in the regulation of the T4 replication cycle by ADP-ribosylating a defined set of host proteins. In order to obtain a better understanding of the phage-host interactions and their consequences for regulating the T4 replication cycle, we studied cloning, overexpression, and characterization of purified ModA and ModB enzymes. Site-directed mutagenesis confirmed that amino acids, as deduced from secondary structure alignments, are indeed decisive for the activity of the enzymes, implying that the transfer reaction follows the Sn1-type reaction scheme proposed for this class of enzymes. In vitro transcription assays performed with Alt- and ModA-modified RNA polymerases demonstrated that the Alt-ribosylated polymerase enhances transcription from T4 early promoters on a T4 DNA template, whereas the transcriptional activity of ModA-modified polymerase, without the participation of T4-encoded auxiliary proteins for middle mode or late transcription, is reduced. The results presented here support the conclusion that ADP-ribosylation of RNA polymerase and of other host proteins allows initial phage-directed mRNA synthesis reactions to escape from host control. In contrast, subsequent modification of the other cellular target proteins limits transcription from phage early genes and participates in redirecting transcription to phage middle and late genes.

The Focus on Youth Prevention and Education Research Programme

Directory of Open Access Journals (Sweden)

Lynette Deveaux

2016-10-01

Full Text Available Like many developing or transitional countries affected by the HIV epidemic, The Bahamas has been deeply committed to HIV and sexually transmitted infection reduction and continues to make great strides in controlling the epidemic within its boundaries. Encouraged by the impact of the Focus on Youth Caribbean (FOYC, a school-based HIV/AIDS prevention programme and its parenting component on Grade 6 and Grade 10 students and their parents, a team of researchers from The Bahamas and the United States sought to implement a similar programme at a national level, while simultaneously evaluating factors that impact the sustainability of sexual risk-reduction programmes like FOYC. This paper describes five research projects conducted in The Bahamas between 1998 and 2016 and includes a list of over 40 published research articles

Radiation research within the framework programmes of the European Commission

Energy Technology Data Exchange (ETDEWEB)

Karaoglou, A.; Kelly, G.N.; Desmet, G.; Menzel, H.G.; Schibilla, H.; Olast, M.; Gasperini, F.; Chadwick, K.H.; Sinnave, J. [European Commission Directorate General science, Brussels (Belgium). Research and Development, Radiation Protection Research Action

1997-09-01

The background to the radiation protection research and training programme of the European Commission is described in the presentation. The objectives and achievements of the third framework programme are summarised together with a description of how the achievements led to the establishment of the priorities for the fourth framework programme. Indications on the preliminary prospects for the fifth framework programme, 1998-2002 are also given. (6 refs.).

RELAP5/MOD2 code assessment

International Nuclear Information System (INIS)

Nithianandan, C.K.; Shah, N.H.; Schomaker, R.J.; Miller, F.R.

1985-01-01

Babcock and Wilcox (B and W) has been working with the code developers at EG and G and the US Nuclear Regulatory Commission in assessing the RELAP5/MOD2 computer code for the past year by simulating selected separate-effects tests. The purpose of this assessment has been to evaluate the code for use in MIST (Ref. 2) and OTIS integral system tests simulations and in the prediction of pressurized water reactor transients. B and W evaluated various versions of the code and made recommendations to improve code performance. As a result, the currently released version (cycle 36.1) has been improved considerably over earlier versions. However, further refinements to some of the constitutive models may still be needed to further improve the predictive capability of RELAP5/MOD2. The following versions of the code were evaluated. (1) RELAP/MOD2/Cycle 22 - first released version; (2) YELAP5/Cycle 32 - EG and G test version of RELAP5/MOD2/Cycle 32; (3) RELAP5/MOD2/Cycle 36 - frozen cycle for international code assessment; (4) updates to cycle 36 based on recommendations developed by B and W during the simulation of a Massachusetts Institute of Technology (MIT) pressurizer test; and (5) cycle 36.1 updates received from EG and G

RELAP5/MOD2 code assessment

Energy Technology Data Exchange (ETDEWEB)

Nithianandan, C.K.; Shah, N.H.; Schomaker, R.J.; Miller, F.R.

1985-11-01

Babcock and Wilcox (B and W) has been working with the code developers at EG and G and the US Nuclear Regulatory Commission in assessing the RELAP5/MOD2 computer code for the past year by simulating selected separate-effects tests. The purpose of this assessment has been to evaluate the code for use in MIST (Ref. 2) and OTIS integral system tests simulations and in the prediction of pressurized water reactor transients. B and W evaluated various versions of the code and made recommendations to improve code performance. As a result, the currently released version (cycle 36.1) has been improved considerably over earlier versions. However, further refinements to some of the constitutive models may still be needed to further improve the predictive capability of RELAP5/MOD2. The following versions of the code were evaluated. (1) RELAP/MOD2/Cycle 22 - first released version; (2) YELAP5/Cycle 32 - EG and G test version of RELAP5/MOD2/Cycle 32; (3) RELAP5/MOD2/Cycle 36 - frozen cycle for international code assessment; (4) updates to cycle 36 based on recommendations developed by B and W during the simulation of a Massachusetts Institute of Technology (MIT) pressurizer test; and (5) cycle 36.1 updates received from EG and G.

Recueil de modèles aléatoires

CERN Document Server

Chafai, Djalil

2016-01-01

Ce recueil puise sa source dans les cours de master de mathématiques appliquées et de préparation à l’épreuve de modélisation de l’agrégation de mathématiques. Le parti pris de cet ouvrage est de polariser la rédaction par les modèles plutôt que par les outils, et de consacrer chaque chapitre à un modèle. Le premier public visé est celui des enseignants-chercheurs en probabilités, débutants ou confirmés. De nombreux chapitres peuvent également bénéficier directement à des étudiants de master ou préparant l’agrégation. Collected Stochastic Models This collection was inspired by applied mathematics Master classes in stochastic modeling. The focus is on models rather than on tools, and each chapter is devoted to a specific model. Though the book is primarily intended for academics in the field of probability theory, beginners and experienced researchers alike, many chapters will also benefit students preparing to pursue their Master degree in mathematics. .

Evaluating a Research Training Programme for People with Intellectual Disabilities Participating in Inclusive Research: The Views of Participants.

Science.gov (United States)

Fullana, Judit; Pallisera, Maria; Català, Elena; Puyalto, Carolina

2017-07-01

This article presents the results of evaluating a research training programme aimed at developing the skills of people with intellectual disabilities to actively participate in inclusive research. The present authors opted for a responsive approach to evaluation, using a combination of interviews, questionnaires and focus groups to gather information on the views of students, trainers and members of the research team regarding how the programme progressed, the learning achieved and participants' satisfaction with the programme. The evaluation showed that most of the participants were satisfied with the programme and provided guidelines for planning contents and materials, demonstrating the usefulness of these types of programme in constructing the research group and empowering people with intellectual disabilities to participate in research. The evaluation revealed that the programme had been a positive social experience that fostered interest in lifelong learning for people with intellectual disabilities. © 2016 John Wiley & Sons Ltd.

Modélisation, simulation et contrôle des installations cryogéniques du CERN

CERN Document Server

Bradu, Benjamin; Gayet, P

2010-01-01

Cette thèse présente le développement d'un simulateur de processus cryogéniques de grande taille appliqué aux installations cryogéniques de l'accélérateur de particules LHC (Large Hadron Collider) au CERN (Organisation Européenne pour la Recherche Nucléaire). Ce simulateur est basé sur une approche de modélisation orientée objet où chaque équipement (échangeur, turbine, compresseur, etc.) est représenté à partir d'un ensemble d'équations physiques algébro-différentielles. L'architecture de contrôle du CERN est également simulée en intégrant le contrôle réalisé par des automates programmables (PLC) avec le système de supervision. Ce simulateur à été développé pour servir différents desseins comme l'entraînement des opérateurs, la vérification des programmes automates (virtual commissioning) et l'optimisation des stratégies de contrôle. Le système cryogénique d'un détecteur de particules (CMS) a d'abord été simulé pour valider les modèles, puis un liquéfacteur d'...

Research reactor programmes at the IAEA

International Nuclear Information System (INIS)

Reijonen, H.

1978-01-01

The activities performed according to the Agency programs for research reactors in the fields of information collection and dissemination, meetings organization, publications of the proceedings and execution of technical assistance are discussed in the paper emphasizing the services that are provided for developing countries. It is intended that the programme on research reactors should be flexible and respond to the actual needs of the countries receiving assistance

Orbit Representations from Linear mod 1 Transformations

Directory of Open Access Journals (Sweden)

Carlos Correia Ramos

2012-05-01

Full Text Available We show that every point $x_0in [0,1]$ carries a representationof a $C^*$-algebra that encodes the orbit structure of thelinear mod 1 interval map $f_{eta,alpha}(x=eta x +alpha$. Such $C^*$-algebra is generated by partial isometries arising from the subintervals of monotonicity of the underlying map $f_{eta,alpha}$. Then we prove that such representation is irreducible. Moreover two such of representations are unitarily equivalent if and only if the points belong to the same generalized orbit, for every $alphain [0,1[$ and $etageq 1$.

Steady-state simulations of a 30-tube once-through steam generator with the RELAP5/MOD3 and RELAP5/MOD2 computer codes

International Nuclear Information System (INIS)

Hassan, Y.A.; Salim, P.

1991-01-01

This paper reports on a steady-state analysis of a 30-tube once-through steam generator that has been performed on the RELAPS/MOD3 and RELAPS/MOD2 computer codes for 100, 75, and 65% loads. Results obtained are compared with experimental data. The RELAP5/MOD3 results for the test facility generally agree reasonably well with the data for the primary-side temperature profiles. The secondary-side temperature profile predicted by RELAP5/MOD3 at 75 and 65% loads agrees fairly well with the data and is better than the RELAP5/MOD2 results. However, the RELAP5/MOD3 calculated secondary-side temperature profile does not compare well with the 100% load data

Vectorization, parallelization and implementation of nuclear codes [MVP/GMVP, QMDRELP, EQMD, HSABC, CURBAL, STREAM V3.1, TOSCA, EDDYCAL, RELAP5/MOD2/C36-05, RELAP5/MOD3] on the VPP500 computer system. Progress report 1995 fiscal year

International Nuclear Information System (INIS)

Nemoto, Toshiyuki; Watanabe, Hideo; Fujita, Toyozo; Kawai, Wataru; Harada, Hiroo; Gorai, Kazuo; Yamasaki, Kazuhiko; Shoji, Makoto; Fujii, Minoru.

1996-07-01

At Center for Promotion of Computational Science and Engineering, time consuming eight nuclear codes suggested by users have been vectorized, parallelized on the VPP500 computer system. In addition, two nuclear codes used on the VP2600 computer system were implemented on the VPP500 computer system. Neutron and photon transport calculation code MVP/GMVP and relativistic quantum molecular dynamics code QMDRELP have been parallelized. Extended quantum molecular dynamics code EQMD and adiabatic base calculation code HSABC have been parallelized and vectorized. Ballooning turbulence simulation code CURBAL, 3-D non-stationary compressible fluid dynamics code STREAM V3.1, operating plasma analysis code TOSCA and eddy current analysis code EDDYCAL have been vectorized. Reactor safety analysis code RELAP5/MOD2/C36-05 and RELAP5/MOD3 were implemented on the VPP500 computer system. (author)

Vectorization, parallelization and implementation of nuclear codes =MVP/GMVP, QMDRELP, EQMD, HSABC, CURBAL, STREAM V3.1, TOSCA, EDDYCAL, RELAP5/MOD2/C36-05, RELAP5/MOD3= on the VPP500 computer system. Progress report 1995 fiscal year

Energy Technology Data Exchange (ETDEWEB)

Nemoto, Toshiyuki; Watanabe, Hideo; Fujita, Toyozo [Fujitsu Ltd., Tokyo (Japan); Kawai, Wataru; Harada, Hiroo; Gorai, Kazuo; Yamasaki, Kazuhiko; Shoji, Makoto; Fujii, Minoru

1996-06-01

At Center for Promotion of Computational Science and Engineering, time consuming eight nuclear codes suggested by users have been vectorized, parallelized on the VPP500 computer system. In addition, two nuclear codes used on the VP2600 computer system were implemented on the VPP500 computer system. Neutron and photon transport calculation code MVP/GMVP and relativistic quantum molecular dynamics code QMDRELP have been parallelized. Extended quantum molecular dynamics code EQMD and adiabatic base calculation code HSABC have been parallelized and vectorized. Ballooning turbulence simulation code CURBAL, 3-D non-stationary compressible fluid dynamics code STREAM V3.1, operating plasma analysis code TOSCA and eddy current analysis code EDDYCAL have been vectorized. Reactor safety analysis code RELAP5/MOD2/C36-05 and RELAP5/MOD3 were implemented on the VPP500 computer system. (author)

Description of the Wetlands Research Programme

CSIR Research Space (South Africa)

Walmsley, RD

1988-01-01

Full Text Available This report presents a rationale to the development of a multidisciplinary South African Wetland Research Programme. A definition of what is meant by the term wetland is given along with a general description of what types of wetland occur in South...

Observations of core toroidal rotation reversals in Alcator C-Mod ohmic L-mode plasmas

International Nuclear Information System (INIS)

Rice, J.E.; Reinke, M.L.; Podpaly, Y.A.; Churchill, R.M.; Cziegler, I.; Dominguez, A.; Ennever, P.C.; Fiore, C.L.; Granetz, R.S.; Greenwald, M.J.; Hubbard, A.E.; Hughes, J.W.; Irby, J.H.; Ma, Y.; Marmar, E.S.; McDermott, R.M.; Porkolab, M.; Duval, B.P.; Bortolon, A.; Diamond, P.H.

2011-01-01

Direction reversals of intrinsic toroidal rotation have been observed in Alcator C-Mod ohmic L-mode plasmas following modest electron density or toroidal magnetic field ramps. The reversal process occurs in the plasma interior, inside of the q = 3/2 surface. For low density plasmas, the rotation is in the co-current direction, and can reverse to the counter-current direction following an increase in the electron density above a certain threshold. Reversals from the co- to counter-current direction are correlated with a sharp decrease in density fluctuations with k R ≥ 2 cm -1 and with frequencies above 70 kHz. The density at which the rotation reverses increases linearly with plasma current, and decreases with increasing magnetic field. There is a strong correlation between the reversal density and the density at which the global ohmic L-mode energy confinement changes from the linear to the saturated regime.

Recycling of actinides and fission products, the Dutch RAS research programme

Energy Technology Data Exchange (ETDEWEB)

Abrahams, K; Cordfunke, E H.P.; Franken, W M.P.; Gruppelaar, H; Kloosterman, J L; Konings, R J.M.; Versteegh, A M

1994-08-01

An ECN, a research programme has been started to contribute to current international research efforts in the field of P and T. The name of this programme is RAS, which is the dutch acronym for recycling of actinides and fission products. This multidisciplinary programme consists of the following components: - Nuclear data (`cross-section libraries`) - Reactor physics and scenario studies - Chemical studies (`actinide chemistry`) - Technological studies and irradiations. (orig./HP).

Upgrade of the RFX-mod real time control system

International Nuclear Information System (INIS)

Manduchi, G.; Barbalace, A.; Luchetta, A.; Soppelsa, A.; Taliercio, C.; Zampiva, E.

2012-01-01

Highlights: ► The paper describes the experience in running the real-time control system of RFX-mod. ► It proposes a new architecture based multicore technology. ► It analyzes two different solutions for data acquisition. ► It discusses the effect of non simultaneous sampling in acquisition. ► It provides some preliminary performance measurements. - Abstract: The real-time control system of RFX-mod, in operation since 2005, has been successful and has allowed several important achievements in the RFX physics research program. As a consequence of this fact, new control algorithms are under investigation, which are more demanding in terms of both enhanced computing power and reduced system latency, currently around 1.5 ms. For this reason, a major upgrade of the system is being considered, and a new architecture has been proposed, taking advantage of the rapid evolution of computer technology in the last years. The central component of the new architecture is a Linux-based multicore server, where individual cores replace the VME computers. The server is connected to the I/O via PCI-e based bus extenders, and every PCI-e connection is managed by a separate core. The system is supervised by MARTe, a software framework for real-time applications written in C++ and developed at JET and currently used for the JET vertical stabilization and in other fusion devices.

Research on the Superheater Material Properties for USC Boiler with 700°C Steam Parameter

Science.gov (United States)

Chongbin, Wang; Xueyuan, Xu; Yufeng, Zhu; Yongqiang, Jin; Hui, Tong; Yu, Wang; Xiaoli, Lu

This paper discusses the materials' properties of superheater for 700°C USC boiler, including Sanicro25, HR6W, 617mod and 740H, and analyzes the range of applicable temperature of superheater made of different tubes, such as T91, T92, Super304H, TP310HCbN, Sanicro25, HR6W, 617Mod and 740H. In addition, some suggestions on the material selection have been proposed.

The benefit of guest loyalty programmes | La Rose | Research in ...

African Journals Online (AJOL)

In the literature review of this research, the following aspects are discussed: a loyalty programme and its use; the sort of loyalty programmes; the effects of a loyalty programme; and the wishes and needs of a leisure guest. Surveys were divided among 46 leisure guests of Apollo Hotels and Resorts in order to collect data on ...

Rare earth materials research in European Community R and D programmes

International Nuclear Information System (INIS)

Gavigan, J.P.

1992-01-01

The level of involvement of EC research programmes in rare earth materials research is quite high. A total of 65 projects have been identified representing an involvement of 283 partners from all over Europe. This corresponds to a budget a 63.3 MECU (76MDollars) of which the EC contributes 40.7 MECU (49MDollars). In this paper, the various research activities will be discussed under the main themes of rare earth permanent magnets, high Tc superconductors, optical and other materials, with specific reference to the three main programmes involved, BRITE/EURAM, SCIENCE and ESPRIT. Two other programmes currently involved in rare earth research are RAW MATERIALS and JOULE. (orig.)

UKAEA underlying research programme annual report

International Nuclear Information System (INIS)

Mason, J.P.

1988-11-01

Work from all technical areas of the Authority's underlying research programme is described. This is typically in the form of an interim progress report for the year April 1987 to March 1988. The seventeen chapters report research into radiation damage, fracture studies, chemical effects at surfaces, surface physics and corrosion, fluid mechanics and heat transfer, nuclear studies, neutron beam studies, theoretical sciences, instrumentation, reactor physics and control, fabrication processes, laser isotope separation, nuclear fuel cycle studies, quantum electronics, radiological protection, and miscellaneous underlying research. (author)

Post-test analysis of LOBI BT-01 using RELAP5/MOD2 and RELAP5/MOD3

International Nuclear Information System (INIS)

Holmes, B.J.

1991-08-01

LOBI is a high pressure, electrically heated integral system test facility simulating a KWU 1300 MW PWR scaled 1:712 by volume, although full scale has been maintained in the vertical direction. This report describes the results of an analysis of test BT-01, which simulates a 10% steam line break. The bulk of the analysis was performed using the Project Version of RELAP5/MOD2, with additional calculations using RELAP5/MOD3 for comparison. The codes provided generally good agreement with data. In particular, the break flows were well modelled, although the mass flow data proved to be unreliable, and this conclusion had to be derived from interpreting other signals. RELAP over-predicted primary/secondary heat transfer in the broken loop, however, leading to a more rapid cool-down of the primary circuit. Furthermore, the primary side pressure response was critically dependent upon the pressuriser behaviour, and the correct timing of the uncovery of the surge line. Inter-phase drag was not well predicted in the broken loop steam generator intermals, although some improvement was seen in the RELAP5/MOD3 predictions. MOD3 gave a reduction in primary/secondary heat transfer during the test pre-conditioning phase, resulting in a lower secondary side pressure at the start of the transient compared with MOD2. (author)

Programme of basic nuclear research and associated fields 1977-1981

International Nuclear Information System (INIS)

1978-01-01

Nuclear research and development have been intensively pursued in West Germany by the Government and the Laender since 1955. In this period, the aims and official measures for fostering the research and use of nuclear power for peaceful purposes were laid down in four nuclear programmes. The 4th Nuclear Programme covers the period 1973 to 1976. From 1977, nuclear development became part of the energy research programme which was published by the West German Government in the spring of 1977. The basic nuclear research, however, was regarded as part of a total concept for fostering basic research (to be developed). While all the activities of research in the natural sciences and arts fostered by the West German Ministry of Research and Technology were to be co-ordinated in a more schematic form in the plan for 'Basic Research', it is the aim of the present statement to take stock of the present situation in 'Basic Nuclear Research' including the associated fields of 'Nuclear Solid Research' and 'Synchrotron Radiation', to analyse their structure, to describe the scientific aims for the next five years and to determine the total financial requirements. The basis for determining the financial programme worked out by the expert committee on 'Physical Research in the Nuclear Field' and the other committees in this field. The plans are in agreement with the medium term plan of the West German Ministry of Research and Technology (at 27.10.1977) and their contents correspond to the state of affairs at the end of 1977. (orig./UA) [de

High-confinement-mode edge stability of Alcator C-mod plasmas

International Nuclear Information System (INIS)

Mossessian, D.A.; Snyder, P.; Hubbard, A.; Hughes, J.W.; Greenwald, M.; La Bombard, B.; Snipes, J.A.; Wolfe, S.; Wilson, H.

2003-01-01

For steady state high-confinement-mode (H-mode) operation, a relaxation mechanism is required to limit build-up of the edge gradient and impurity content. Alcator C-Mod [Hutchinson et al., Phys. Plasmas 1, 1511 (1994)] sees two such mechanisms--EDA (enhanced D-alpha H mode) and grassy ELMs (edge localized modes), but not large type I ELMs. In EDA the edge relaxation is provided by an edge localized quasicoherent (QC) electromagnetic mode that exists at moderate pedestal temperature T 95 >3.5, and does not limit the buildup of the edge pressure gradient. The q boundary of the operational space of the mode depends on plasma shape, with the q 95 limit moving down with increasing plasma triangularity. At high edge pressure gradients and temperatures the mode is replaced by broadband fluctuations ( f<50 kHz) and small irregular ELMs are observed. Ideal MHD (magnetohydrodynamic) stability analysis that includes both pressure and current driven edge modes shows that the discharges where the QC mode is observed are stable. The ELMs are identified as medium n (10< n<50) coupled peeling/ballooning modes. The predicted stability boundary of the modes as a function of pedestal current and pressure gradient is reproduced in experimental observations. The measured dependence of the ELMs' threshold and amplitude on plasma triangularity is consistent with the results of ideal MHD analysis performed with the linear stability code ELITE [Wilson et al., Phys. Plasmas 9, 1277 (2002)

Analysis of the OECD-LOFT International Standard Problem 31 using SCDAP/RELAP5/MOD3

International Nuclear Information System (INIS)

Hohorst, J.K.; Allison, C.M.

1992-01-01

The CORA-13 bundle heating and melting experiment performed at the Kernforechungszentrum, Karlaruhe, (KfK) was analyzed at the Idaho National Engineering Laboratory (INEL) using SCDAP/RELAP5/MOD3. This analysis was part of a systematic assessment of SCDAP/RELAP5/MOD3 for the US Nuclear Regulatory Commission to (a) evaluate the variances between calculated and observed behavior, (b) identify outstanding modeling deficiencies, and (c) to evaluate the impact of ongoing modeling improvements. A brief discussion of the CORA-13 experiment including a description of the facility, important test conditions, and comparisons with other CORA experimental conditions and results is provided in this report. This report describes the results of the SCDAP/RELAPS/MOD3 analysis including a description of the SCDAP/RELAPS model of the facility, base case results, sensitivity results, and a comparison with other SCDAP/RELAP5/MOD3 code-to-data comparisons

Gas jet disruption mitigation studies on Alcator C-Mod and DIII-D

International Nuclear Information System (INIS)

Granetz, R.S.; Hollmann, E.M.; Whyte, D.G.; Izzo, V.A.; Antar, G.Y.; Bader, A.; Bakhtiari, M.; Biewer, T.; Boedo, J.A.; Evans, T.E.; Hutchinson, I.H.; Jernigan, T.C.; Gray, D.S.; Groth, M.; Humphreys, D.A.; Lasnier, C.J.; Moyer, R.A.; Parks, P.B.; Reinke, M.L.; Rudakov, D.L.; Strait, E.J.; Terry, J.L.; Wesley, J.; West, W.P.; Wurden, G.; Yu, J.

2007-01-01

High-pressure noble gas jet injection is a mitigation technique which potentially satisfies the requirements of fast response time and reliability, without degrading subsequent discharges. Previously reported gas jet experiments on DIII-D showed good success at reducing deleterious disruption effects. In this paper, results of recent gas jet disruption mitigation experiments on Alcator C-Mod and DIII-D are reported. Jointly, these experiments have greatly improved the understanding of gas jet dynamics and the processes involved in mitigating disruption effects. In both machines, the sequence of events following gas injection is observed to be quite similar: the jet neutrals stop near the plasma edge, the edge temperature collapses and large MHD modes are quickly destabilized, mixing the hot plasma core with the edge impurity ions and radiating away the plasma thermal energy. High radiated power fractions are achieved, thus reducing the conducted heat loads to the chamber walls and divertor. A significant (2 x or more) reduction in halo current is also observed. Runaway electron generation is small or absent. These similar results in two quite different tokamaks are encouraging for the applicability of this disruption mitigation technique to ITER

Measurement of particle transport coefficients on Alcator C-Mod

Energy Technology Data Exchange (ETDEWEB)

Luke, T.C.T.

1994-10-01

The goal of this thesis was to study the behavior of the plasma transport during the divertor detachment in order to explain the central electron density rise. The measurement of particle transport coefficients requires sophisticated diagnostic tools. A two color interferometer system was developed and installed on Alcator C-Mod to measure the electron density with high spatial ({approx} 2 cm) and high temporal ({le} 1.0 ms) resolution. The system consists of 10 CO{sub 2} (10.6 {mu}m) and 4 HeNe (.6328 {mu}m) chords that are used to measure the line integrated density to within 0.08 CO{sub 2} degrees or 2.3 {times} 10{sup 16}m{sup {minus}2} theoretically. Using the two color interferometer, a series of gas puffing experiments were conducted. The density was varied above and below the threshold density for detachment at a constant magnetic field and plasma current. Using a gas modulation technique, the particle diffusion, D, and the convective velocity, V, were determined. Profiles were inverted using a SVD inversion and the transport coefficients were extracted with a time regression analysis and a transport simulation analysis. Results from each analysis were in good agreement. Measured profiles of the coefficients increased with the radius and the values were consistent with measurements from other experiments. The values exceeded neoclassical predictions by a factor of 10. The profiles also exhibited an inverse dependence with plasma density. The scaling of both attached and detached plasmas agreed well with this inverse scaling. This result and the lack of change in the energy and impurity transport indicate that there was no change in the underlying transport processes after detachment.

Measurement of particle transport coefficients on Alcator C-Mod

International Nuclear Information System (INIS)

Luke, T.C.T.

1994-10-01

The goal of this thesis was to study the behavior of the plasma transport during the divertor detachment in order to explain the central electron density rise. The measurement of particle transport coefficients requires sophisticated diagnostic tools. A two color interferometer system was developed and installed on Alcator C-Mod to measure the electron density with high spatial (∼ 2 cm) and high temporal (≤ 1.0 ms) resolution. The system consists of 10 CO 2 (10.6 μm) and 4 HeNe (.6328 μm) chords that are used to measure the line integrated density to within 0.08 CO 2 degrees or 2.3 x 10 16 m -2 theoretically. Using the two color interferometer, a series of gas puffing experiments were conducted. The density was varied above and below the threshold density for detachment at a constant magnetic field and plasma current. Using a gas modulation technique, the particle diffusion, D, and the convective velocity, V, were determined. Profiles were inverted using a SVD inversion and the transport coefficients were extracted with a time regression analysis and a transport simulation analysis. Results from each analysis were in good agreement. Measured profiles of the coefficients increased with the radius and the values were consistent with measurements from other experiments. The values exceeded neoclassical predictions by a factor of 10. The profiles also exhibited an inverse dependence with plasma density. The scaling of both attached and detached plasmas agreed well with this inverse scaling. This result and the lack of change in the energy and impurity transport indicate that there was no change in the underlying transport processes after detachment

Irradiation hardening of Mod.9Cr-1Mo steel

International Nuclear Information System (INIS)

Ryu, Woo-Seog; Kim, Sung-Ho; Choo, Kee-Nam; Kim, Do-Sik

2009-01-01

An irradiation test of Mod.9Cr-1Mo steel was carried out in the OR5 test hole of HANARO of a 30 MW thermal power at 390±10degC up to a fast neutron fluence of 4.4x10 19 (n/cm 2 ) (E > 1.0 MeV). The dpa of the irradiated specimens was evaluated to be 0.034 - 0.07. Tensile and impact tests of the irradiated Mod.9Cr-1Mo were done in the hot cell of the IMEF. The change of the tensile strength by irradiation was similar to the change of the yield strength. The increase of the yield and tensile strengths was up to 18% and 10% respectively. The elongation reduction of the weldment was up to 65%. (author)

Inventory of Dutch National Research on Global Climate Change: Inside and outside the National Research Programme

International Nuclear Information System (INIS)

Smythe, K.D.; Bernabo, C.; Kingma, J.; Vrakking, W.

1993-04-01

This summary of Dutch research on global climate change was compiled from a survey of the major research organisations in the Netherlands. The scope and structure of the survey and this report were based on a request for information from the World Meteorological Organisation for an intergovernmental meeting on the World Climate Programme (WCP) held (from 14 to 16 April 1993). The WMO request emphasized activities related to the WCP and its associated programmes. To extend the usefulness of the exercise, an attempt has been made to broaden the focus to give additional attention to the Intergovernmental Geosphere-Biosphere Programme (IGBP) and the Human Dimensions Programme (HDP). This was the first attempt to inventory the research projects on global climate change underway in the Netherlands - both inside and outside the National Research Programme. Other surveys on Dutch climate-related research have been conducted. The most extensive effort was a cataloging of publications from climate research in the Netherlands from 1981 to 1991, which was conducted by the Netherlands Royal Academy of Sciences (KNAW). That inventory is being updated to include publications through 1992. The database resulting from this exercise will be a useful tool for organisations sponsoring and conducting global climate change research in their efforts to stimulate cooperation and promote coordination among research groups in the Netherlands and abroad. There are plans to update the inventory in the future and to provide the information to participating Dutch organisations as well as research organisations in other countries. An overview of the current research is provided in Volume 1 with a list of projects

Rf modeling and design of a folded waveguide launcher for the Alcator C-Mod tokamak

International Nuclear Information System (INIS)

Bigelow, T.S.; Fogelman, C.F.; Baity, F.W.; Carter, M.D.; Hoffman, D.J.; Ryan, P.M.; Yugo, J.J.; Golovato, S.N.; Bonoli, P.

1993-01-01

The folded waveguide (FWG) launcher is being investigated as an improved antenna configuration for plasma heating in the ion cyclotron range of frequencies (ICRF). A development FWG launcher was successfully tested at Oak Ridge National Laboratory (ORNL) with a low-density plasma load and found to have significantly greater power density capability than current strap-type antennas operating in similar plasmas. To further test the concept on a high density tokamak plasma, a collaboration has been set up between ORNL and Massachusetts Institute of Technology (MIT) to develop and test an 80-MHz, 2-MW FWG on the Alcator C-Mod tokamak at MIT. The radio frequency (rf) electromagnetic modeling techniques and laboratory measurements used in the design of this antenna are described in this paper. A companion paper describes the mechanical design of the FWG

Full-wave and Fokker Planck analysis of ICRF heating experiments in the Alcator C-Mod tokamak

International Nuclear Information System (INIS)

Bonoli, P.T.; Golovato, S.; Porkolab, M.; Takase, Y.

1996-01-01

The Alcator C-Mod device is a high field, high density, shaped tokamak with parameters a = 0.22 m, R 0 = 0.67 m, B 0 ≤ 9.0 T, κ ≤ 1.8, δ ≤ 0.8, and 1.0 x 10 20 m -3 n e (0) ≤ 1.0 x 10 21 m -3 . Four megawatt of ICRF power is available at 80 MHz. The wide operating range in magnetic field makes several heating schemes possible: (i) Second harmonic heating of hydrogen (f 0 = 2f CH ) at 2.6 T in (D-H); (ii) Fundamental heating of (H) (f 0 = f CH ) at 5.3T in a D-(H) plasma; and (iii) Fundamental heating of ( 3 He) (f 0 = f C 3 He ) at 7.9 T in a D-( 3 He) plasma. The most successful heating regime to date has been (H)-minority heating at 5.3 T. Pellet enhanced performance (PEP) modes have also been achieved in C-Mod in D-(H) at 5.3 T and in D-( 3 He) at 7.9 T, with a combination of intense ICRF heating and Li-pellet injection. A variety of numerical models are used to analyze these heating schemes. A 1-D full-wave code (FELICE) is used to study open-quotes single passclose quotes damping of the ICRF wavefront and damping of mode-converted ion Bernstein waves. A toroidal full-wave code (FISIC) is used to study interference and focussing effects of the ICRF waves as well as damping of the ICRF power upon multiple passes of the ICRF wavefront. A combined bounce averaged Fokker Planck and toroidal full-wave code (FPPRF) is used to study the ion tail formation, orbit losses, and the power partition of the ICRF tail to the background electrons and ions. Full-wave and Fokker Planck analyses confirm the strong single pass absorption of the ICRF power in D-(H) at 5.3 T. Analysis of PEP-mode plasmas in D-( 3 He) indicates improved wave focussing and 3 He-cyclotron absorption of the ICRF waves relative to L-mode. A dramatic increase in the transfer of 3 He tail power to the background deuterium is also found for PEP-mode plasmas

The Nordic Research programme on nuclear safety

International Nuclear Information System (INIS)

1992-06-01

Only two of the five Nordic countries (Denmark, Iceland, Finland, Norway and Sweden) - Sweden and Finland - operate nuclear power plants, but there are a number of nuclear installations close to their borders. Regular 4-year programmes were initiated in 1977, designated NKS-programmes. (NKS: Nordisk KerneSikkerhedsforskning - Nordic nuclear-safety research). The current fourth NKS-programme is, influenced by the Chernobyl accident, dominated by the necessity for acquiring knowledge on unexpected events and release of radioactive material from nuclear installations. The present programme is divided into the areas of emergency preparedness, waste and decommissioning, radioecology and reactor safety. It comprises a total of 18 projects, the results of which will later be published in the form of handbooks for use in cases of emergency etc. The future of joint Nordic project work in the nuclear safety field must be seen in the light of changing conditions in and around the Nordic countries, such as the opening of relations to neighbours in the east, the move towards the European Communities and the need for training a new generation of specialists in the nuclear field etc. Each project is described in considerable detail and a list of reports resulting from the third NKS-programme 1985-1989 is given. (AB)

CORCON-MOD1 modelling improvements

International Nuclear Information System (INIS)

Corradini, M.L.; Gonzales, F.G.; Vandervort, C.L.

1986-01-01

Given the unlikely occurrence of a severe accident in a light water reactor (LWR), the core may melt and slump into the reactor cavity below the reactor vessel. The interaction of the molten core with exposed concrete (a molten-core-concrete-interaction, MCCI) causes copious gas production which influences further heat transfer and concrete attack and may threaten containment integrity. In this paper the authors focus on the low-temperature phase of the MCCI where the molten pool is partially solidified, but is still capable of attacking concrete. The authors have developed some improved phenomenological models for pool freezing and molten core-coolant heat transfer and have incorporated them into the CORCON-MOD1 computer program. In the paper the authors compare the UW-CORCON/MOD1 calculations to CORCON/MOD2 and WECHSL results as well as the BETA experiments which are being conducted in Germany

Swiss Biomass Programme - Overview report on the 2007 research programme; Programm Biomasse: Ueberblicksbericht zum Forschungsprogramm 2007

Energy Technology Data Exchange (ETDEWEB)

Binggeli, D; Guggisberg, B

2008-07-01

This illustrated report for the Swiss Federal Office of Energy (SFOE) presents an overview of the results obtained in 2007 within the framework of the Swiss Biomass research programme. The potential for biomass use in Switzerland is reviewed and the emphases of the national programme are discussed. The results obtained are noted for the following areas: process optimisation, including - amongst others - particle emissions and control aspects as well as combined wood-pellets and solar heating systems. Projects involving non-wood biomass are reported on, including biomass digesters and various biogas systems. Further reports deal with the analysis and optimisation of material flows, organic pollutants and methane losses. New conversion technologies are reported on. Further reports deal with basic strategies and concepts in the area of biomass usage. National and international co-operation is also discussed. A selection of innovative pilot and demonstration projects is also presented and research and development projects are listed.

Experimental and computational evaluation of neutrals in the Alcator C-Mod edge pedestal

Science.gov (United States)

Hughes, J. W.; Mossessian, D.; Labombard, B.; Terry, J.

2004-11-01

Pedestal-forming edge transport barriers (ETBs) in tokamak plasmas and the physics governing them are linked to the enhancement of confinement obtained in H-mode plasmas. Studies on Alcator C-Mod employ experimental measurements and simple 1-D transport models in order to better understand ETB physics. We examine the influences of ionization and charge exchange on the pedestals in electron density and temperature. Routine measurements from edge Thomson scattering (ETS) give pedestal scalings with global plasma parameters, while individual ETS profiles are combined with scanning Langmuir probe data and optical D_α emissivity measurements to give atomic density profiles and the associated radial distribution of the ionization source rate. From H-mode profiles of these quantities a well in effective plasma diffusivity is calculated, and is shown to systematically vary as the confinement regime is varied from ELM-free to EDA. Experimental work is supplemented with modeling and computation of edge neutral transport via KN1D, a kinetic solver for atomic and molecular distribution functions in slab geometry. The level of agreement between experiment and model is encouraging.

Romanian - Swiss cooperative research programme "Environmental Science and Technology in Romania" (ESTROM)

OpenAIRE

PANIN, Nicolae; GIGER, Walter

2008-01-01

The Romanian Ministry for Education, Research and Youth (MECT), the Swiss Agency for Development and Cooperation (SDC) and the Swiss National Science Foundation had launched in 2004 the Romanian-Swiss research programme known as “Environmental Science and Technology in Romania” (ESTROM). ESTROM was established as a pilot programme of scientific co-operation between Swiss Research and Education Units with similar ones from Romania in the framework of SCOPES – a Swiss national programme for sup...

Postgraduate and research programmes in Medicine and Public ...

African Journals Online (AJOL)

... 3 Master programmes in the pipeline (Global Health, Health Financing, and Supply Chain Management); partnerships with research institutions of great renown, which contributed to the reinforcement of the institutional research capacity and visibility towards excellence in leadership, accountability, and self sustainability.

The measurement of the intrinsic impurities of molybdenum and carbon in the Alcator C-Mod tokamak plasma using low resolution spectroscopy

International Nuclear Information System (INIS)

May, M.J.; Finkenthal, M.; Regan, S.P.

1997-01-01

The intrinsic impurity content of molybdenum and carbon was measured in the Alcator C-Mod tokamak using low resolution, multilayer mirror (MLM) spectroscopy (Δλ ∼ 1-10 A). Molybdenum was the dominant high-Z impurity and originated from the molybdenum armour tiles covering all the plasma facing surfaces (including the inner column, the poloidal divertor plates and the ion cyclotron resonant frequency (ICRF) limiter) at Alcator C-Mod. Soft X ray extreme ultraviolet (XUV) emission, lines of charge states, ranging from hydrogen-like to helium-like lines of carbon (radius/minor radius, r/a ∼ 1) at the plasma edge to potassium- to chlorine-like (0.4 eff value, and the power losses through line radiation were estimated. For the diverted ohmically heated plasma examined, the intrinsic molybdenum and carbon concentrations in the core plasma were found to be ∼ 1.2 x 10 10 and ∼ 1.7 x 10 12 cm -3 , respectively. These measurements were obtained before the plasma facing components were boronized. The calculated radiated power from molybdenum was 170 kW; for carbon it was 45 kW. The contribution to the measured Z eff - 1 value of ∼ 0.8 was ∼ 0.11 for molybdenum and ∼ 0.5 for carbon. (author). 36 refs, 11 figs, 3 tabs

RD and D-Programme 2004. Programme for research, development and demonstration of methods for the management and disposal of nuclear waste, including social science research

Energy Technology Data Exchange (ETDEWEB)

NONE

2004-09-01

SKB (the Swedish Nuclear Fuel and Waste Management Co), which is owned by the companies that operate the Swedish nuclear power plants, has been assigned the task of managing and disposing of the spent nuclear fuel from the reactors. The Nuclear Activities Act requires a programme of comprehensive research and development and other measures that are needed to manage and dispose of nuclear waste in a safe manner and to decommission and dismantle the nuclear power plants. SKB is now presenting RD and D-Programme 2004 in fulfilment of this requirement. The programme describes SKB's plans for the period 2005-2010. The period of immediate concern is 2005-2007. The level of detail for the three subsequent years is naturally lower.The programme provides a basis for designing systems for safe management and disposal of the radioactive waste from the nuclear power plants. SKB's plan is to implement deep disposal of the spent fuel in accordance with the KBS-3 method. In the RD and D-Programme we describe our activities and planning for this line of action and the work that is being conducted on alternative methods. Review of the programme can contribute valuable outside viewpoints. The regulatory authorities and the Government can clarify how they look upon different parts of the programme and stipulate guidelines for the future. Municipalities and other stakeholders can, after studying the programme, offer their viewpoints to SKB, the regulatory authorities or the Government.The goal for the period up to the end of 2008 is to be able to submit permit applications for the encapsulation plant and the deep repository. This RD and D-Programme therefore differs from the preceding ones in that it concentrates on questions relating to technology development for these facilities. The programmes for safety assessment and research on the long-term processes that take place in the deep repository are then linked together with the programmes for technology development. Another new

RD and D-Programme 2004. Programme for research, development and demonstration of methods for the management and disposal of nuclear waste, including social science research

International Nuclear Information System (INIS)

2004-09-01

SKB (the Swedish Nuclear Fuel and Waste Management Co), which is owned by the companies that operate the Swedish nuclear power plants, has been assigned the task of managing and disposing of the spent nuclear fuel from the reactors. The Nuclear Activities Act requires a programme of comprehensive research and development and other measures that are needed to manage and dispose of nuclear waste in a safe manner and to decommission and dismantle the nuclear power plants. SKB is now presenting RD and D-Programme 2004 in fulfilment of this requirement. The programme describes SKB's plans for the period 2005-2010. The period of immediate concern is 2005-2007. The level of detail for the three subsequent years is naturally lower.The programme provides a basis for designing systems for safe management and disposal of the radioactive waste from the nuclear power plants. SKB's plan is to implement deep disposal of the spent fuel in accordance with the KBS-3 method. In the RD and D-Programme we describe our activities and planning for this line of action and the work that is being conducted on alternative methods. Review of the programme can contribute valuable outside viewpoints. The regulatory authorities and the Government can clarify how they look upon different parts of the programme and stipulate guidelines for the future. Municipalities and other stakeholders can, after studying the programme, offer their viewpoints to SKB, the regulatory authorities or the Government.The goal for the period up to the end of 2008 is to be able to submit permit applications for the encapsulation plant and the deep repository. This RD and D-Programme therefore differs from the preceding ones in that it concentrates on questions relating to technology development for these facilities. The programmes for safety assessment and research on the long-term processes that take place in the deep repository are then linked together with the programmes for technology development. Another new

Nirex Safety Assessment Research Programme bibliography, 1990

International Nuclear Information System (INIS)

Cooper, M.J.

1990-10-01

This bibliography lists reports and papers written as part of the Nirex Safety Assessment Research Programme, which is concerned with disposal of low-level and intermediate-level waste (LLW and ILW) and associated radiological assessments. (author)

The Nirex safety assessment research programme for 1987/88

International Nuclear Information System (INIS)

Cooper, M.J.; Tasker, P.W.

1987-10-01

This report outlines the work of the Nirex Safety Assessment Research Programme during the period 1st April 1987 to 31st March 1988. The research programme has the specific objective of providing the information requirements of the post-emplacement radiological safety case for the disposal of low-level and intermediate-level radioactive waste in underground repositories. For convenience the programme has been divided into seven areas: physical containment, near-field radionuclide chemistry, evolution of the near-field aqueous environment, mass transfer in the geosphere, the biosphere, gas evolution and migration, and integrated studies. The near-field includes the waste, its immobilising medium, its container, the engineered structure in which the container is emplaced and the immediately adjacent geological formation disturbed by the construction of the repository. (author)

Results from the UK 3rd generation programme: Albion

Science.gov (United States)

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

2008-10-01

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

Prise en compte des ``courants de London'' dans la modélisation des supraconducteurs

Science.gov (United States)

Bossavit, Alain

1997-10-01

A model is given, in variational form, in which volumic “Bean currents”, ruled by Bean's law, and surface “London currents” coexist. This macroscopic model generalizes Bean's one, by appending to the critical density j_c a second parameter, with the dimension of a length, similar to London's depth λ. The one-dimensional version of the model is investigated, in order to link this parameter with the standard observable H-M characteristics On propose un modèle, sous forme variationnelle, associant des “courants de Bean” volumiques, décrits par la loi de Bean, et des “courants de London”, surfaciques. Ce modèle macroscopique généralise celui de Bean, caractérisé par le courant critique j_c, et fait intervenir un second paramètre, homogène à une longueur, analogue au λ de London. La version unidimensionnelle du modèle est étudiée en détail de manière à relier ce paramètre à l'observation des caractéristiques H-M usuelles.

The role of opinion research in communications programmes

International Nuclear Information System (INIS)

Curtin, Tom

1995-01-01

Nirex is a company financed by the UK nuclear industry to dispose of intermediate and some long-lived low-level radioactive waste. The company has no responsibility for high-level radioactive waste. Most low-level waste is disposed of at a shallow site owned by BNFL, one of Nirex's shareholders. At Nirex, we use opinion research in a number of ways: as a map to guide communications programmes; to set baselines and targets to isolate issues of concern to our publics. The Company carries out market research covering three key audiences: the general public, politicians, and journalists. For Nirex, opinion research is a map. It guides our communication programmes in dealing with our key audiences. Without it, we would be driving blind. Opinion research allows us to isolate key issues for communication. It also allows us to measure performance and to see which initiatives are successful and which are not

Evaluation of MODS Culture in the Diagnosis of Pulmonary Tuberculosis

Directory of Open Access Journals (Sweden)

Z Aminzadeh

2012-05-01

Full Text Available

Background and Objectives

Culture of M. tuberculosis is the golden standard for the diagnosis of TB which is a much more sensitive test than Smear examination. There is a strong need to use the new assays in order to speed up diagnostic methods. The aim of this research was to determine the evaluation of Microscopic Observation Drug Susceptibility culture in pulmonary tuberculosis in comparison with Ziehl-Neelsen stain and Lowenstein-Jensen culture of sputum.

Methods

The research method was a Cross-sectional (diagnostic test and the technique was observational-interview type. If the patient's history revealed clinical criteria compatible with TB and the infectious specialist’s judgment was that of "TB suspected case, the patient was considered a pulmonary TB suspect. Then, in addition to sputum Ziehl-Neelsen stain and culture for Lowenstein-Jensen, we carried out MODS culture as well.

Results

100 patients (48 male, 52 female with mean age of 52.9 ± 21.83 were evaluated. During sputum examination, 40% were Ziehl-Neelsen stain positive while 30% had positive sputum culture for Mycobacterium Tuberculosis in Lowenstein-Jensen and 47% had positive MODS culture. In comparison with sputum smear and Lowenstein-Jensen culture, MODS had a sensitivity of 82.5% and 86%, specificity of 77% and 70%, positive predictive value of 70% and 55%, negative predictive value of 86% and 92%, respectively.

Conclusion

Flux pinning characteristics of Sn-doped YBCO film by the MOD process

International Nuclear Information System (INIS)

Choi, S.M.; Shin, G.M.; Yoo, S.I.

2013-01-01

Highlights: ► The pinning effects of undoped and Sn-doped YBCO films by MOD were characterized. ► Sn-containing nanoparticles were trapped in Sn-doped YBCO films by MOD. ► Sn-containing nanoparticles were identified as the YBa 2 SnO 5.5 (YBSO) phase by TEM. ► The YBSO nanoparticles are responsible for improved flux pinning effect. ► We report the orientation relationship between YBSO nanoparticles and YBCO matrix. -- Abstract: Compared with the undoped YBa 2 Cu 3 O 7−δ (YBCO) film, 10 mol% Sn-doped YBCO film exhibited significantly enhanced critical current densities (J c ) in magnetic fields up to 5 T at 65 and 77 K for H//c, indicating that the Sn-doped YBCO film possesses more effective flux pinning centers. Both samples were grown on the SrTiO 3 (STO) (1 0 0) single crystal substrates by the metal-organic deposition (MOD) process. Larger J c (77 K, 1 T) values of Sn-doped YBCO film are observed over a wide field-orientation angle (θ) except the field-orientations close to the ab-plane of YBCO (85° c values for 85° 2 SnO 5.5 (YBSO) phase by STEM (scanning transmission electron microscopy)-EDS (energy dispersive X-ray spectroscopy) analysis. Further analyses by HR-TEM (high resolution-transmission electron microscopy) revealed that YBSO nanoparticles completely surrounded by the YBCO matrix had random orientation with YBCO while those located at the interface of YBCO/STO substrate had epitaxial relationship with YBCO

The JET project and the European fusion research programme

International Nuclear Information System (INIS)

Wuester, H.-O.

1984-01-01

The paper concerns the Joint European Torus (JET) project and the European Fusion Research Programme. Fusion as an energy source and commercial fusion power are briefly discussed. The main features of the JET apparatus and the tokamak magnetic field configuration are given. Also described are the specific aims of JET, and the proposed future fusion reactor programme. (U.K.)

RD and D-Programme 2004. Programme for research, development and demonstration of methods for the management and disposal of nuclear waste, including social science research

Energy Technology Data Exchange (ETDEWEB)

NONE

2004-09-01

SKB (the Swedish Nuclear Fuel and Waste Management Co), which is owned by the companies that operate the Swedish nuclear power plants, has been assigned the task of managing and disposing of the spent nuclear fuel from the reactors. The Nuclear Activities Act requires a programme of comprehensive research and development and other measures that are needed to manage and dispose of nuclear waste in a safe manner and to decommission and dismantle the nuclear power plants. SKB is now presenting RD and D-Programme 2004 in fulfilment of this requirement. The programme describes SKB's plans for the period 2005-2010. The period of immediate concern is 2005-2007. The level of detail for the three subsequent years is naturally lower.The programme provides a basis for designing systems for safe management and disposal of the radioactive waste from the nuclear power plants. SKB's plan is to implement deep disposal of the spent fuel in accordance with the KBS-3 method. In the RD and D-Programme we describe our activities and planning for this line of action and the work that is being conducted on alternative methods. Review of the programme can contribute valuable outside viewpoints. The regulatory authorities and the Government can clarify how they look upon different parts of the programme and stipulate guidelines for the future. Municipalities and other stakeholders can, after studying the programme, offer their viewpoints to SKB, the regulatory authorities or the Government.The goal for the period up to the end of 2008 is to be able to submit permit applications for the encapsulation plant and the deep repository. This RD and D-Programme therefore differs from the preceding ones in that it concentrates on questions relating to technology development for these facilities. The programmes for safety assessment and research on the long-term processes that take place in the deep repository are then linked together with the programmes for technology development. Another

NetMOD Version 2.0 User?s Manual.

Energy Technology Data Exchange (ETDEWEB)

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

2015-10-01

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

Co-ordinated research programme on applications of stable isotope tracers in human nutrition research

International Nuclear Information System (INIS)

1989-01-01

This Co-ordinated Research Programme (CRP) was formally established by the Agency in October 1988, and has since then expanded to encompass 13 participants in 13 countries. Its general objective is to help establish competence in the use of stable isotope techniques, particularly in developing countries, and particularly with reference to applications of 2 H, 13 C, 15 N, and 18 O. This report summarizes the discussions that took place during the first Research Co-ordination Meeting (RCM). Working papers (progress reports) presented by the participants are included as annexes together with a preliminary report on the results of a series of intercomparison exercises involving enriched stable isotope reference materials containing 2 H, 13 C, 15 N and 18 O. For the future it was agreed that more work needs to be done to harmonize the analytical techniques being used, and to obtain support for new CRPs relating to human energy expenditure studies in pregnancy, lactation, growth and other conditions, and to studies of nitrogen turnover in relation to malnutrition and liver function. Refs, figs and tabs

Transport phenomena in the edge of Alcator C-Mod plasmas

International Nuclear Information System (INIS)

Terry, J.L.; Basse, N.P.; Cziegler, I.; Greenwald, M.; LaBombard, B.; Edlund, E.M.; Hughes, J.W.; Lin, L.; Lin, Y.; Porkolab, M.; Veto, B.; Wukitch, S.J.; Grulke, O.; Zweben, S.J.; Sampsell, M.

2005-01-01

Two aspects of edge turbulence and transport in Alcator C-Mod are explored. The quasi-coherent mode, an edge fluctuation present in Enhanced Da H-mode plasmas, is examined with regard to its role in the enhanced particle transport found in these plasmas, its in/out asymmetry, its poloidal wave number, and its radial width and location. It is shown to play a dominant role in the perpendicular particle transport. The QCM is not observed at the inboard midplane, indicating that its amplitude there is significantly smaller than on the outboard side. The peak amplitude of the QCM is found just inside the separatrix, with a radial width ≥5 mm, leading to a non-zero amplitude outside the separatrix and qualitatively consistent with its transport enhancement. Also examined are the characteristics of the intermittent convective transport, associated with 'blobs' and typically occurring in the scrape-off-layer. The blobs are qualitatively similar in L- and H-mode. When their sizes, occurrence frequencies, and magnitudes are compared, it is found that the blob size may be somewhat smaller in ELMfree H-Mode, and blob frequency is similar. A clear difference is seen in the blob magnitude in the far SOL, with ELMfree H-mode showing a smaller perturbation there than L-mode. As the Greenwald density limit is approached (n/n GW ≥0.7), blobs are seen inside the separatrix, consistent with the observation that the high cross-field transport region, normally found in the far scrape-off, penetrates the closed flux surfaces at high n/n GW . (author)

Comparison of SCDAP/RELAP5/MOD3 to TRAC-PF1/MOD1 for timing analysis of PWR fuel pin failures

International Nuclear Information System (INIS)

Jones, K.R.; Katsma, K.R.; Wade, N.L.; Siefken, L.J.; Straka, M.

1991-01-01

A comparison has been made of SCDAP/RELAP5/MOD3- and TRAC-PF1/MOD1- based calculations of the fuel pin failure timing (time from containment isolation signal to first fuel pin failure) in a loss-of-coolant accident (LOCA). The two codes were used to calculate the thermal-hydraulic boundary conditions for a complete, double-ended, offset-shear break of a cold leg in a Westinghouse 4-loop pressurized water reactor. Both calculations used the FRAPCON-2 code to calculate the steady-state fuel rod behavior and the FRAP-T6 code to calculate the transient fuel rod behavior. The analysis was performed for 16 combinations of fuel burnups and power peaking factors extending up to the Technical Specifications limits. While all calculations were made on a best-estimate basis, the SCDAP/RELAP5/MOD3 code has not yet been fully assessed for large-break LOCA analysis. The results indicate that SCDAP/RELAP5/MOD3 yields conservative fuel pin failure timing results in comparison to those generated using TRAC-PF1/MOD1. 7 refs., 5 figs

Highlights of the UKAEA Underlying Research Programme: April 1988-March 1989

International Nuclear Information System (INIS)

1990-01-01

Investment in fundamental research is essential to the success of any organisation whose business is the selling of research and development and the services relating to it. The resulting scientific and technical excellence is the hall-mark of a major contract research and development organisation and its main product. Fundamental research in the AEA is co-ordinated through the Underlying Research Programme. The Programme has to keep closely in touch with all the applied projects, in order to identify within these the problems that are hindering progress and might therefore benefit from further investigation. It also has the responsibility for developing new skills and techniques across the AEA. This brochure highlights some of the projects undertaken as part of the Underlying Research Programme. The Programme is organised into fifteen different areas of research, with the research projects not obviously fitting into any of these areas having a separate section to themselves. The text introduces each of these areas in turn, and then describes two or three examples of the sort of work undertaken within it. The areas are radiation effects, fracture studies, chemical effects at surfaces, surface physics and corrosion, fluid mechanics and heat transfer, nuclear studies, neutron beam studies, theoretical sciences, instrumentation, reactor physics and control, fabrication processes, laser isotope separation, nuclear fuel cycle studies, quantum electronics and radiological protection. (author)

An activity-based cost analysis of the Honduras community-based, integrated child care (AIN-C) programme.

Science.gov (United States)

Fiedler, John L; Villalobos, Carlos A; De Mattos, Annette C

2008-11-01

The Honduras AIN-C programme is a preventive health and nutrition programme of the Honduras Ministry of Health (MOH) that relies on volunteers to help mothers monitor and maintain the adequate growth of young children. A quasi-experimental, design-based evaluation found that the programme achieved near-universal coverage and was effective in improving mothers' child-rearing knowledge, attitudes and practices, including feeding and appropriate care-giving and care-seeking practices for children with diarrhoea and acute respiratory illness. The programme is widely regarded as a model. This study was undertaken to provide the first comprehensive estimates of the cost of the AIN-C programme, with the goal of providing a programme and financial planning tool for Honduras. An additional comparison of study findings was also undertaken to determine the cost of the AIN-C programme's community-based services relative to a similar facility-based service. Expressed in mid-2005 US dollars, the study found that after the programme is phased-in: (1) the annual, recurrent cost per child under 2 years participating in the programme is $6.43; (2) the annual, incremental budget requirements per child under 2 years participating in the programme are $3.90; (3) the cost of an AIN-C monthly growth monitoring and counselling session per child is 11% of the cost of a traditional MOH, facility-based growth and development consultation per child; and (4) the effect of mothers substituting AIN-C monitor care for MOH facility-based care 'saves' 203 000 outpatient visits a year, with a potential cost saving of $1.66 million, the equivalent of 60% of the recurrent cost of the programme and roughly equal to the annual incremental budget requirements of the programme. Sensitivity analysis of the cost estimates is performed to provide insight, for countries considering introducing a similar programme, into how modifications of key characteristics of the programme affect its costs.

Cold Fronts Research Programme: Progress, Future Plans, and Research Directions.

Science.gov (United States)

Ryan, B. F.; Wilson, K. J.; Garratt, J. R.; Smith, R. K.

1985-09-01

Following the analysis of data collected during Phases land II of the Cold Fronts Research Programme (CFRP) a conceptual model for the Australian summertime "cool change" has been proposed. The model provides a focus and a framework for the design of Phase III.The model is based on data gathered from a mesoscale network centered on Mount Gambier, South Australia, and includes the coastal waters to the west and relatively flat terrain to the east. The first objective of Phase III is to generalize the model so that it is applicable to the ocean waters to the far west of Mount Gambier and to the more rugged terrain farther to the east in the vicinity of Melbourne, Victoria. The remaining objectives concentrate on resolving unsatisfactory aspects of the model such as the evolution of convective lines and the relationship between the surface cold front and the upper-tropospheric cold pool and its associated jet stream.The integrated nature of the Cold Fronts Research Programme has meant that it has stimulated a wide range of research activities that extend beyond the field observations. The associated investigations include climatological, theoretical, and numerical modeling studies.

Upgrade of the RFX-mod real time control system

Energy Technology Data Exchange (ETDEWEB)

Manduchi, G., E-mail: gabriele.manduchi@igi.cnr.it [Consorzio RFX, Euratom-ENEA Association, Corso Stati Uniti 4, Padova 35127 (Italy); Barbalace, A.; Luchetta, A.; Soppelsa, A.; Taliercio, C.; Zampiva, E. [Consorzio RFX, Euratom-ENEA Association, Corso Stati Uniti 4, Padova 35127 (Italy)

2012-12-15

Highlights: Black-Right-Pointing-Pointer The paper describes the experience in running the real-time control system of RFX-mod. Black-Right-Pointing-Pointer It proposes a new architecture based multicore technology. Black-Right-Pointing-Pointer It analyzes two different solutions for data acquisition. Black-Right-Pointing-Pointer It discusses the effect of non simultaneous sampling in acquisition. Black-Right-Pointing-Pointer It provides some preliminary performance measurements. - Abstract: The real-time control system of RFX-mod, in operation since 2005, has been successful and has allowed several important achievements in the RFX physics research program. As a consequence of this fact, new control algorithms are under investigation, which are more demanding in terms of both enhanced computing power and reduced system latency, currently around 1.5 ms. For this reason, a major upgrade of the system is being considered, and a new architecture has been proposed, taking advantage of the rapid evolution of computer technology in the last years. The central component of the new architecture is a Linux-based multicore server, where individual cores replace the VME computers. The server is connected to the I/O via PCI-e based bus extenders, and every PCI-e connection is managed by a separate core. The system is supervised by MARTe, a software framework for real-time applications written in C++ and developed at JET and currently used for the JET vertical stabilization and in other fusion devices.

The European Fusion Research and Development Programme and the ITER Project

International Nuclear Information System (INIS)

Green, B J

2006-01-01

The EURATOM fusion research and development programme is a well integrated and coordinated programme. It has the objective of ''developing the technology for a safe, sustainable, environmentally responsible and economically viable energy source.'' The programme is focussed on the magnetic confinement approach and supports 23 Associations which involve research entities (many with experimental and technology facilities) each having a bilateral contractual relationship with the European Commission. The paper will describe fusion reactions and present their potential advantages as an energy source. Further, it will describe the EURATOM programme and how it is organised and implemented. The success of the European programme and that of other national programmes, have provided the basis for the international ITER Project, which is the next logical step in the development of fusion energy. The paper will describe ITER, its aims, its design, and the supporting manufacture of prototype components. The European contribution to ITER, the exploitation of the Joint European Torus (JET), and the long-term reactor technology R and D are carried out under the multilateral European Fusion Development Agreement (EFDA)

Science Academies' Summer Research Fellowship Programme for ...

Indian Academy of Sciences (India)

IAS Admin

2013-11-30

Nov 30, 2013 ... Science Academies' Summer Research Fellowship Programme for. Students and Teachers – 2014. Sponspored by. Indian Academy of Sciences, Bangalore. Indian National Science Academy, New Delhi. The National Academy of Sciences, India, Allahabad. The three national science academies offer ...

Assessment and improvement of condensation model in RELAP5/MOD3

Energy Technology Data Exchange (ETDEWEB)

Rho, Hui Cheon; Choi, Kee Yong; Park, Hyeon Sik; Kim, Sang Jae [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of); Lee, Sang Il [Korea Power Engineering Co., Inc., Seoul (Korea, Republic of)

1997-07-15

The objective of this research is to remove the uncertainty of the condensation model through the assessment and improvement of the various heat transfer correlations used in the RELAP5/MOD3 code. The condensation model of the standard RELAP5/MOD3 code is systematically arranged and analyzed. A condensation heat transfer database is constructed from the previous experimental data on various condensation phenomena. Based on the constructed database, the condensation models in the code are assessed and improved. An experiment on the reflux condensation in a tube of steam generator in the presence of noncondensable gases is planned to acquire the experimental data.

Density limit and cross-field edge transport scaling in Alcator C-Mod

International Nuclear Information System (INIS)

LaBombard, B.

2002-01-01

Experiments in Alcator C-Mod have uncovered a direct link between the character and scaling of edge transport and the empirical Greenwald density limit (n G ). In low to moderate density discharges, the scrape-off layer (SOL) exhibits a two-layer structure: a near SOL (∼5 mm zone) with steep density and temperature gradients and a far SOL with flatter profiles. In the far SOL, the transport fluxes exhibit large transport events ('bursts' which carry particles to main-chamber structures. In the near SOL, transport fluxes appear to be less 'bursty' particle diffusivities in this region is found to increase strongly with local plasma collisionality. As n/n G (or collisionality) is raised, cross-field heat convection begins to compete with parallel conduction to the divertor. At N/n G ∼0.5, T E at the separatrix is reduced. As n/n G approaches ∼1, regions inside the separatrix exhibit flatter profiles with 'bursty' transport behavior; cross-field heat convection to main-chamber structures becomes comparable to the radiated power. Thus as n/n G is increased, cross-field edge transport physics progressively changes, ultimately impacting the power balance of the discharge near N/n G ∼1. (author)

Bascule d'un modèle poutre à un modèle 3D en dynamique des machines tournantes

OpenAIRE

Tannous , Mikhael; Cartraud , Patrice; Dureisseix , David; Torkhani , Mohamed

2013-01-01

National audience; Les problèmes de machines tournantes incluant un contact rotor-stator, nécessitent un maillage 3D de la zone de contact. Cependant, un modèle 3D pour toute la durée de simulation conduit à des temps de calcul rédhibitoires. Or un modèle poutre est suffisant pour décrire la dynamique de la machine tournante hors contact. Une stratégie qui permet d'utiliser un modèle poutre et un autre 3D, pendant deux phases différentes durant la même simulation, permet donc de gagner en tem...

RDandD Programme 2007. Programme for research, development and demonstration of methods for the management and disposal of nuclear waste

International Nuclear Information System (INIS)

2007-09-01

The programme describes in general terms the planned measures and the facilities that are needed for the task, with a focus on the plans for the period 2008-2013. The period of immediate concern is 2008-2010. The level of detail for the three subsequent years is naturally lower. The programme provides a basis for designing systems to manage and dispose of the radioactive waste from the nuclear power plants. SKB intends to dispose of the spent nuclear fuel in accordance with the KBS-3 method. In the RDandD Programme we describe our activities and the planning for it. We also deal with societal research and other methods for disposal of spent nuclear fuel. The planning for low- and intermediate-level waste, as well as for the societal research, is presented in separate parts. The upcoming review of the programme can contribute valuable outside viewpoints. The regulatory authorities and the Government can clarify how they view different parts of the activity. Municipalities and other stakeholders can, after studying the programme, offer their viewpoints to SKB, the regulatory authorities or the Government. The most important milestone during the coming three-year period is to submit applications under the Nuclear Activities Act for the final repository for spent nuclear fuel and under the Environmental Code for the final repository system. RDandD programme 2007 therefore focuses on the technology development that is needed to realize the final repository for spent nuclear fuel. The site investigations in Forsmark and Laxemar will be concluded in 2007. The work of compiling the applications for the final repository is under way. In contrast to the immediately preceding programmes, RDandD Programme 2007 therefore also contains a summary of the site investigation phase and a look ahead at the steps that remain before the final repository can be put into operation. RDandD Programme 2007 consists of six parts: Part I SKB's plan of action; Part II Final repository for spent

RDandD Programme 2007. Programme for research, development and demonstration of methods for the management and disposal of nuclear waste

Energy Technology Data Exchange (ETDEWEB)

2007-09-15

The programme describes in general terms the planned measures and the facilities that are needed for the task, with a focus on the plans for the period 2008-2013. The period of immediate concern is 2008-2010. The level of detail for the three subsequent years is naturally lower. The programme provides a basis for designing systems to manage and dispose of the radioactive waste from the nuclear power plants. SKB intends to dispose of the spent nuclear fuel in accordance with the KBS-3 method. In the RDandD Programme we describe our activities and the planning for it. We also deal with societal research and other methods for disposal of spent nuclear fuel. The planning for low- and intermediate-level waste, as well as for the societal research, is presented in separate parts. The upcoming review of the programme can contribute valuable outside viewpoints. The regulatory authorities and the Government can clarify how they view different parts of the activity. Municipalities and other stakeholders can, after studying the programme, offer their viewpoints to SKB, the regulatory authorities or the Government. The most important milestone during the coming three-year period is to submit applications under the Nuclear Activities Act for the final repository for spent nuclear fuel and under the Environmental Code for the final repository system. RDandD programme 2007 therefore focuses on the technology development that is needed to realize the final repository for spent nuclear fuel. The site investigations in Forsmark and Laxemar will be concluded in 2007. The work of compiling the applications for the final repository is under way. In contrast to the immediately preceding programmes, RDandD Programme 2007 therefore also contains a summary of the site investigation phase and a look ahead at the steps that remain before the final repository can be put into operation. RDandD Programme 2007 consists of six parts: Part I SKB's plan of action; Part II Final repository for spent

RDandD Programme 2007. Programme for research, development and demonstration of methods for the management and disposal of nuclear waste

Energy Technology Data Exchange (ETDEWEB)

2007-09-15

The programme describes in general terms the planned measures and the facilities that are needed for the task, with a focus on the plans for the period 2008-2013. The period of immediate concern is 2008-2010. The level of detail for the three subsequent years is naturally lower. The programme provides a basis for designing systems to manage and dispose of the radioactive waste from the nuclear power plants. SKB intends to dispose of the spent nuclear fuel in accordance with the KBS-3 method. In the RDandD Programme we describe our activities and the planning for it. We also deal with societal research and other methods for disposal of spent nuclear fuel. The planning for low- and intermediate-level waste, as well as for the societal research, is presented in separate parts. The upcoming review of the programme can contribute valuable outside viewpoints. The regulatory authorities and the Government can clarify how they view different parts of the activity. Municipalities and other stakeholders can, after studying the programme, offer their viewpoints to SKB, the regulatory authorities or the Government. The most important milestone during the coming three-year period is to submit applications under the Nuclear Activities Act for the final repository for spent nuclear fuel and under the Environmental Code for the final repository system. RDandD programme 2007 therefore focuses on the technology development that is needed to realize the final repository for spent nuclear fuel. The site investigations in Forsmark and Laxemar will be concluded in 2007. The work of compiling the applications for the final repository is under way. In contrast to the immediately preceding programmes, RDandD Programme 2007 therefore also contains a summary of the site investigation phase and a look ahead at the steps that remain before the final repository can be put into operation. RDandD Programme 2007 consists of six parts: Part I SKB's plan of action; Part II Final repository for

FUDA MOD-2: a computer program for simulation the performance of fuel element validation exercise

International Nuclear Information System (INIS)

Chouhan, S.K.; Tripathi, R.M.; Prasad, P.N.; Chauhan, Ashok

2014-01-01

The PHWR fuel element performance is evaluated using the fuel analysis computer code FUDA MOD2. It is specifically written for performance simulation of UO 2 fuel pellet, located in zirconium alloy sheath operating under coolant pressure. For specific element power histories, the code investigates the variables and their interactions that govern fuel element performance. The input data requires pellet dimensions, element dimensions, sheath properties, heat transfer data, thermal hydraulic parameters of coolant, the inner filler gas composition, flux gradient and linear heat ratings (LHR) at different burn up. The output data generated by the code are radial temperature profile of fuel and sheath, fuel sheath-gap heat transfer coefficient, fission gas generated and released, fission gas pressure, sheath stress and strain for different burn-up zones. The code has been verified against literature data and post irradiation examinations carried out. It is also bench marked against various international fuel element simulation programmes available with water cooled reactors operating countries. The present paper describes the FUDA MOD2 code verification studies carried out using the literature data and post irradiation examination data. (author)

ModFOLD6: an accurate web server for the global and local quality estimation of 3D protein models.

Science.gov (United States)

Maghrabi, Ali H A; McGuffin, Liam J

2017-07-03

Methods that reliably estimate the likely similarity between the predicted and native structures of proteins have become essential for driving the acceptance and adoption of three-dimensional protein models by life scientists. ModFOLD6 is the latest version of our leading resource for Estimates of Model Accuracy (EMA), which uses a pioneering hybrid quasi-single model approach. The ModFOLD6 server integrates scores from three pure-single model methods and three quasi-single model methods using a neural network to estimate local quality scores. Additionally, the server provides three options for producing global score estimates, depending on the requirements of the user: (i) ModFOLD6_rank, which is optimized for ranking/selection, (ii) ModFOLD6_cor, which is optimized for correlations of predicted and observed scores and (iii) ModFOLD6 global for balanced performance. The ModFOLD6 methods rank among the top few for EMA, according to independent blind testing by the CASP12 assessors. The ModFOLD6 server is also continuously automatically evaluated as part of the CAMEO project, where significant performance gains have been observed compared to our previous server and other publicly available servers. The ModFOLD6 server is freely available at: http://www.reading.ac.uk/bioinf/ModFOLD/. © The Author(s) 2017. Published by Oxford University Press on behalf of Nucleic Acids Research.

Lifetime prediction of ammunition at TNO Prins Maurits Laboratory

NARCIS (Netherlands)

Leenders, A.P.M.; Driel, C.A. van; Klerk, W.P.C. de; Keizers, H.L.J.

2000-01-01

TNO-PML is an independent R & D organisation, with the Dutch MoD as its most important customer. In 1993, the ‘Lifetime prediction of ammunition’ research programme, funded by the MoD, was started at TNO-PML. One of the reasons for starting this programme was the economical profit that can be made

An Optimization Scheme for ProdMod

International Nuclear Information System (INIS)

Gregory, M.V.

1999-01-01

A general purpose dynamic optimization scheme has been devised in conjunction with the ProdMod simulator. The optimization scheme is suitable for the Savannah River Site (SRS) High Level Waste (HLW) complex operations, and able to handle different types of optimizations such as linear, nonlinear, etc. The optimization is performed in the stand-alone FORTRAN based optimization deliver, while the optimizer is interfaced with the ProdMod simulator for flow of information between the two

LIEKKI 2 - Combustion and gasification research programme 1993- 1998. Final report

Energy Technology Data Exchange (ETDEWEB)

Hupa, M [ed.

1999-12-31

The six-year Combustion and Gasification Research Programme LIEKKI 2 (1993-1998) was oriented towards research serving the development of energy production technologies based on combustion and gasification. The programme was divided into six research areas: 1. Modelling of the furnace processes (39 projects); 2. Chemistry of gaseous emission components (28); 3. Particle behaviour, ash, aerosols (42); 4. New combustion and gasification technologies (27); 5. Black liquor (33) and 6. Conventional combustion technologies, waste incineration (19). The main aim of the research has been to develop new, more efficient and environmentally friendly techniques. The development of conventional combustion technology has also been an important part of the programme. Another important goal has been to maintain and develop maintain the competence of the research organisations in the combustion area and to intensify their collaboration. Concerning its research contents and its objectives LIEKKI 2, like its forerunner, has not been fuel-specific. The programme has investigated the thermal conversion of oil, gas, black liquor, and coal as well as that of peat, biofuels, and various waste materials, and it has further advanced the know-how concerning the utilisation of these fuels. This approach differs from the usual fuel-specific differentiation, which, for instance, IEA (International Energy Agency) and EU have applied in their research activities. This approach seems in retrospect to have been the right choice. It has been appropriate to stimulate co-operation between parties who would not seek co-operation spontaneously. One example of this is the development of a steelmaking process by a Finnish steel manufacturer under the LIEKKI programme. The programme has also provided synergetic advantages to the development of the recovery boiler processes of the pulp industry. Assessing the impact of the programme is a matter of many facets. The six-year research work and a total

LIEKKI 2 - Combustion and gasification research programme 1993- 1998. Final report

Energy Technology Data Exchange (ETDEWEB)

Hupa, M. [ed.

1998-12-31

The six-year Combustion and Gasification Research Programme LIEKKI 2 (1993-1998) was oriented towards research serving the development of energy production technologies based on combustion and gasification. The programme was divided into six research areas: 1. Modelling of the furnace processes (39 projects); 2. Chemistry of gaseous emission components (28); 3. Particle behaviour, ash, aerosols (42); 4. New combustion and gasification technologies (27); 5. Black liquor (33) and 6. Conventional combustion technologies, waste incineration (19). The main aim of the research has been to develop new, more efficient and environmentally friendly techniques. The development of conventional combustion technology has also been an important part of the programme. Another important goal has been to maintain and develop maintain the competence of the research organisations in the combustion area and to intensify their collaboration. Concerning its research contents and its objectives LIEKKI 2, like its forerunner, has not been fuel-specific. The programme has investigated the thermal conversion of oil, gas, black liquor, and coal as well as that of peat, biofuels, and various waste materials, and it has further advanced the know-how concerning the utilisation of these fuels. This approach differs from the usual fuel-specific differentiation, which, for instance, IEA (International Energy Agency) and EU have applied in their research activities. This approach seems in retrospect to have been the right choice. It has been appropriate to stimulate co-operation between parties who would not seek co-operation spontaneously. One example of this is the development of a steelmaking process by a Finnish steel manufacturer under the LIEKKI programme. The programme has also provided synergetic advantages to the development of the recovery boiler processes of the pulp industry. Assessing the impact of the programme is a matter of many facets. The six-year research work and a total

Publicly administrated nuclear waste management research programme 1994-1996. Final report

Energy Technology Data Exchange (ETDEWEB)

Vuori, S. [ed.] [VTT Energy, Espoo (Finland)

1997-09-01

The main objective of the JYT-programme has been to provide the authorities with independent information and research results relevant for the safety of nuclear waste management. The main emphasis in this research programme has been devoted to the final disposal of spent fuel. The whole area of the research programme has been subdivided into following main topic areas: (1) bedrock structure and stability, rock investigation methods and characteristics and flow of ground water, (2) release of radionuclides from a repository and subsequent transport in the bedrock, (3) performance and safety assessment of repositories and other phases of nuclear waste management, (4) natural analogue studies, (5) waste management technology and costs and (6) socio political and other societal issues and environmental impact assessment.

Publicly administrated nuclear waste management research programme 1994-1996. Final report

International Nuclear Information System (INIS)

Vuori, S.

1997-09-01

The main objective of the JYT-programme has been to provide the authorities with independent information and research results relevant for the safety of nuclear waste management. The main emphasis in this research programme has been devoted to the final disposal of spent fuel. The whole area of the research programme has been subdivided into following main topic areas: (1) bedrock structure and stability, rock investigation methods and characteristics and flow of ground water, (2) release of radionuclides from a repository and subsequent transport in the bedrock, (3) performance and safety assessment of repositories and other phases of nuclear waste management, (4) natural analogue studies, (5) waste management technology and costs and (6) socio political and other societal issues and environmental impact assessment

Bioenergy Research Programme. Yearbook 1994. Production of wood fuels

International Nuclear Information System (INIS)

Alakangas, E.

1995-01-01

BIOENERGIA Research Programme is one of energy technology programmes of the Finnish Ministry of Trade and Industry (in 1995 TEKES, Technology Development Center). The aim of Bioenergy Research Programme is to increase the use of economically profitable and environmentally sound bioenergy by improving the competitiveness of present peat and wood fuels. Research and development projects will also develop new economically competitive biofuels and new equipment and methods for production, handling and using of biofuels. The funding for 1994 was nearly 50 million FIM and projects numbered 60. The main goal of the production of wood fuels research area is to develop new production methods in order to decrease the production costs to the level of imported fuels. The total potential of the wood fuel use should be at least 1.0 million toe/a (5.5 million m 3 ). There were 27 projects in 1994 for research on wood fuel production. This part of the yearbook 1994 presents the main results of these projects. The wood reserves do not limit the obtainability of the target. Research and development work has, however, directed to development of equipment and research on wood fuels production chains. Many devices, designed for both separate and integrated production of wood fuels became ready or were becoming ready for prototyping, to be used for production tests. Results of the biomass harvesting and properties research were obtained for utilization in 1994. According to the results it is possible to obtain the desired targets both in integrated and separated production of wood fuels. (author)

High-resolution disruption halo current measurements using Langmuir probes in Alcator C-Mod

Science.gov (United States)

Tinguely, R. A.; Granetz, R. S.; Berg, A.; Kuang, A. Q.; Brunner, D.; LaBombard, B.

2018-01-01

Halo currents generated during disruptions on Alcator C-Mod have been measured with Langmuir ‘rail’ probes. These rail probes are embedded in a lower outboard divertor module in a closely-spaced vertical (poloidal) array. The dense array provides detailed resolution of the spatial dependence (~1 cm spacing) of the halo current distribution in the plasma scrape-off region with high time resolution (400 kHz digitization rate). As the plasma limits on the outboard divertor plate, the contact point is clearly discernible in the halo current data (as an inversion of current) and moves vertically down the divertor plate on many disruptions. These data are consistent with filament reconstructions of the plasma boundary, from which the edge safety factor of the disrupting plasma can be calculated. Additionally, the halo current ‘footprint’ on the divertor plate is obtained and related to the halo flux width. The voltage driving halo current and the effective resistance of the plasma region through which the halo current flows to reach the probes are also investigated. Estimations of the sheath resistance and halo region resistivity and temperature are given. This information could prove useful for modeling halo current dynamics.

Conceptual design of the 7 megawatt Mod-5B wind turbine generator

Science.gov (United States)

Douglas, R. R.

1982-01-01

Similar to MOD-2, the MOD-5B wind turbine generator system is designed for the sole purpose of providing electrical power for distribution by a major utility network. The objectives of the MOD-2 and MOD-5B programs are essentially identical with one important exception; the cost-of-electricity (COE) target is reduced from 4 cent/Kwhr on MOD-2 to 3 cent/Kwhr on MOD-5B, based on mid 1977 dollars and large quantity production. The MOD-5B concept studies and eventual concept selection confirmed that the program COE targets could not only be achieved but substantially bettered. Starting from the established MOD-2 technology as a base, this achievement resulted from a combination of concept changes, size changes, and design refinements. The result of this effort is a wind turbine system that can compete with conventional power generation over significant geographical areas, increasing commercial market potential by an order of magnitude.

The Wind Energy programme - SFOE Research Programme 2000 - 2003; Programm Wind. Konzept BFE-Forschungsprogramm 'Wind' 2000 - 2003

Energy Technology Data Exchange (ETDEWEB)

Horbaty, R.

2001-07-01

This document, issued by the Swiss Federal Office of Energy (SFOE) describes the concept behind the Swiss wind energy programme. The first part of the report discusses the origins and development of the wind energy programme in Switzerland, discussing the importance of wind energy and policy matters associated with its promotion. The experience gained during the previous research programmes is reviewed. The degree to which targets were reached, promotional activities, the central government's own wind energy activities and the results of a programme evaluation are discussed. Lists of projects that have been realised and activities that have been carried out are presented and positive and negative influences on development are noted. A second part is dedicated to the goals of the wind energy programme in terms of target figures for the year 2010 and the strategies chosen to reach these goals, including pilot and demonstration projects (P and D) and promotional activities. Details of the P and D programme including lists of wind-power projects to be supported, the priorities that have been set and information and further education that is to be provided, are given. New activities in the wind power area such as the development of new type of wind turbine especially suited to alpine conditions are discussed. The role of the Swiss Association for Wind Energy 'Suisse Eole' as a network-partner in the wind energy programme is discussed. An appendix provides details of wind energy projects in Switzerland, market partners and customers. The results of a survey made of wind energy activities at Swiss institutes of higher education are presented.

NetMOD version 1.0 user's manual

Energy Technology Data Exchange (ETDEWEB)

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

2014-01-01

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

Comparison of Scrape-off Layer Turbulence in Alcator C-Mod with Three Dimensional Gyrofluid Computations

International Nuclear Information System (INIS)

Zweben, S.J.; Scott, B.D.; Terry, J.L.; LaBombard, B.; Hughes, J.W.; Stotler, D.P.

2009-01-01

This paper describes quantitative comparisons between turbulence measured in the scrape-off layer (SOL) of Alcator C-Mod (S. Scott, A. Bader, M. Bakhtiari et al., Nucl. Fusion 47, S598 (2007)) and three dimensional computations using electromagnetic gyrofluid equations in a two-dimensional tokamak geometry. These comparisons were made for the outer midplane SOL for a set of inner-wall limited, near-circular Ohmic plasmas. The B field and plasma density were varied to assess gyroradius and collisionality scaling. The poloidal and radial correlation lengths in the experiment and computation agreed to within a factor of 2 and did not vary significantly with either B or density. The radial and poloidal propagation speeds and the frequency spectra and poloidal k-spectra also agreed fairly well. However, the autocorrelation times and relative Da fluctuation levels were higher in the experiment by more than a factor of 2. Possible causes for these disagreements are discussed.

EMC3-EIRENE modeling of toroidally-localized divertor gas injection experiments on Alcator C-Mod

Energy Technology Data Exchange (ETDEWEB)

Lore, J.D., E-mail: lorejd@ornl.gov [Oak Ridge National Laboratory, Oak Ridge, TN 37831 (United States); Reinke, M.L. [York Plasma Institute, Department of Physics, University of York, Heslington, York YO10 5DD (United Kingdom); LaBombard, B. [Plasma Science and Fusion Center, MIT, Cambridge, MA 02139 (United States); Lipschultz, B. [York Plasma Institute, Department of Physics, University of York, Heslington, York YO10 5DD (United Kingdom); Churchill, R.M. [Plasma Science and Fusion Center, MIT, Cambridge, MA 02139 (United States); Pitts, R.A. [ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance (France); Feng, Y. [Max Planck Institute for Plasma Physics, Greifswald (Germany)

2015-08-15

Experiments on Alcator C-Mod with toroidally and poloidally localized divertor nitrogen injection have been modeled using the three-dimensional edge transport code EMC3-EIRENE to elucidate the mechanisms driving measured toroidal asymmetries. In these experiments five toroidally distributed gas injectors in the private flux region were sequentially activated in separate discharges resulting in clear evidence of toroidal asymmetries in radiated power and nitrogen line emission as well as a ∼50% toroidal modulation in electron pressure at the divertor target. The pressure modulation is qualitatively reproduced by the modeling, with the simulation yielding a toroidal asymmetry in the heat flow to the outer strike point. Toroidal variation in impurity line emission is qualitatively matched in the scrape-off layer above the strike point, however kinetic corrections and cross-field drifts are likely required to quantitatively reproduce impurity behavior in the private flux region and electron temperatures and densities directly in front of the target.

1981 research programme and budget of Hahn-Meitner-Institut fuer Kernforschung Berlin

International Nuclear Information System (INIS)

Anon.

1981-01-01

Hahn-Meitner-Institut fuer Kernforschung Berlin (HMI) is one of the twelve large research centers of the Federal Republic of Germany; like the other centers, it has to present a combined research programme and budget (programme budget) every year. In these programme budgets, as in the medium-term financial planning in the federal budget, planning for the current year is combined with a medium-term plan for the three next years. For the year 1981, the budget of HMI includes a total expenditure of about DM 85 million, DM 71.2 million of which are direct R + D expenditures. This R + D programme is carried by 396 of the total staff of 705. Research is done in the following fields (approximate figures): Heavy ion physics DM 23.0 million. Radiation- and photochemistry DM 11.4 million. Solid state research DM 20.9 million. Nuclear chemistry DM 8.9 million. Data processing/electronics DM 7.0 million. (orig./UA) [de

IAEA activities related to research reactor fuel conversion and spent fuel return programmes

International Nuclear Information System (INIS)

Ritchie, I.G.; Adelfang, P.; Goldman, I.N.

2004-01-01

Full text: The IAEA has been involved for more than twenty years in supporting international nuclear non-proliferation efforts associated with reducing the amount of highly enriched uranium (HEU) in international commerce. IAEA projects and activities have directly supported the Reduced Enrichment for Research and Test Reactors (RERTR) programme, as well as directly associated efforts to return research reactor fuel to the country of origin where it was originally enriched. IAEA efforts have included the development and maintenance of several data bases with information related to research reactors and research reactor spent fuel inventories that have been essential in planning and managing both RERTR and spent fuel return programmes. Other IAEA regular budget programmes have supported research reactor fuel conversion from HEU to low enriched uranium, and in addressing issues common to many member states with spent fuel management problems and concerns. The paper briefly describes IAEA involvement since the early 1980's in these areas, including regular budget and Technical Co-operation programme activities, and focuses on efforts in the past five years to continue to support and accelerate U.S. and Russian research reactor spent fuel return programmes. It is hoped that an announcement of the extension of the U.S. Acceptance Programme, which is expected in the very near future, will facilitate the life extensions of many productive TRIGA reactors around the world. (author)

Observations of core modes during RF-generated internal transport barriers in Alcator C-Mod

Energy Technology Data Exchange (ETDEWEB)

Lynn, A G [Fusion Research Center, University of Texas at Austin, Austin, TX (United States); Phillips, P E [Fusion Research Center, University of Texas at Austin, Austin, TX (United States); Hubbard, A E [Plasma Science and Fusion Center, MIT, Cambridge, MA (United States); Wukitch, S J [Plasma Science and Fusion Center, MIT, Cambridge, MA (United States)

2004-05-01

In the Alcator C-Mod tokamak, a high-resolution heterodyne ECE radiometer has been used to measure the electron temperature in plasma discharges with internal transport barriers (ITBs). ITBs are formed by the application of off-axis (r/a {approx} 0.5) ICRF power. Strong density peaking indicates the formation of the ITB. When the ITB is formed, the ECE radiometer detects a small amplitude mode localized near the magnetic axis. Surprisingly, as this mode amplitude grows a dip in the temperature profile is clearly observed at the same location. If sawteeth are present, the mode amplitude appears to be suppressed by the sawtooth crash and no dip in the temperate profiles is observed. TORAY, a ray-tracing code, has been used to investigate the possible refractive effects of the steep density gradients in the ITB and its effects on the ECE observations. The results show that refractive effects can explain the observed local changes in temperature. Ray-tracing also indicates that the observed modes are density fluctuations. Observations of broadband density fluctuations during 4.5 T ITBs are also described.

MOD silver metallization for photovoltaics

Science.gov (United States)

Vest, G. M.; Vest, R. W.

1984-01-01

The development of flat plate solar arrays is reported. Photovoltaic cells require back side metallization and a collector grid system on the front surface. Metallo-organic decomposition (MOD) silver films can eliminate most of the present problems with silver conductors. The objectives are to: (1) identify and characterize suitable MO compounds; (2) develop generic synthesis procedures for the MO compounds; (3) develop generic fabrication procedures to screen printable MOD silver inks; (4) optimize processing conditions to produce grid patterns and photovoltaic cells; and (5) develop a model which describes the adhesion between the fired silver film and the silicon surface.

Perspectives for food research and European collaboration in the European Research Area and the new Framework Programme.

Science.gov (United States)

Breslin, L

2001-08-01

Since 1987, successive framework programmes have contributed to strengthen European food research through the establishment of networks between research institutions, universities and companies from various European countries. In the FAIR programme (1994-1998), 118 research projects comprising nearly 1,000 participants from the European Union and Associated States have been supported in the food area with a European funding of about [symbol: see text] 108 million. Within the Quality of Life and Management of Living Resources programme (1998-2002), food research is mostly supported within the key action 'food, nutrition and health' with a budget of [symbol: see text] 290 million. After the first four deadlines, 735 eligible research proposals have already been received. Further to their evaluation by a panel of independent experts, 108 proposals have been funded or selected for funding representing a total contribution of about [symbol: see text] 168 million. Among those, several clusters of projects are now running on important topics such as probiotics, coeliac diseases, mycotoxins, GMO, safety and food for the elderly. In addition, technology stimulation measures are largely benefiting SMEs to foster their innovation potential. In January 2000, the European Commission adopted a Communication entitled "Towards the European Research Area (ERA)" with the objective to contribute to developing better framework conditions for research in Europe. On 21 February 2001, the Commission adopted proposals to be submitted to the European Parliament and Council for the next framework programme for research and innovation (2002-2006). The new framework programme that is becoming one of the financial instruments of the ERA aims at catalysing the integration of European research by: strengthening of links between the Community research effort and national and regional research policies; concentrating on a limited number of priority fields or research to which activities at the

NetMOD Version 2.0 Parameters

Energy Technology Data Exchange (ETDEWEB)

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

2015-08-01

NetMOD ( Net work M onitoring for O ptimal D etection) is a Java-based software package for conducting simulation of seismic, hydroacoustic and infrasonic networks. Network simulations have long been used to study network resilience to station outages and to determine where additional stations are needed to reduce monitoring thresholds. NetMOD makes use of geophysical models to determine the source characteristics, signal attenuation along the path between the source and station, and the performance and noise properties of the station. These geophysical models are combined to simulate the relative amplitudes of signal and noise that are observed at each of the stations. From these signal-to-noise ratios (SNR), the probability of detection can be computed given a detection threshold. This document describes the parameters that are used to configure the NetMOD tool and the input and output parameters that make up the simulation definitions.

Biomass programme: Overview of the 2006 Swiss research programme; Programm Biomasse. Ueberblicksbericht zum Forschungsprogramm 2006

Energy Technology Data Exchange (ETDEWEB)

Binggeli, D.; Guggisberg, B.

2007-07-01

This report for the Swiss Federal Office of Energy (SFOE) reviews work done within the framework of the Swiss biomass research programme in 2006. The programme concentrates on the efficient conversion of biomass into heat, electrical power and motor fuels. Projects concerned with the optimisation of processes are reported on, including low-particle-emission systems, control systems for bivalent heating installations, use of demanding biomass fuels, combined pellets and solar heating systems and the elimination of ammonia emissions. In the material flow area, measurement campaigns, organic pollutants in compost, the effects of fermented wastes in agriculture and methane losses in biogas conditioning are reported on. New conversion technologies are reviewed, including hydro-thermal gasification, plant-oil fuelled combined heat and power units, flameless burners and catalytic direct liquefaction. In the area of basics, studies and concepts, eco-balances and life-cycle analyses are reported on; the production of synthetic natural gas and the influence of combustion particles are discussed and decentralised power generation from solid biomass is reported on. National and international co-operation is reviewed. The report is concluded with a review of eight pilot and demonstration projects, a review of work to be done in 2007 and a list of research and demonstration projects.

Experimental Study of Reversed Shear Alfven Eigenmodes During The Current Ramp In The Alcator C-Mod Tokamak

International Nuclear Information System (INIS)

Edlund, E.M.; Porkolab, M.; Kramer, G.J.; Lin, L.; Lin, Y.; Tsuji, N.; Wukitch, S.J.

2010-01-01

Experiments conducted in the Alcator C-Mod tokamak at MIT have explored the physics of reversed shear Alfven eigenmodes (RSAEs) during the current ramp. The frequency evolution of the RSAEs throughout the current ramp provides a constraint on the evolution of q min , a result which is important in transport modeling and for comparison with other diagnostics which directly measure the magnetic field line structure. Additionally, a scaling of the RSAE minimum frequency with the sound speed is used to derive a measure of the adiabatic index, a measure of the plasma compressibility. This scaling bounds the adiabatic index at 1.40 ± 0.15 used in MHD models and supports the kinetic calculation of separate electron and ion compressibilities with an ion adiabatic index close to 7/4.

A New Approach to Evaluate MODIS Annual NPP Product (MOD17A3) Using Forest Field Data from Turkey

Energy Technology Data Exchange (ETDEWEB)

Gulbeyaz, Onder; Bond-Lamberty, Benjamin; Akyurek, Zuhal; West, Tristram O.

2018-04-18

In this study we present the first evaluation of the MODIS (MODerate resolution Imaging Spectroradiometer) annual Net Primary Product (NPP) for Turkey's forest ecosystems using field measurements. Due to lack of country scale field measurements (i.e. flux tower for forest ecosystems), tree DBH (Diameter at Breast Height) dataset provided by Ministry of Forest and Water Affair (MFWA) of Turkey is used to calculate NPP of Turkey’s forest ecosystems. The lack of a reliable NPP dataset leads the researchers to use global NPP models such as MODIS annual NPP product. The MODIS MOD17A3 product of vegetation net primary production (NPP) is one of the most highly used data sources for studies of global carbon 25 cycle. However, it is still necessary to test its predictions in multiple biomes, especially for heterogeneous areas in terms of its accuracy and potential bias. Here, we studied a new approach to evaluate coarse scale NPP estimates from the MODIS NPP- MOD17A3 data product, using 2008-2013 field measurements of tree growth throughout Turkey. There different methods were used to calculate field NPP, including standardized growth coefficients (MC), growth coefficients from North America (JC) and annual expected increment (AEI). The average NPP values for all the country is calculated as 2.06 kgC m-2(5years)-1 (0.412 kgC m-2 year-1) (SD = 1.15 kgC m-2 (5years)-1) from MOD17A3, 0.90 kgC m-2(5years)-1 (0.18 kgC m-2 year-1) (SD = 0.57 kgC m-2(5years)-1) with MC, 0.63 kgC m-2(5years)-1 (0.126 kgC m-2 year-1) (SD = 0.37 kgC m-2(5years)-1) with JC and 0.58 kgC m-2 year-1 (SD = 0.29 kgC m-2(5years)-1) with AEI for the studied plots. We found that the MODIS NPP product has a clear relation with both the NPP estimates obtained by using MC (R36 2 = 0.34, RMSE=1.51 kgC m-2(5years)-1) and JC (R37 2 = 0.32, RMSE = 1.73 kgC m-2(5years)-1). In addition to that, the relation between MOD17A3 product and AEI-derived NPP is relatively strong (R39 2 = 0.48, RMSE = 0.26 kgC m-2 year

RELAP5/MOD3 code coupling model

International Nuclear Information System (INIS)

Martin, R.P.; Johnsen, G.W.

1994-01-01

A new capability has been incorporated into RELAP5/MOD3 that enables the coupling of RELAP5/MOD3 to other computer codes. The new capability has been designed to support analysis of the new advanced reactor concepts. Its user features rely solely on new RELAP5 open-quotes styledclose quotes input and the Parallel Virtual Machine (PVM) software, which facilitates process management and distributed communication of multiprocess problems. RELAP5/MOD3 manages the input processing, communication instruction, process synchronization, and its own send and receive data processing. The flexible capability requires that an explicit coupling be established, which updates boundary conditions at discrete time intervals. Two test cases are presented that demonstrate the functionality, applicability, and issues involving use of this capability

Numerical investigation of edge plasma phenomena in an enhanced D-alpha discharge at Alcator C-Mod: Parallel heat flux and quasi-coherent edge oscillations

International Nuclear Information System (INIS)

Russell, D. A.; D’Ippolito, D. A.; Myra, J. R.; LaBombard, B.; Terry, J. L.; Zweben, S. J.

2012-01-01

Reduced-model scrape-off layer turbulence (SOLT) simulations of an enhanced D-alpha (EDA) H-mode shot observed in the Alcator C-Mod tokamak were conducted to compare with observed variations in the scrape-off-layer (SOL) width of the parallel heat flux profile. In particular, the role of the competition between sheath- and conduction-limited parallel heat fluxes in determining that width was studied for the turbulent SOL plasma that emerged from the simulations. The SOL width decreases with increasing input power and with increasing separatrix temperature in both the experiment and the simulation, consistent with the strong temperature dependence of the parallel heat flux in balance with the perpendicular transport by turbulence and blobs. The particularly strong temperature dependence observed in the case analyzed is attributed to the fact that these simulations produce SOL plasmas which are in the conduction-limited regime for the parallel heat flux. A persistent quasi-coherent (QC) mode dominates the SOLT simulations and bears considerable resemblance to the QC mode observed in C-Mod EDA operation. The SOLT QC mode consists of nonlinearly saturated wave-fronts located just inside the separatrix that are convected poloidally by the mean flow, continuously transporting particles and energy and intermittently emitting blobs into the SOL.

The Research Contract Programme annual report and statistics for 2000

International Nuclear Information System (INIS)

2001-06-01

53 Coordinated Research Projects (CRPs) were completed in 2000. 38 of these CRPs concerned topics in Nuclear Sciences and Applications and 15 were related to nuclear energy and safety. These CRPs were funded for $9,275,648; the average annual cost per CRP was $38,892. A list of these CRPs is included. Evaluations of these CRPs will be completed by the end of 2001 and included in the next annual report. The Agency's unique position as a technical international organization has enabled it to act as an international platform to lead groups of nuclear scientists by co-ordinating research and developmental activities addressing important problems in Member States. CRPs have been used to transfer existing technologies to developing countries, as well as for the development of new technologies in those countries. Since CRPs are tailored to finding solutions to specific problems, as compared to general techniques, their potential value in terms of the effect on Member States' level of development is substantial. In an effort to further enhance the effectiveness of CRPs developed and coordinated by the Agency, various initiatives have been suggested and the Research Contract Programme has been the subject of several advisory fora. The PPAS of Major Programme 2, the Senior Evaluation Group (SEG), and an internal audit of the programme have recently made recommendations to this end. Based on these reviews, the Agency has begun to fund fewer, but better focused and more substantially funded CRPs. Whereas in 1999, the Agency was carrying out 159 CRPs, 132 CRPs were carried out in 2000. The average annual amount of funding available per CRP during this period increased by 14%, from US $47,500 in 1999 to US $ 54,000 in 2000. In addition, the introduction of a new type of CRP (called Thematic CRP), meant to complement traditional CRPs, is currently being tested by the Human Health programme. This new, optional type of CRP is designed to strengthen promotion of research on nuclear

The Research Contract Programme annual report and statistics for 2000

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-06-15

53 Coordinated Research Projects (CRPs) were completed in 2000. 38 of these CRPs concerned topics in Nuclear Sciences and Applications and 15 were related to nuclear energy and safety. These CRPs were funded for $9,275,648; the average annual cost per CRP was $38,892. A list of these CRPs is included. Evaluations of these CRPs will be completed by the end of 2001 and included in the next annual report. The Agency's unique position as a technical international organization has enabled it to act as an international platform to lead groups of nuclear scientists by co-ordinating research and developmental activities addressing important problems in Member States. CRPs have been used to transfer existing technologies to developing countries, as well as for the development of new technologies in those countries. Since CRPs are tailored to finding solutions to specific problems, as compared to general techniques, their potential value in terms of the effect on Member States' level of development is substantial. In an effort to further enhance the effectiveness of CRPs developed and coordinated by the Agency, various initiatives have been suggested and the Research Contract Programme has been the subject of several advisory fora. The PPAS of Major Programme 2, the Senior Evaluation Group (SEG), and an internal audit of the programme have recently made recommendations to this end. Based on these reviews, the Agency has begun to fund fewer, but better focused and more substantially funded CRPs. Whereas in 1999, the Agency was carrying out 159 CRPs, 132 CRPs were carried out in 2000. The average annual amount of funding available per CRP during this period increased by 14%, from US $47,500 in 1999 to US $ 54,000 in 2000. In addition, the introduction of a new type of CRP (called Thematic CRP), meant to complement traditional CRPs, is currently being tested by the Human Health programme. This new, optional type of CRP is designed to strengthen promotion of research on nuclear

Radiation protection research and training programme 1990-91 Catalogue of contracts

International Nuclear Information System (INIS)

1991-01-01

This catalogue contains summaries of contacts included in the 1990-91 radiation protection research and training programme, which is divided into three sectors: (a) human exposure to radiation and radioactivity: (i) measurement of radiation dose and its interpretation, (ii) transfer and behaviour of radionuclides in the environment; (b) consequences of radiation exposure to man; their assessment, prevention and treatment: (i) stochastic effects of radiation, (ii) non-stochastic effects of radiation, (iii) radiation effects on the developing organism; (c) risks and management of radiation exposure: (i) assessment of human exposure and risks, (ii) optimization and management of radiation protection

Evaluation of the fusion technology and safety programme of the Joint Research Centre (1980-85)

International Nuclear Information System (INIS)

Haines, M.; Cabibbo, N.; Crocker, J.G.; Lecomte, M.; Merz, E.

1986-01-01

The Joint Research Centre, Ispra, has been involved in fusion research since 1973. In July 1985 the Commission of European Communities - DG XII, following a policy of systematically evaluating its RandD activities, appointed a panel of external experts to evaluate the fusion technology and safety programme carried out at the Joint Research Centre. This report describes the work of the panel in evaluating the research performed by the JRC within the framework of its 1984-87 programme. The achievements of the previous programme, 1980-83, were also taken into consideration. The different research areas covered in the programme, i.e.: reactor studies, breeding blanket technology, structural materials studies, risk assessment and tritium laboratory studies, are described and a draft proposal for the period 1987-90 presented. The evaluation panel has been asked to assess the following aspects: the scientific and technical achievements of the programme, the contribution of the programme to the development of other Community policies, the role played by the JRC in the European fusion research (including NET) and in international collaborations such as INTOR. From its assessment the evaluation panel has made a series of recommendations for the current programme and for future work

Study of volume recombination and radiation opacity effects in Alcator C-Mod

International Nuclear Information System (INIS)

Terry, J.L.; Lipschultz, B.; Pigarov, A.Y.; Boswell, C.; Krasheninnikov, S.I.; LaBombard, B.; Pappas, D.A.

1998-01-01

Observations of significant volume recombination within the Alcator C-Mod divertor plasma and in the edge plasma (MARFE) are described. The recombination occurs in regions where T e approx-lt 1 eV and n e approx-gt 1x10 21 m -3 . The determinations of the recombination rates are made by measuring the D 0 Lyman and/or Balmer spectra and by using a collisional radiative model describing the level populations, ionization and recombination of D 0 . In regions of strong recombination the upper levels (n approx-gt 4) populations are close to those determined by Saha-Boltzmann distribution and are independent of the ground state density. Thus the intensities of lines from these levels are related to the recombination rate, and curves determining the number of open-quote recombinations per photon close-quote are calculated. Ly β line emission is shown to be trapped in some cases, meaning that Ly α can be strongly trapped. Since opacity affects the recombination rates, the effects of the trapping of Ly α,β photons on the open-quote recombinations per photon close-quote curves are calculated and considered in the recombination rate determinations. Total recombination rates in the detached divertor plasma and in MARFEs located at the periphery of the main plasma are determined. Recombination can be a significant sink for ions. copyright 1998 American Institute of Physics

Comparison of measured and modeled gas-puff emissions on Alcator C-Mod

Science.gov (United States)

Baek, Seung-Gyou; Terry, J. L.; Stotler, D. P.; Labombard, B. L.; Brunner, D. F.

2017-10-01

Understanding neutral transport in tokamak boundary plasmas is important because of its possible effects on the pedestal and scrape-off layer (SOL). On Alcator C-Mod, measured neutral line emissions from externally-puffed deuterium and helium gases are compared with the synthetic results of a neutral transport code, DEGAS 2. The injected gas flow rate and the camera response are absolutely calibrated. Time-averaged SOL density and temperature profiles are input to a steady-state simulation. An updated helium atomic model is employed in DEGAS2. Good agreement is found for the D α peak brightness and profile shape. However, the measured helium I line brightness is found to be lower than that in the simulation results by a roughly a factor of three over a wide range of density particularly in the far SOL region. Two possible causes for this discrepancy are reviewed. First, local cooling due to gas puff may suppress the line emission. Second, time-dependent turbulence effect may impact the helium neutral transport. Unlike deuterium atoms that gain energy from charge exchange and dissociation processes, helium neutrals remain cold and have a relatively short mean free path, known to make them prone to turbulence based on the Kubo number criterion. Supported by USDoE awards: DE-FC02-99ER54512, DE-SC0014251, and DE-AC02-09CH11466.

National Nuclear Power Plant Safety Research 2003-2006. Proposal for the Content and Organisation of a New Research Programme

International Nuclear Information System (INIS)

2002-11-01

A country utilising nuclear energy is presumed to possess a sufficient infrastructure to cover the education and research in this field, besides the operating and supervisory organisations of the plants. The starting point of public nuclear safety research programmes is that they provide the necessary conditions for retaining the knowledge needed for ensuring the continuance of safe and economic use of nuclear power, for development of new know-how and for participation in international cooperation. In fact, the Finnish organisations engaged in research in this sector have been an important resource which the various ministries, the Radiation and Nuclear Safety Authority (STUK) and the power companies have had at their disposal. The Steering Group to the Finnish Research Programme on Nuclear Power Plant Safety (FINNUS), which was launched upon the assignment of the Advisory Committee on Nuclear Energy, appointed in spring 2002 a group to plan the contents of the new programme. This report contains a proposal for the general outline of the programme, preliminarily entitled as SAFIR (SAfety of Nuclear Power Plants - Finnish National Research Programme). The plan has been made for the period 2003-2006, but it is based on safety challenges identified for a longer time span as well. The favourable decision-in-principle on a new nuclear power plant unit adopted by Parliament has also been taken into account in the plan. The safety challenges set by the existing plants and the new plant unit, as well as the ensuing research needs do, however, converge to a great extent. The construction of the new power plant unit will increase the need for experts in the field in Finland. At the same time, the retirement of the existing experts is continuing. These factors together will call for more education and training, in which active research activities play a key role. This situation also makes long-term safety research face a great challenge. The general plan aims to define the

WHO/IAEA joint research programme on trace elements in cardiovascular diseases

International Nuclear Information System (INIS)

1980-03-01

After several years of support by WHO and IAEA for the joint research programme on trace elements in cardiovascular diseases, a consultants' meeting was held (1) to examine the present status of the programme with a view to advising on actions necessary for its completion, and (2) to advise on the form, content and timing of a final report. The meeting was attended by the invited experts and other persons. The main work of this research programme is divided, as before, between two projects, (1) on Cd, Cr, Cu, Se, Zn and other elements in relation to ischaemic heart disease, and (2) on Cd, Se and Zn in relation to arterial hypertension

VARSKIN MOD 2 and SADDE MOD2: Computer codes for assessing skin dose from skin contamination

International Nuclear Information System (INIS)

Durham, J.S.

1992-12-01

The computer code VARSKIN has been modified to calculate dose to skin from three-dimensional sources, sources separated from the skin by layers of protective clothing, and gamma dose from certain radionuclides correction for backscatter has also been incorporated for certain geometries. This document describes the new code, VARSKIN Mod 2, including installation and operation instructions, provides detailed descriptions of the models used, and suggests methods for avoiding misuse of the code. The input data file for VARSKIN Mod 2 has been modified to reflect current physical data, to include the contribution to dose from internal conversion and Auger electrons, and to reflect a correction for low-energy electrons. In addition, the computer code SADDE: Scaled Absorbed Dose Distribution Evaluator has been modified to allow the generation of scaled absorbed dose distributions for mixtures of radionuclides and intereat conversion and Auger electrons. This new code, SADDE Mod 2, is also described in this document. Instructions for installation and operation of the code and detailed descriptions of the models used in the code are provided

Properties of the periplasmic ModA molybdate-binding protein of Escherichia coli.

Science.gov (United States)

Rech, S; Wolin, C; Gunsalus, R P

1996-02-02

The modABCD operon, located at 17 min on the Escherichia coli chromosome, encodes the protein components of a high affinity molybdate uptake system. Sequence analysis of the modA gene (GenBank L34009) predicts that it encodes a periplasmic binding protein based on the presence of a leader-like sequence at its N terminus. To examine the properties of the ModA protein, the modA structural gene was overexpressed, and its product was purified. The ModA protein was localized to the periplasmic space of the cell, and it was released following a gentle osmotic shock. The N-terminal sequence of ModA confirmed that a leader region of 24 amino acids was removed upon export from the cell. The apparent size of ModA is 31.6 kDa as determined by gel sieve chromatography, whereas it is 22.5 kDa when examined by SDS-polyacrylamide gel electrophoresis. A ligand-dependent protein mobility shift assay was devised using a native polyacrylamide gel electrophoresis protocol to examine binding of molybdate and other anions to the ModA periplasmic protein. Whereas molybdate and tungstate were bound with high affinity (approximately 5 microM), sulfate, chromate, selenate, phosphate, and chlorate did not bind even when tested at 2 mM. A UV spectral assay revealed apparent Kd values of binding for molybdate and tungstate of 3 and 7 microM, respectively. Strains defective in the modA gene were unable to transport molybdate unless high levels of the anion were supplied in the medium. Therefore the modA gene product is essential for high affinity molybdate uptake by the cell. Tungstate interference of molybdate acquisition by the cell is apparently due in part to the high affinity of the ModA protein for this anion.

Radiation research: the European programme

International Nuclear Information System (INIS)

Gerber, G.B.

1985-01-01

A summary is given of an oral presentation on the European Community's Radiation Protection Programme. Aspects of the programme discussed included its development which began 25 years ago, the administrative structure, the financial success and the funding for 1985/89. Finally, the six subject sectors of the programme were discussed, giving a broad description of where the emphases had been laid and how each sector had fared. (U.K.)

Implementation of the thermal-hydraulic transient analysis code RELAP4/MOD5 and MOD6 on the FACOM 230/75 computer system

International Nuclear Information System (INIS)

Kohsaka, Atsuo; Ishigai, Takahiro; Kumakura, Toshimasa; Naraoka, Ken-itsu

1979-03-01

Development efforts have continued on the extensively used LOCA analysis code RELAP-4, as seen in its history; that is, from the prototype version MOD2 to the latest one MOD6 which is capable of one-through calculations from blowdown to reflood phase of PWR-LOCA. Many improvements and refinements of the models have enlarged the scopes and extents of phenomena to treat. Correspondingly the size of program has increased version to version, and special programming techniques have continuously been introduced to manage the program within limited capacity of core memory. For example, the Dynamic Storage Allocation of MOD5 and the PRELOAD Preprocessor newly incorporated in MOD6 are those designed for the CDC computer with relatively small core size. Described are these programming techniques in detail and experiences on implementation of the codes on FACOM 230/75, together with some results of confirmatory calculations. (author)

AECL research programmes in materials science

International Nuclear Information System (INIS)

Cox, B.; Eastwood, T.A.; Mitchell, I.V.; Dutton, R.

1980-10-01

The high capacity factors achieved by CANDU nuclear power reactors can be attributed in part to the careful attention which has been paid in the concept and design phases to the selection of materials. Improved tolerance of these materials to the hostile conditions of a reactor core depends upon our understanding of such phenomena as radiation damage, corrosion and cracking. This report is an introduction to some of the fundamental and underlying research programmes that have evolved at the AECL laboratories in response to this need. The interactions of energetic atomic particles with solids on a microscopic scale are considered, first under the general heading of radiation effects, followed by sections on energy loss processes, ion channeling, and crystal lattice defects. The latter section leads into the important programmes on deformation processes (creep and growth) in zirconium. The final section discusses the extensive work on the oxidation and environmental cracking of zirconium alloys. (auth)

Experimental Assessment of Battery Cycle Life Within the SIMSTOCK Research Program Évaluation expérimentale de la durée de vie de la batterie dans le programme de recherche SIMSTOCK

Directory of Open Access Journals (Sweden)

Gyan P.

2013-05-01

éhicules électrifiés, hybrides et électriques. L’affaiblissement de la capacité et l’augmentation de la résistance interne due au vieillissement affecteront directement l’autonomie du véhicule et ses performances. Par conséquent, la prévision du vieillissement des ESS reste un domaine important de recherche. Atteindre cet objectif implique des recherches fondamentales sur les matériaux, l’expérimentation, la simulation et la conception. Ce papier décrit les principaux résultats du programme de recherche collaboratif SIMSTOCK qui s’est déroulé pendant 3,5 années avec un budget de 4,2 M € et qui s’est terminé à l’automne 2011. Ce programme a impliqué 15 partenaires parmi lesquels, des laboratoires de recherche, des fabricants d’ESS, des fournisseurs de composants de véhicules et des constructeurs automobiles et il a bénéficié du soutien de l’ADEME. Cet article se concentre principalement sur la modélisation et la simulation d’une cellule lithium-ion haute puissance testée dans ce programme. En premier lieu, est décrit l’élaboration d’un modèle numérique de circuit électrique équivalent de la batterie, associé à un outil de calibration et à sa validation expérimentale. En second, sont présentées la construction d’un plan d’expériences, son utilisation et sa validation, pour la définition des expressions mathématiques représentant les évolutions des paramètres du modèle de batterie en fonction du vieillissement de la batterie. Ensuite le papier détaille la méthode mathématique créée dans le but de prendre en compte le cycle et les effets calendaires sur les caractéristiques de la batterie lors des expériences sur bancs. Enfin, le modèle de batterie est intégré dans un modèle complet du véhicule hybride dans la plateforme de simulation Imagine Lab AMESim, afin de déterminer, avec des conditions de conduite réalistes, l’impact du vieillissement de la batterie sur la performance du véhicule et

Integrated numerical design of an innovative Lower Hybrid launcher for Alcator C-Mod

International Nuclear Information System (INIS)

Meneghini, O.; Shiraiwa, S.; Beck, W.; Irby, J.; Koert, P.; Parker, R. R.; Viera, R.; Wukitch, S.; Wilson, J.

2009-01-01

The new Alcator C-Mod LHCD system (LH2) is based on the concept of a four way splitter [1] which evenly splits the RF power among the four waveguides that compose one of the 16 columns of the LH grill. In this work several simulation tools have been used to study the LH2 coupling performance and the launched spectra when facing a plasma, numerically verifying the effectiveness of the four way splitter concept and further improving its design. The TOPLHA code has been used for modeling reflections at the antenna/plasma interface. TOPLHA results have been then coupled to the commercial code CST Microwave Studio to efficiently optimize the four way splitter geometry for several plasma scenarios. Subsequently, the COMSOL Multiphysics code has been used to self consistently take into account the electromagnetic-thermal-structural interactions. This comprehensive and predictive analysis has proven to be very valuable for understanding the behavior of the system when facing the plasma and has profoundly influenced several design choices of the LH2. According to the simulations, the final design ensures even poloidal power splitting for a wide range of plasma parameters, which ultimately results in an improvement of the wave coupling and an increased maximum operating power.

An experimental assessment of methods used to compute secondary electron emission yield for tungsten and molybdenum electrodes based on exposure to Alcator C-Mod scrape-off layer plasmas

Science.gov (United States)

McCarthy, W.; LaBombard, B.; Brunner, D.; Kuang, A. Q.

2018-03-01

Plasma potentials computed from Langmuir probe data rely on a method to account for secondary electron emission (SEE) from the electrodes. However, significant variations exist among published models for SEE and the reported experimental parameters used to evaluate them. As a means to critically assess SEE computation methods, two of four tungsten electrodes on a Langmuir-Mach probe head were replaced with molybdenum and exposed to Alcator C-Mod boundary plasmas where electron temperatures exceed 50 eV and SEE becomes significant. In this situation, plasma potentials computed for either material should be identical—the SEE evaluation method should properly account for the differences in SEE yields. Of the six methods used to compute SEE, two are found to produce consistent results (Sternglass model with Bronstein experimental parameters and Young-Dekker model with Bronstein experimental parameters). In contrast, the method previously used for C-Mod data analysis (Sternglass model with Kollath parameters) was found to be inconsistent. We have since adopted Young-Dekker-Bronstein as the preferred method.

Lithium pellet injection experiments on the Alcator C-Mod tokamak

Energy Technology Data Exchange (ETDEWEB)

Garnier, Darren Thomas [Univ. of California, Berkeley, CA (United States)

1996-06-01

A pellet enhanced performance mode, showing significantly reduced core transport, is regularly obtained after the injection of deeply penetrating lithium pellets into Alcator C-Mod discharges. These transient modes, which typically persist about two energy confinement times, are characterized by a steep pressure gradient (ℓ_p ℓ a/5) in the inner third of the plasma, indicating the presence of an internal transport barrier. Inside this barrier, particle and energy diffusivities are greatly reduced, with ion thermal diffusivity dropping to near neoclassical values. Meanwhile, the global energy confinement time shows a 30% improvement over ITER89-P L-mode scaling. The addition of ICRF auxiliary heating shortly after the pellet injection leads to high fusion reactivity with neutron rates enhanced by an order of magnitude over L-mode discharges with similar input powers. A diagnostic system for measuring equilibrium current density profiles of tokamak plasmas, employing high speed lithium pellets, is also presented. Because ions are confined to move along field lines, imaging the Li⁺ emission from the toroidally extended pellet ablation cloud gives the direction of the magnetic field. To convert from temporal to radial measurements, the 3-D trajectory of the pellet is determined using a stereoscopic tracking system. These measurements, along with external magnetic measurements, are used to solve the Grad-Shafranov equation for the magnetic equilibrium of the plasma. This diagnostic is used to determine the current density profile of PEP modes by injection of a second pellet during the period of good confinement. This measurement indicates that a region of reversed magnetic shear exists at the plasma core. This current density profile is consistent with TRANSP calculations for the bootstrap current created by the pressure gradient. MHD stability analysis indicates that these plasmas are near the n = ∞ and the n = 1 marginal stability limits.

Lithium pellet injection experiments on the Alcator C-Mod tokamak

International Nuclear Information System (INIS)

Garnier, D.T.

1996-06-01

A pellet enhanced performance mode, showing significantly reduced core transport, is regularly obtained after the injection of deeply penetrating lithium pellets into Alcator C-Mod discharges. These transient modes, which typically persist about two energy confinement times, are characterized by a steep pressure gradient (ell p ≤ a/5) in the inner third of the plasma, indicating the presence of an internal transport barrier. Inside this barrier, particle and energy diffusivities are greatly reduced, with ion thermal diffusivity dropping to near neoclassical values. Meanwhile, the global energy confinement time shows a 30% improvement over ITER89-P L-mode scaling. The addition of ICRF auxiliary heating shortly after the pellet injection leads to high fusion reactivity with neutron rates enhanced by an order of magnitude over L-mode discharges with similar input powers. A diagnostic system for measuring equilibrium current density profiles of tokamak plasmas, employing high speed lithium pellets, is also presented. Because ions are confined to move along field lines, imaging the Li + emission from the toroidally extended pellet ablation cloud gives the direction of the magnetic field. To convert from temporal to radial measurements, the 3-D trajectory of the pellet is determined using a stereoscopic tracking system. These measurements, along with external magnetic measurements, are used to solve the Grad-Shafranov equation for the magnetic equilibrium of the plasma. This diagnostic is used to determine the current density profile of PEP modes by injection of a second pellet during the period of good confinement. This measurement indicates that a region of reversed magnetic shear exists at the plasma core. This current density profile is consistent with TRANSP calculations for the bootstrap current created by the pressure gradient. MHD stability analysis indicates that these plasmas are near the n = ∞ and the n = 1 marginal stability limits

A component of the Indian Climate Research Programme (ICRP)

Indian Academy of Sciences (India)

The Indian Climate Research Programme (ICRP) focuses on the study of climate variability and its impact on agriculture. To address the role of the Bay of Bengal in monsoon variability, a process study was organised during July-August 1999, deploying research ships, buoys, INSAT, coastal radar and conventional ...

The Nirex safety assessment research programme: annual report for 1985/86

International Nuclear Information System (INIS)

Hodgkinson, D.P.; Cooper, M.J.; Atkinson, A.

1987-01-01

The report describes progress of the Nirex Safety Assessment Research Programme in 1985/86. In addition, some background information is given on the overall programme and on the individual research projects, and likely future work is outlined. Research into the disposal of low-level waste (LLW) and intermediate-level waste (ILW) into underground repositories and onto the sea bed is reported. A large part of the programme is concerned with the effectiveness of near-field barriers to water-borne leakage of radionuclides from cementitious repositories. Considerable progress has been made with quantifying the longevity of steel containers and concrete structures, and the effectiveness of chemical constraints in limiting near-field concentrations. A range of techniques for measuring and modelling far-field phenomena has been developed and tested. Some initial studies have been performed to assess the durability of sea disposal packages and the behaviour of polythene in sea water. (author)

Applications of field-programmable gate arrays in scientific research

CERN Document Server

Sadrozinski, Hartmut F W

2011-01-01

Focusing on resource awareness in field-programmable gate array (FPGA) design, Applications of Field-Programmable Gate Arrays in Scientific Research covers the principle of FPGAs and their functionality. It explores a host of applications, ranging from small one-chip laboratory systems to large-scale applications in ""big science."" The book first describes various FPGA resources, including logic elements, RAM, multipliers, microprocessors, and content-addressable memory. It then presents principles and methods for controlling resources, such as process sequencing, location constraints, and in

Inr training programme in nuclear research

International Nuclear Information System (INIS)

Cretu, I.; Ionila, M.; Gyongyosi, E.; Dragan, E.; Petra, M.

2013-01-01

The field of scientific research goes through rapid changes to which organizations must dinamically and efficiently adapt, which leads to the need to develop a continuous learning process that should be the basis for a long-term operational performance. Thus, human resource management systems and continuous learning should be perfectly correlated/alligned with the organizational strategy and knowledge. The research institutes through the nature of their activity are constantly undergoing a transformation process by exploring new research areas which presumes ensuring competent human resources who have to continuously learn and improve. The «learning organization » concept represents a metaphor rooted in the search of a strategy for promoting the personal development of the individual within an organization through a continuous transformation. Learning is associated with the idea of continuous transformation based on the individual and organizational development. Within « learning organizations » the human development strategy occupies a central role in management strategies. It was learned that organizations which perform excellently depend on the employees committment, especially in the budget constraints environment. For this, the human resources have to be used at maximum capacity but this is possible only with an increased committment of the employee towards the organization. The purpose of this paper is to present the basic training programme for the new employees which is part of the training strategy which carry out activities in the nuclear field of SCN Pitesti. With the majority of the research personnel aged between 45 and 60 years old there is the risk of loosing the knowledge gained in this domain. The expertise gained by experienced experts in the institute nationally and internationally can be exploited through the knowledge transfer to the new employees by organizing training programmes. The knowledge transfer between generations is one of the

LIEKKI 2 - Annual Review 1996. Gasification Research Programme; LIEKKI 2 - Vuosikirja 1996. Seurantaryhmaeraportit

Energy Technology Data Exchange (ETDEWEB)

Hupa, M; Matinlinna, J [eds.

1996-12-01

The LIEKKI 2 program is planned to cover the research work to be performed in the period beginning in 1993 and ending in 1998. LIEKKI 2 is largely a continuation of the combustion and gasification research earlier included in the national research programmes LIEKKI and JALO. The research within the scope of the LIEKKI 2 research programme is aimed at supporting the development of energy conversion techniques relating to combustion and gasification in Finland. Research serving the development of new, more efficient and environmentally sound techniques will receive special attention, but research developing conventional combustion techniques is also to be included in the programme. Another important objective of the programme is to maintain and develop the competence of different research groups in this field of technology on a long term basis. The main research areas are: (1) modelling of the furnace processes, (2) the chemistry of gaseous emission components, (3) ash, aerosols and the behaviour of particles, (4) new combustion and gasification technologies, (5) black liquor, (6) conventional combustion technologies and waste incineration. This part of the book contains the reports of the review group chairmen for 1995 and the entire text of the LIEKKI 2 Board of Directors internal evaluation report. (author)

SIHTI 2 - Energy and environmental technology. Yearbook 1993 of the research programme. Project reports

International Nuclear Information System (INIS)

Korhonen, M.; Saviharju, K.

1994-01-01

The SIHTI 2 research programme on energy and environmental technology, established by the Finnish Ministry of Trade and Industry, is concentrating on areas of environmental technology that are vital to Finland or in which Finns can engage in pioneering research. The promotion of product development within the environmental technology industry produces solutions for reducing the emissions of the energy sector. It is also a way of boosting Finland's share of the world market for such technology. The objectives of the programme are to cut down harmful emissions, recycle raw materials, reduce the amount of byproducts and wastes and achieve a greater utilization of wastes. In addition, an objective is to create basic information about the effects of environmental protection technology for the other research programmes financed by the Ministry of Trade and Industry. The development of internationally comparable research, monitoring and measurement methods creates a basis for wide-ranging international cooperation. The programme, to be carried out in 1993 - 1998, is in part a continuation of the previous SIHTI programme. New areas of research are environmental problems connected with energy in the forest and base metal industries as well as the systematic development of life-cycle analyses. This publication is yearbook 1993 of the programme. It contains the project reports of the research and joint development projects and information about the participating institutions

NetMOD Version 2.0 Mathematical Framework

Energy Technology Data Exchange (ETDEWEB)

Merchant, Bion J. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Young, Christopher J. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Chael, Eric P. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2015-08-01

NetMOD ( Net work M onitoring for O ptimal D etection) is a Java-based software package for conducting simulation of seismic, hydroacoustic and infrasonic networks. Network simulations have long been used to study network resilience to station outages and to determine where additional stations are needed to reduce monitoring thresholds. NetMOD makes use of geophysical models to determine the source characteristics, signal attenuation along the path between the source and station, and the performance and noise properties of the station. These geophysical models are combined to simulate the relative amplitudes of signal and noise that are observed at each of the stations. From these signal-to-noise ratios (SNR), the probabilities of signal detection at each station and event detection across the network of stations can be computed given a detection threshold. The purpose of this document is to clearly and comprehensively present the mathematical framework used by NetMOD, the software package developed by Sandia National Laboratories to assess the monitoring capability of ground-based sensor networks. Many of the NetMOD equations used for simulations are inherited from the NetSim network capability assessment package developed in the late 1980s by SAIC (Sereno et al., 1990).

Researching the Impact of Teacher Professional Development Programmes Based on Action Research, Constructivism, and Systems Theory

Science.gov (United States)

Zehetmeier, Stefan; Andreitz, Irina; Erlacher, Willibald; Rauch, Franz

2015-01-01

This paper deals with the topic of professional development programmes' impact. Concepts and ideas of action research, constructivism, and systems theory are used as a theoretical framework and are combined to describe and analyse an exemplary professional development programme in Austria. Empirical findings from both quantitative and qualitative…

Ten years of IAEA cooperation with the Russian research reactor fuel return programme

Energy Technology Data Exchange (ETDEWEB)

Tozser, S.; Adelfang, P.; Bradley, E. [International Atomic Energy Agency, Vienna (Austria)

2013-01-15

The Russian Research Reactor Fuel Return (RRRFR) Programme was launched in 2001. Over the duration, the programme successfully completed 43 safe shipments of 1.6 tons of fresh and spent HEU fuel from different countries using Russian fuelled research reactors to the country of origin. The IAEA has been a very active supporter of the RRRFR Programme since its inception. Under the auspices of the RRRFR Programme, the Agency has been ensuring a broad range of technical advisory and organizational support to the HEU fuel repatriation, as well as training and advisory assistance for supporting RR conversion from HEU to LEU. The presentation gives an overview of the RRRFR programme achievements with special consideration of the IAEA contribution. These include an overview of the shipments' history in terms of fresh and spent fuel, as well as a summary of experiences gained during the shipments' preparation and termination. The presentation focuses on technical advisory support given by the IAEA during the programme implementation, captures the consolidated knowledge of the unique international programme and shares the most important lessons learned. (orig.)

Survey and evaluation of the external research and development programme 1977-1983 of the Swedish Radiation Protection Institute

International Nuclear Information System (INIS)

Persson, Lars.

1993-01-01

A review of the external research programme of SSI is undertaken. The main research programme is in this report divided into five subprogrammes according to the main programmes of the Institute. This report covers research projects reported 1977-1983. An evaluation of the impact of the R and D programme is included in the report. The external R and D research programme of SSI has had an important impact on the radiation protection work in Sweden. The methods for evaluation of research programmes are also discussed in the report

SOLPS-ITER Study of neutral leakage and drift effects on the alcator C-Mod divertor plasma

Directory of Open Access Journals (Sweden)

W. Dekeyser

2017-08-01

Full Text Available As part of an effort to validate the edge plasma model in the SOLPS-ITER code suite under ITER-relevant divertor plasma and neutral conditions, we report on progress in the modeling of the Alcator C-Mod divertor plasma with the new code. We perform simulations with a complete drifts model and kinetic neutrals, including effects of neutral viscosity, ion-molecule collisions and Lyα-opaque conditions, but assuming a pure deuterium plasma. Through a series of simulations with varying divertor geometries, we show the importance of including neutal leakage paths through the divertor substructure on the divertor plasma solution. Moreover, the impact of drifts on inner-outer target asymmetries is assessed. Including both effects, we achieve excellent agreement between simulations and upstream and outer target Langmuir Probe data. In absence of strong volumetric losses due to e.g. impurity radiation in our simulations, the strong inner target detachment observed experimentally remains elusive in our modeling at present.

Mod 1 ICS TI Report: ICS Conversion of a 140% HPGe Detector

Energy Technology Data Exchange (ETDEWEB)

Bounds, John Alan [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2016-07-05

This report evaluates the Mod 1 ICS, an electrically cooled 140% HPGe detector. It is a custom version of the ORTEC Integrated Cooling System (ICS) modified to make it more practical for us to use in the field. Performance and operating characteristics of the Mod 1 ICS are documented, noting both pros and cons. The Mod 1 ICS is deemed a success. Recommendations for a Mod 2 ICS, a true field prototype, are provided.

Les industries culturelles en mutation : des modèles en question

Directory of Open Access Journals (Sweden)

Lucien Perticoz

2012-09-01

Full Text Available La présente contribution se propose de questionner la notion de modèles socio-économiques dans le cadre des travaux relatifs aux mutations des industries culturelles. À cette fin, l’exposé se déroulera en trois temps : nous reviendrons tout d’abord sur les caractéristiques essentielles des modèles génériques (modèle éditorial et de flot ainsi que sur leurs principaux apports ; nous expliquerons ensuite dans quelle mesure ils doivent être considérés, non comme une description fidèle de la réalité dont ils entendent rendre compte, mais davantage comme des règles du jeu permettant d’appréhender les mutations à l’œuvre ; enfin, à l’aune de la numérisation des contenus et de leur consommation via Internet, nous interrogerons l’hypothèse de l’émergence de nouveaux modèles génériques. En conclusion, nous insisterons sur la nécessité, à notre sens, de prendre en compte l’évolution des pratiques culturelles médiatiques en tant que dimension structurante de ces modèles.This paper aims to question the concept of socio-economic models within the framework of research about cultural industries mutations. For this purpose, our presentation will proceed in three parts : first of all, we will reconsider the essential characteristics of the generic models (publishing model and flow model and their main contributions to the research ; we will explain then why they must be considered, not as a faithful description of the reality of which they intend to give an account, but more like rules of the game allowing to understand the mutations of cultural industries ; finally, considering the digitalization of contents and their consumption using Internet, we will question the hypothesis of the emergence of new generic models. In conclusion, we will insist on the importance, from our opinion, to take into account the evolution of the media cultural practices as a structuring dimension of these models.

Application of non-destructive testing and in-service inspections to research reactors and preparation of ISI programme and manual for WWR-C research reactors

International Nuclear Information System (INIS)

Khattab, M.

1996-01-01

The present report gives a review on the results of application of non-destructive testing and in-service inspections to WWR-C reactors in different countries. The major problems related to reactor safety and the procedure of inspection techniques are investigated to collect the experience gained from this type of reactors. Exchangeable experience in solving common problems in similar reactors play an important role in the effectiveness of their rehabilitation programmes. 9 figs., 4 tabs

Assessment of full power turbine trip start-up test for C. Trillo 1 with RELAP5/MOD2

International Nuclear Information System (INIS)

Lozano, M.F.; Moreno, P.; de la Cal, C.; Larrea, E.; Lopez, A.; Santamaria, J.G.; Lopez, E.; Novo, M.

1993-07-01

C. Trillo I has developed a model of the plant with RELAP5/MOD2/36.04. This model will be validated against a selected set of start-up tests. One of the transients selected to that aim is the turbine trip, which presents very specific characteristics that make it significantly different from the same transient in other PWRs of different design, the main difference being that the reactor is not tripped: a reduction in primary power is carried out instead. Pre-test calculations were done of the Turbine Trip Test and compared against the actual test. Minor problems in the first model, specially in the Control and Limitation Systems, were identified and post-test calculations had been carried out. The results show a good agreement with data for all the compared variables

Presentation of the Nirex disposal safety research programme

International Nuclear Information System (INIS)

1988-01-01

Implementation of Nirex plans for the disposal of solid low and intermediate level radioactive waste deep underground requires assurances of safety at every stage. This includes assessment of long-term safety, which must be based on an understanding of how the repository and its contents will behave far into the future. This understanding is being provided by the company's substantial disposal research and development programme, currently running at a level of more than Pound 5 million annually. The principal contractor for the work is the UKAEA's Harwell Laboratory, with contributions from experts in universities and industry. Information from other national and international programmes also contributes. This document supports a presentation held at the CEGB Conference Centre, Didcot Power Station, Oxfordshire on 1st November 1988 to outline the scope of the work and its objectives in the context of the Company's plans and the requirements of safety assessments. It summarises the results and understanding being obtained from the current programme. (author)

Phebus FP. An international severe accident research programme

International Nuclear Information System (INIS)

Hardt, P.; Tattegrain, A.

1995-01-01

The main hazard during a hypothetical severe nuclear reactor accident resides in its fission product (FP) inventory. For this reason, the behaviour of FPs has been extensively studied, with the aim of determining the potential source to the environment. The Phebus FP programme proposes a novel, integral approach to this research. After 5 years of construction and of analytical preparation the Phebus FP programme has been supplying a large volume of new experimental data. Their processing by code calculations is presently a major challenge to all partners. The intense collaboration of 25 organizations from 15 countries has proven to be a major asset of Phebus FP. (author). 6 refs., 2 figs

RDandD Programme 2010. Programme for research, development and demonstration of methods for the management and disposal of nuclear waste

International Nuclear Information System (INIS)

2010-09-01

The RD and D programme 2010 gives an account of SKB's plans for research, development and demonstration during the period 2011-2016. SKB's activities are divided into two main areas - the programme for Low and Intermediate Level Waste (the Loma program) and the Nuclear Fuel Program. The RD and D Programme 2010 consists of five parts: Part I: Overall Plan, Part II: Loma program, Part III: Nuclear Fuel Program, Part IV: Research on analysis of long-term safety, Part V: Social Science Research. The 2007 RD and D programme was focused primarily on technology development to realize the final repository for spent nuclear fuel. The actions described were aimed at increasing awareness of long-term safety and to obtain technical data for application under the Nuclear Activities Act for the final repository for spent fuel and under the Environmental Code of the repository system. Many important results from these efforts are reported in this program. An overall account of the results will be given in the Licensing application in early 2011. The authorities' review of RD and D programme in 2007 and completion of the program called for clarification of plans and programs for the final repository for short-lived radioactive waste, SFR, and the final repository for waste, SFL. This RD and D program describes these plans in a more detailed way

Microscopic observation drug susceptibility assay (MODS for early diagnosis of tuberculosis in children.

Directory of Open Access Journals (Sweden)

Dang Thi Minh Ha

2009-12-01

Full Text Available MODS is a novel liquid culture based technique that has been shown to be effective and rapid for early diagnosis of tuberculosis (TB. We evaluated the MODS assay for diagnosis of TB in children in Viet Nam. 217 consecutive samples including sputum (n = 132, gastric fluid (n = 50, CSF (n = 32 and pleural fluid (n = 3 collected from 96 children with suspected TB, were tested by smear, MODS and MGIT. When test results were aggregated by patient, the sensitivity and specificity of smear, MGIT and MODS against "clinical diagnosis" (confirmed and probable groups as the gold standard were 28.2% and 100%, 42.3% and 100%, 39.7% and 94.4%, respectively. The sensitivity of MGIT and MODS was not significantly different in this analysis (P = 0.5, but MGIT was more sensitive than MODS when analysed on the sample level using a marginal model (P = 0.03. The median time to detection of MODS and MGIT were 8 days and 13 days, respectively, and the time to detection was significantly shorter for MODS in samples where both tests were positive (P<0.001. An analysis of time-dependent sensitivity showed that the detection rates were significantly higher for MODS than for MGIT by day 7 or day 14 (P<0.001 and P = 0.04, respectively. MODS is a rapid and sensitive alternative method for the isolation of M.tuberculosis from children.

SAFIR. The Finnish research programme on nuclear power plant safety 2003-2006. Executive summary

International Nuclear Information System (INIS)

Puska, E.

2006-12-01

Major part of Finnish public research on nuclear power plant safety during the years 2003-2006 has been carried out in the SAFIR programme. The programme has been administrated by the steering group that was nominated by the Ministry of Trade and Industry (KTM). The steering group of SAFIR has consisted of representatives from Radiation and Nuclear Safety Authority (STUK), Ministry of Trade and Industry (KTM), Technical Research Centre of Finland (VTT), Teollisuuden Voima Oy (TVO), Fortum Power and Heat Oy, Fortum Nuclear Services Oy (Fortum), Finnish Funding Agency for Technology and Innovation (Tekes), Helsinki University of Technology (TKK) and Lappeenranta University of Technology (LTY). The key research areas of SAFIR have been (1) reactor fuel and core, (2) reactor circuit and structural safety, (3) containment and process safety functions, that was divided in 2005 into (3a) thermal hydraulics and (3b) severe accidents, (4) automation, control room and IT, (5) organisations and safety management and (6) risk-informed safety management. The research programme has included annually from 20 up to 24 research projects, whose volume has varied from a few person months to several person years. The total volume of the programme during the four year period 2003-2006 has been 19.7 million euros and 148 person years. The research in the programme has been carried out primarily by Technical Research Centre of Finland (VTT). Other research units responsible for the projects include Lappeenranta University of Technology, Fortum Nuclear Services Oy, Helsinki University of Technology and RAMSE Consulting Oy. In addition, there have been a few minor subcontractors in some projects. The programme management structure has consisted of the steering group, a reference group in each of the seven research areas and a number of ad hoc groups in the various research areas. This report gives a short summary of the results of the SAFIR programme for the period January 2003 - November

Hot particle dose calculations using the computer code VARSKIN Mod 2

International Nuclear Information System (INIS)

Durham, J.S.

1991-01-01

The only calculational model recognised by the Nuclear Regulatory Commission (NRC) for hot particle dosimetry is VARSKIN Mod 1. Because the code was designed to calculate skin dose from distributed skin contamination and not hot particles, it is assumed that the particle has no thickness and, therefore, that no self-absorption occurs within the source material. For low energy beta particles such as those emitted from 60 Co, a significant amount of self-shielding occurs in hot particles and VARSKIN Mod 1 overestimates the skin dose. In addition, the presence of protective clothing, which will reduce the calculated skin dose for both high and low energy beta emitters, is not modelled in VARSKIN Mod 1. Finally, there is no provision in VARSKIN Mod 1 to calculate the gamma contribution to skin dose from radionuclides that emit both beta and gamma radiation. The computer code VARSKIN Mod 1 has been modified to model three-dimensional sources, insertion of layers of protective clothing between the source and skin, and gamma dose from appropriate radionuclides. The new code, VARSKIN Mod 2, is described and the sensitivity of the calculated dose to source geometry, diameter, thickness, density, and protective clothing thickness are discussed. Finally, doses calculated using VARSKIN Mod 2 are compared to doses measured from hot particles found in nuclear power plants. (author)

Teaching Mods with Class

DEFF Research Database (Denmark)

Champion, Erik

2012-01-01

from around the world, representing fields as diverse as architecture, ethnography, puppetry, cultural studies, music education, interaction design and industrial design. How can we design, play with and reflect on the contribution of game mods, related tools and techniques, to both game studies...

C-Vitamin mod åreforkalkning

DEFF Research Database (Denmark)

Frikke-Schmidt, Henriette Rønne; Lykkesfeldt, Jens

2009-01-01

Overraskende mange mennesker i den vestlige verden får ikke C-vitamin nok. Muligvis vil tilskud med C-vitamin kunne forebygge hjertekarsygdomme.......Overraskende mange mennesker i den vestlige verden får ikke C-vitamin nok. Muligvis vil tilskud med C-vitamin kunne forebygge hjertekarsygdomme....

Co-ordinated research programme applications of stable isotope tracers in human nutrition research

International Nuclear Information System (INIS)

1992-01-01

The objective of this Co-ordinated Research Programme is to help establish competence in the use of stable isotope techniques, particularly in developing countries. This report summarizes the discussions that took, place during the Second Research Co-ordination Meeting, held in Bangalore in November 1990. Working papers presented by the participants are included as annexes. Refs, figs and tabs

An assessment of ion temperature measurements in the boundary of the Alcator C-Mod tokamak and implications for ion fluid heat flux limiters

International Nuclear Information System (INIS)

Brunner, D; LaBombard, B; Churchill, R M; Hughes, J; Lipschultz, B; Ochoukov, R; Theiler, C; Walk, J; Rognlien, T D; Umansky, M V; Whyte, D

2013-01-01

The ion temperature is not frequently measured in the boundary of magnetic fusion devices. Comparisons among different ion temperature techniques and simulations are even rarer. Here we present a comparison of ion temperature measurements in the boundary of the Alcator C-Mod tokamak from three different diagnostics: charge exchange recombination spectroscopy (CXRS), an ion sensitive probe (ISP), and a retarding field analyzer (RFA). Comparison between CXRS and the ISP along with close examination of the ISP measurements reveals that the ISP is space charge limited. It is thus unable to measure ion temperature in the high density (>10 19 m −3 ) boundary plasma of C-Mod with its present geometry. Comparison of ion temperatures measured by CXRS and the RFA shows fair agreement. Ion and electron parallel heat flow is analyzed with a simple 1D fluid code. The code takes divertor measurements as input and results are compared to the measured ratios of upstream ion to electron temperature, as inferred respectively by CXRS and a Langmuir probe. The analysis reveals the limits of the fluid model at high Knudsen number. The upstream temperature ratio is under predicted by a factor of 2. Heat flux limiters (kinetic corrections) to the fluid model are necessary to match experimental data. The values required are found to be close to those reported in kinetic simulations. The 1D code is benchmarked against the 2D plasma fluid code UEDGE with good agreement. (paper)

An assessment of ion temperature measurements in the boundary of the Alcator C-Mod tokamak and implications for ion fluid heat flux limiters

Science.gov (United States)

Brunner, D.; LaBombard, B.; Churchill, R. M.; Hughes, J.; Lipschultz, B.; Ochoukov, R.; Rognlien, T. D.; Theiler, C.; Walk, J.; Umansky, M. V.; Whyte, D.

2013-09-01

The ion temperature is not frequently measured in the boundary of magnetic fusion devices. Comparisons among different ion temperature techniques and simulations are even rarer. Here we present a comparison of ion temperature measurements in the boundary of the Alcator C-Mod tokamak from three different diagnostics: charge exchange recombination spectroscopy (CXRS), an ion sensitive probe (ISP), and a retarding field analyzer (RFA). Comparison between CXRS and the ISP along with close examination of the ISP measurements reveals that the ISP is space charge limited. It is thus unable to measure ion temperature in the high density (>1019 m-3) boundary plasma of C-Mod with its present geometry. Comparison of ion temperatures measured by CXRS and the RFA shows fair agreement. Ion and electron parallel heat flow is analyzed with a simple 1D fluid code. The code takes divertor measurements as input and results are compared to the measured ratios of upstream ion to electron temperature, as inferred respectively by CXRS and a Langmuir probe. The analysis reveals the limits of the fluid model at high Knudsen number. The upstream temperature ratio is under predicted by a factor of 2. Heat flux limiters (kinetic corrections) to the fluid model are necessary to match experimental data. The values required are found to be close to those reported in kinetic simulations. The 1D code is benchmarked against the 2D plasma fluid code UEDGE with good agreement.

NDA generic research programme for higher activity waste management issues - 16390

International Nuclear Information System (INIS)

McKinney, James; Brownridge, Melanie

2009-01-01

NDA has a responsibility to ensure decommissioning activities are sufficiently technically underpinned and appropriate Research and Development (Rand D) is carried out. The NDA funds research and development (R and D) indirectly via the Site Licence Companies (SLCs) or directly. The main component of directly funded R and D is the NDA Direct Research Portfolio (DRP). The DRP is split into four framework areas: - University Interactions; - Waste Processing; - Material Characterisation; - Actinide and Strategic Nuclear Materials. These four framework areas were competed through an Official Journal of European Union (OJEU) process in 2008. Although all four areas involve waste management, Waste Processing and Material Characterisation specifically deal with Higher Activity Waste (HAW) waste management issues. The Waste Processing area was awarded to three groups: (i) National Nuclear Laboratory (NNL), (ii) Consortium led by Hyder Consulting Ltd, and (iii) Consortium led by UKAEA Ltd. The Material Characterisation area was awarded to three groups: (i) NNL, (ii) Serco, and (iii) Consortium led by UKAEA Ltd. The initial work in Waste Processing and Material Characterisation was centered on establishing a forward research programme to address the generic needs of the UK civil nuclear industry and the NDA strategic drivers for waste management and land quality. This has been achieved by the four main framework contractors from the Waste Processing and Materials Characterisation areas working together with the NDA to identify the key research themes and begin the development of the NDA's HAW Management Research Programme. The process also involves active engagement with both industry and regulators via the Nuclear Waste Research Forum (NWRF). The NDA's HAW Management Research Programme includes a number of themes: - Optimisation of Interim Store Operation and Design; - Alternative Waste Encapsulants; - Waste Package Integrity; - Alternative Waste treatment methods

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

International Nuclear Information System (INIS)

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

1978-12-01

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

Modèle conceptuel commun pour la supervision des systèmes de sûreté du CERN

CERN Document Server

Hammouti, L

2000-01-01

La supervision des systèmes de sûreté des accélérateurs et des zones expérimentales du CERN est gérée spécifiquement d'une machine à l'autre. Chaque programme a été conçu et réalisé au moyen de la technologie de l'époque et sans suivre un modèle conceptuel commun. La situation actuelle risque de poser des problèmes importants pour l'avenir. En effet la disparité des systèmes de supervision et la nécessité de les faire évoluer ou de les renouveler alourdissent sensiblement la charge de travail ainsi que le coût de la maintenance. D'autre part, il est difficile, voire impossible, de les faire communiquer entre eux, or cela constitue une des requêtes principales de l'opération pour une meilleure coordination de l'exploitation. Le but de ce document consiste à présenter les bases d'un modèle conceptuel unique, en cours d'élaboration dans le cadre du LHC, afin de répondre aux problèmes et aux requêtes posés. Ce modèle servira de référence pour le renouvellement et l'évolution ...

The EURATOM research and training programme in its wider context

International Nuclear Information System (INIS)

Deffrennes, M.

2008-01-01

In this presentation research and training activities of the EURATOM are reviewed. This review consists of the following parts: Setting the scene; EURATOM research framework programme; Sustainable nuclear energy technology platform; Strategic energy technology plan; EURATOM FP and international cooperation.

Evaluation of the applicability of cladding deformation model in RELAP5/MOD3.2 code for VVER-1000 fuel

International Nuclear Information System (INIS)

Vorob'ev, Yu.; Zhabin, O.

2015-01-01

Applicability of cladding deformation model in RELAP5/MOD3.2 code is analyzed for VVER-1000 fuel cladding from Zr+1%Nb alloy. Experimental data and calculation model of fuel assembly channel of the core are used for this purpose. The model applicability is tested for the cladding temperature range from 600 to 1200 deg C and pressure range from 1 to 12 MPa. Evaluation results demonstrate limited applicability of built-in RELAP5/MOD3.2 cladding deformation model to the estimation of Zr+1%Nb cladding rupture conditions. The limitations found shall be considered in application of RELAP5/MOD3.2 cladding deformation model in the design-basis accident analysis of VVER reactors

Méditerranée asiatique : un modèle urbain polycentrique

OpenAIRE

Gipouloux , François

2012-01-01

Publication de la revue "Diplomatie. Affaires stratégiques et relations internationales" http://www.diplomatie-presse.com/; International audience; En Asie orientale, un corridor maritime a pris forme autour de plates-formes logistiques et portuaires, fidèles au modèle de Hong Kong. C'est là que bat le coeur de l'économie régionale.

Radiological protection of service and civilian personnel

International Nuclear Information System (INIS)

1990-01-01

Since the United Kingdom's defence nuclear industry was founded in the late 1940s, Service and civilian personnel have been exposed to ionising radiation. During the last forty years, as knowledge about the effects of radiation exposure has grown, concern to ensure adequate protection against exposure has also increased,. As part of our continuing scrutiny of the Ministry of Defence (MoD), we have undertaken a short inquiry to examine MoD's current and future policy and practice on radiological protection. The principal work involving exposure of Service and civilian personnel to significant levels of radiation falls into two discrete areas: the nuclear weapons programme and the nuclear propulsion programme. The nuclear weapons programme involves research, the production of nuclear warheads and their deployment with Her Majesty's Forces. The nuclear propulsion programme involves research, production, operation, refitting and decommissioning of pressurised water reactors as a source of propulsion power in Royal Navy submarines. These two nuclear programmes are not the only sources of ionising radiation within MoD's responsibility: it also arises from research, non-destructive testing and medical applications, most notably conventional radiography. In this Report we have concentrated upon ionising radiation arising from the two defence nuclear programmes. (author)

NAUA Mod 4

International Nuclear Information System (INIS)

Bunz, H.; Koyro, M.; Schoeck, W.

1983-08-01

This report describes the computer program NAUA Mod4. Its purpose is to calculate the behaviour of a polydisperse aerosol system in a closed vessel containing a condensing atmosphere as a function of the time. The main object is to explain the physical background and to describe the structure of the code and the input and output in detail. (orig.) [de

Building capacity for sustainable research programmes for cancer in Africa.

Science.gov (United States)

Adewole, Isaac; Martin, Damali N; Williams, Makeda J; Adebamowo, Clement; Bhatia, Kishor; Berling, Christine; Casper, Corey; Elshamy, Karima; Elzawawy, Ahmed; Lawlor, Rita T; Legood, Rosa; Mbulaiteye, Sam M; Odedina, Folakemi T; Olopade, Olufunmilayo I; Olopade, Christopher O; Parkin, Donald M; Rebbeck, Timothy R; Ross, Hana; Santini, Luiz A; Torode, Julie; Trimble, Edward L; Wild, Christopher P; Young, Annie M; Kerr, David J

2014-05-01

Cancer research in Africa will have a pivotal role in cancer control planning in this continent. However, environments (such as those in academic or clinical settings) with limited research infrastructure (laboratories, biorespositories, databases) coupled with inadequate funding and other resources have hampered African scientists from carrying out rigorous research. In September 2012, over 100 scientists with expertise in cancer research in Africa met in London to discuss the challenges in performing high-quality research, and to formulate the next steps for building sustainable, comprehensive and multi-disciplinary programmes relevant to Africa. This was the first meeting among five major organizations: the African Organisation for Research and Training in Africa (AORTIC), the Africa Oxford Cancer Foundation (AfrOx), and the National Cancer Institutes (NCI) of Brazil, France and the USA. This article summarizes the discussions and recommendations of this meeting, including the next steps required to create sustainable and impactful research programmes that will enable evidenced-based cancer control approaches and planning at the local, regional and national levels.

Developmental assessment of RELAP5/MOD3 using the semiscale natural circulation tests

International Nuclear Information System (INIS)

Carlson, K.E.

1990-01-01

A code development effort creating RELAP5/MOD3 from RELAP5/MOD2 has been completed. Upon completion, a developmental assessment task was performed. One of the problems used for the developmental assessment was the Semiscale Natural Circulation Test. Calculated results from RELAP5/MOD3 are compared to measured data and previously calculated results from RELAP5/MOD2. 10 refs., 6 figs., 1 tab

Phase 2 of the International Piping Integrity Research Group programme

International Nuclear Information System (INIS)

Darlaston, B.J.

1994-01-01

The results of phase 1 of the International Piping Integrity Research Group (IPIRG-1) programme have been widely reported. The significance of the results is reviewed briefly, in order to put the phase 2 programme into perspective. The success of phase 1 led the participants to consider further development and validation of pipe and pipe component fracture analysis technology as part of another international group programme (IPIRG-2). The benefits of combined funding and of the technical exchanges and interactions are considered to be of significant advantage and value. The phase 2 programme has been designed with the overall objective of developing and experimentally validating methods of predicting the fracture behaviour of nuclear reactor safety-related piping, to both normal operating and accident loads. The programme will add to the engineering estimation analysis methods that have been developed for straight pipes. The pipe system tests will expand the database to include seismic loadings and flaws in fittings, such as bends, elbows and tees, as well as ''short'' cracks. The results will be used to validate further the analytical methods, expand the capability to make fittings and extend the quasi-static results for the USNRC's new programme on short cracks in piping and piping welds. The IPIRG-2 programme is described to provide a clear understanding of the content, strategy, potential benefits and likely significance of the work. ((orig.))

The Nirex Safety Assessment Research Programme; annual report for 1988/89

International Nuclear Information System (INIS)

Cooper, M.J.

1989-07-01

This report summarises progress of the Nirex Safety Assessment Research Programme during 1988/89, in support of assessments of the post-emplacement radiological safety of a repository for the disposal of low-level and intermediate-level radioactive waste. During this period the assessments were concentrating on a comparative study of concepts and areas for deep emplacement of waste, in order to assist in the selection of preferred sites, and the research programme was therefore focussed on providing the data necessary for broad comparisons between different options to be made. (author)

Establishing a Radiation Protection Programme for a Research Reactor

International Nuclear Information System (INIS)

Abdallah, M. M.

2014-04-01

The nature and intensity of radiation from the operation of a research reactor depend on the type of reactor, its design features and its operational history. The protection of workers from the harmful effect of radiation must therefore be of paramount importance to any operating organization of a research reactor. This project report attempts to establish an operational radiation protection programme for a research reactor using the Ghana Research Reactor-1 as a case study. (au)

EDISON - research programme on electric distribution automation 1993-1997. Final report 1997

Energy Technology Data Exchange (ETDEWEB)

Lehtonen, M [ed.; VTT Energy, Espoo (Finland). Energy Systems

1998-08-01

This report comprises a summary of the results of the five year research programme EDISON on distribution automation in Finnish utilities. The research programme (1993 - 1997) was conducted under the leadership of VTT Energy, in cooperation with universities, distribution companies and the manufacturing industry. The main part of the funding has been from the Technology Development Centre TEKES and from manufacturing companies. The goal of the research programme was to develop a new scheme for a complete distribution automation system, including the network automation, computer systems in the control centre and the customer associated automation functions. In addition, the techniques for demand side management were developed and integrated into the automation scheme. The final aim was to demonstrate the automation functions and systems of the scheme in real distribution systems. The results of nineteen projects are given in this report

Københavns Kommunes indsats mod social dumping - målopfyldelsesevaluering

DEFF Research Database (Denmark)

Baadsgaard, Kelvin; Jørgensen, Henning

2016-01-01

Evaluering af, om de politiske intentioner med indsats mod social dumping i Københavns Kommune er blevet indfriet......Evaluering af, om de politiske intentioner med indsats mod social dumping i Københavns Kommune er blevet indfriet...

RELAP5/MOD3 AP600 problems

International Nuclear Information System (INIS)

Riemke, R.A.

1993-01-01

RELAP5/MOD3 is a reactor systems analysis code that has been developed jointly by the US Nuclear Regulatory Commission (USNRC) and a consortium consisting of several of the countries and domestic organizations that were members of the International Code Assessment and Applications Program (ICAP). The code is currently being used to simulate transients for the next generation of advanced light water reactors (ALWR's). One particular reactor design is the Westinghouse AP600 pressurized water reactor (PWR), which consists of two hot legs and four cold legs as well as passive emergency core cooling (ECC) systems. Initial calculations with RELAP5/MOD3 indicated that the code was not as robust as RELAP5/MOD2.5 with regard to AP600 calculations. Recent modifications in the areas of condensation wall heat transfer, interfacial heat transfer in the presence of noncondensibles, bubbly flow interfacial heat transfer, and time smoothing of both interfacial drag and interfacial heat transfer have improved the robustness, although more reliability is needed

The NIHR Public Health Research Programme: responding to local authority research needs in the United Kingdom.

Science.gov (United States)

Dorling, Hannah; Cook, Andrew; Ollerhead, Liz; Westmore, Matt

2015-12-11

The remit of the National Institute for Health Research Public Health Research (PHR) Programme is to evaluate public health interventions, providing new knowledge on the benefits, costs, acceptability and wider impacts of interventions, set outside of the National Health Service, intended to improve the health of the public and reduce inequalities. This paper illustrates how the PHR Programme is providing new knowledge for public health decision makers, based on the nine key areas for local authority public health action, described by the King's Fund. Many funded PHR projects are evaluating interventions, applied in a range of settings, across the identified key areas for local authority influence. For example, research has been funded on children and young people, and for some of the wider determinants of health, such as housing and travel. Other factors, such as spatial planning, or open and green spaces and leisure, are less represented in the PHR Programme. Further opportunities in research include interventions to improve the health of adolescents, adults in workplaces, and communities. Building evidence for public health interventions at local authority level is important to prioritise and implement effective changes to improve population health.

Extension of the lod score: the mod score.

Science.gov (United States)

Clerget-Darpoux, F

2001-01-01

In 1955 Morton proposed the lod score method both for testing linkage between loci and for estimating the recombination fraction between them. If a disease is controlled by a gene at one of these loci, the lod score computation requires the prior specification of an underlying model that assigns the probabilities of genotypes from the observed phenotypes. To address the case of linkage studies for diseases with unknown mode of inheritance, we suggested (Clerget-Darpoux et al., 1986) extending the lod score function to a so-called mod score function. In this function, the variables are both the recombination fraction and the disease model parameters. Maximizing the mod score function over all these parameters amounts to maximizing the probability of marker data conditional on the disease status. Under the absence of linkage, the mod score conforms to a chi-square distribution, with extra degrees of freedom in comparison to the lod score function (MacLean et al., 1993). The mod score is asymptotically maximum for the true disease model (Clerget-Darpoux and Bonaïti-Pellié, 1992; Hodge and Elston, 1994). Consequently, the power to detect linkage through mod score will be highest when the space of models where the maximization is performed includes the true model. On the other hand, one must avoid overparametrization of the model space. For example, when the approach is applied to affected sibpairs, only two constrained disease model parameters should be used (Knapp et al., 1994) for the mod score maximization. It is also important to emphasize the existence of a strong correlation between the disease gene location and the disease model. Consequently, there is poor resolution of the location of the susceptibility locus when the disease model at this locus is unknown. Of course, this is true regardless of the statistics used. The mod score may also be applied in a candidate gene strategy to model the potential effect of this gene in the disease. Since, however, it

Second Generation HTs Wire Based on RABiTS Substrates and MOD YBCO

Energy Technology Data Exchange (ETDEWEB)

Schoop, U. [American Superconductor Corporation, Westborough, MA; Rupich, Marty [American Superconductor Corporation, Westborough, MA; Thieme, C. L. H. [American Superconductor Corporation, Westborough, MA; Verebelyi, D. T. [American Superconductor Corporation, Westborough, MA; Zhang, W. [American Superconductor Corporation, Westborough, MA; Li, Xiaoping [American Superconductor Corporation, Westborough, MA; Kodenkandath, Thomas [American Superconductor Corporation, Westborough, MA; Nguyen, N. [American Superconductor Corporation, Westborough, MA; Siegal, E. E. [American Superconductor Corporation, Westborough, MA; Civale, L. [Los Alamos National Laboratory (LANL); Holesinger, T. G. [Los Alamos National Laboratory (LANL); Maiorov, B. [Los Alamos National Laboratory (LANL); Goyal, Amit [ORNL; Paranthaman, Mariappan Parans [ORNL

2005-01-01

The performance of Second Generation (2G) high temperature superconducting wire manufactured by continuous reel-to-reel processes is nearing the 300 A/cm-width (77 K, self field) performance threshold for commercial power cable applications. The 2G manufacturing approach under development at American Superconductor is based on the combination of the RABiTS substrate-buffer technology with metal organic deposition (MOD) of the YBCO layer. The capability of this process has been demonstrated in multiple 10 meter lengths with critical currents exceeding 250 A/cm-width with high uniformity and reproducibility. Critical currents of 380 A/cm-width have been achieved in short length samples prepared by the same basic process. The incorporation of nanoparticles ('nanodots') into the YBCO layer using the MOD process has resulted in a 2-fold improvement in the critical current at 65 K in a 3 T field. The research and development focus at ASMC is now directed toward the economical scale-up of the RABiTS/MOD process, optimization of the conductor properties for targeted applications and the use of 2G wire in initial demonstration applications.

On the programme of research development in the exclave region

Directory of Open Access Journals (Sweden)

Bilchak Vasily

2011-06-01

Full Text Available This article focuses on the development of research in the exclave region. The authors offer a programme of research development in the Kaliningrad region. The article describes the principal lines of implementation of priorities of modernization and technological upgrade of regional industries.

Assessment of RELAP5/MOD2 against a natural circulation experiment in Nuclear Power Plant Borssele

International Nuclear Information System (INIS)

Winters, L.

1993-07-01

As part of the ICAP (International Code Assessment and Applications Program) agreement between ECN (Netherlands Energy Research Foundation) and USNRC, ECN has performed a number of assessment calculations for the thermohydraulic system analysis code RELAP5/MOD2/36.05. This document describes the assessment of this computer program versus a natural circulation experiment as conducted at the Borssele Nuclear Power Plant. The results of this comparison show that the code RELAP5/MOD2 predicts well the natural circulation behaviour of Nuclear Power Plant Borssele

A Study of Electron Modes in Off-axis Heated Alcator C-Mod Plasmas

Science.gov (United States)

Fiore, C. L.; Ernst, D. R.; Mikkelsen, D.; Ennever, P. C.; Howard, N. T.; Gao, C.; Reinke, M. L.; Rice, J. E.; Hughes, J. W.; Walk, J. R.

2013-10-01

Understanding the underlying physics and stability of the peaked density internal transport barriers (ITB) that have been observed during off-axis ICRF heating of Alcator C-Mod plasmas is the goal of recent gyro-kinetic simulations. Two scenarios are examined: an ITB plasma formed with maximal (4.5 MW) off-axis heating power; also the use of off-axis heating in an I-mode plasma as a target in the hopes of establishing an ITB. In the former, it is expected that evidence of trapped electron mode instabilities could be found if a sufficiently high electron temperature is achieved in the core. Linear simulations show unstable modes are present across the plasma core from r/a = 0.2 and greater. In the latter case, despite establishing similar conditions to those in which ITBS were formed, none developed in the I-mode plasmas. Linear gyrokinetic analyses show no unstable ion modes at r/a < 0.55 in these I-mode plasmas, with both ITG and ETG modes present beyond r/a = 0.65. The details of the experimental results will be presented. Linear and non-linear simulations of both of these cases will attempt to explore the underlying role of electron and ion gradient driven instabilities to explain the observations. This work was supported by US-DoE DE-FC02-99ER54512 and DE-AC02-09CH11466.

Measurement of LHCD edge power deposition through modulation techniques on Alcator C-Mod

Energy Technology Data Exchange (ETDEWEB)

Faust, I. C.; Brunner, D.; LaBombard, B.; Parker, R. R.; Baek, S. G.; Chilenksi, M. A.; Hubbard, A.; Hughes, J. W.; Terry, J. L.; Shiraiwa, S.; Walk, J. R.; Wallace, G. M.; Whyte, D. G. [MIT Plasma Science and Fusion Center, Cambridge, MA USA (United States); Edlund, E. [Princeton Plasma Physics Laboratory, Princeton, NJ USA (United States)

2015-12-10

The efficiency of LHCD on Alcator C-Mod drops exponentially with line average density. At reactor relevant densities (> 1 · 1020 [m{sup −3}]) no measurable current is driven. While a number of causes have been suggested, no specific mechanism has been shown to be responsible for the loss of current drive at high density. Fast modulation of the LH power was used to isolate and quantify the LHCD deposition within the plasma. Measurements from these plasmas provide unique evidence for determining a root cause. Modulation of LH power in steady plasmas exhibited no correlated change in the core temperature. A correlated, prompt response in the edge suggests that the loss in efficiency is related to a edge absorption mechanism. This follows previous results which found the generation of n{sub ||}-independent SOL currents. Multiple Langmuir probe array measurements of the conducted heat conclude that the lost power is deposited near the last closed flux surface. The heat flux induced by LH waves onto the outer divertor is calculated. Changes in the neutral pressure, ionization and hard X-ray emission at high density highlight the importance of the active divertor in the loss of efficiency. Results of this study implicate a mechanism which may occur over multiple passes, leading to power absorption near the LCFS.

The Norwegian Climate and Ozone Research Programme

Energy Technology Data Exchange (ETDEWEB)

Dahlin, E. [ed.

1996-03-01

This report includes abstracts from a workshop arranged by the Norwegian Climate and Ozone Research Programme 11-12 March 1996. The abstracts are organized according to the sessions: (1) Regional effects of climate change with emphasis on ecology, (2) Climate research related to the North Atlantic, (3) What lessons can be drawn from paleoclimatology about changes in the current climate?, (4) Changes in the ozone layer and their effect on UV and biology. Abstracts of a selection of papers presented at the workshop can be found elsewhere in the present data base. 70 refs., 19 figs., 2 tabs.

Design and operation of a high-heat flux, flush-mounted ‘rail’ Langmuir probe array on Alcator C-Mod

Directory of Open Access Journals (Sweden)

A.Q. Kuang

2017-08-01

Full Text Available A poloidal array of toroidally-extended, flush-mounted ‘rail’ Langmuir probes was recently installed on Alcator C-Mod's vertical target plate divertor. The aim was to investigate if a Langmuir probe array could be designed to survive reactor-level heat fluxes and have the ability to make measurements that could be reliably interpreted under reactor-level plasma densities, neutral densities and magnetic fields. Langmuir probes are typically built to have incident field-line angles >10° to avoid interpretation issues associated with sheath expansion. However, at the high parallel heat fluxes experienced in reactor-relevant conditions such a probe would quickly overheat and melt. To mitigate both the issues of extreme heat flux and sheath expansion, each probe was designed to be flush with the divertor surface, toroidally-extended and field-aligned, giving it a ‘rail’ geometry. The flush mounted probes have proven to be exceptionally robust surviving the 2015–2016 campaign – a first for a C-Mod probe system. Examination of the probe current-voltage (I-V characteristics reveals that they are immune to sheath expansion at incident field angles down to ∼0.5°. Comparison of the flush probes to traditional proud probes shows that both measure the same electron pressure across the divertor plate. However, there are significant and systematic differences in the density, temperature and floating potential. This suggests that there is important physics, perhaps unique to conditions in a vertical-target plate divertor with small field-line attack angles, that affects the I-V characteristics and is not currently included in probe data analyses. Finally, the probe response is examined in the ‘death-ray’ regime, just near detachment. Previous work using proud probes has suggested that the ‘death-ray’ is an artefact of the probe bias. However, on flush mounted probes the ‘death-ray’ manifests itself under different conditions, which

High-J_c YBa₂Cu₃O_7-x-Ag superconducting thin films synthesized through a fluorine-free MOD method

DEFF Research Database (Denmark)

Tang, Xiao; Yue, Zhao; Wu, W.

2015-01-01

Obtaining a high critical current density (Jc) remains the main challenge in developing fluorine-free metal organic deposition (MOD) methods to fabricate YBCO superconducting thin films. Silver addition was used to raise the Jc values in this research work. By reacting with propionic acid...... and ammonia, AgNO3 was initially mixed with YBCO carboxylate precursors dissolved in methanol. High-temperature in situ XRD measurements on the YBCO-Ag powders revealed that silver addition lowers the incongruent melting temperature of YBCO to 760°C and resulted in a smooth surface morphology of the YBCO...... films at a temperature as low as 760°C. Grain growth and intergranular conductivity were also found to be improved by silver doping. After annealing under optimized conditions, a high Jc of 4.6MA/cm2 was obtained in a YBCO-Ag thin film with 10 wt% Ag....

Vaccine mod halthed testes i besætning

DEFF Research Database (Denmark)

Lauritsen, Klara Tølbøll

2012-01-01

Ny vaccine mod ledbetændelse forårsaget af Mycoplasma hyosynoviae testes nu hos 200 svin i en problembesætning. Håbet er færre halte svin og en nedbringelse af antibiotikaforbruget.......Ny vaccine mod ledbetændelse forårsaget af Mycoplasma hyosynoviae testes nu hos 200 svin i en problembesætning. Håbet er færre halte svin og en nedbringelse af antibiotikaforbruget....

A framework for designing a research-based “maths counsellor” teacher programme

DEFF Research Database (Denmark)

Jankvist, Uffe Thomas; Niss, Mogens

2015-01-01

force” of so-called “maths counsellors”, i.e., mathematics teachers whose goal it is to help identify students with genuine learning difficulties in mathematics, investigate the nature of these difficulties, and carry out research-based interventions to assist the students in overcoming them. We present...... and discuss the various components of the programme, theoretical as well as practical, and account for how these make up a framework for designing a research-based “maths counsellor” teacher programme...

SAFIR2014. The Finnish Research Programme on Nuclear Power Plant Safety 2011-2014. Interim Report

Energy Technology Data Exchange (ETDEWEB)

Simola, K. [ed.

2013-02-15

The Finnish Nuclear Power Plant Safety Research Programme 2011-2014, SAFIR2014, is a 4-year publicly funded national technical and scientific research programme on the safety of nuclear power plants. The programme is funded by the State Nuclear Waste Management Fund (VYR), as well as other key organisations operating in the area of nuclear energy. The programme provides the necessary conditions for retaining knowledge needed for ensuring the continuance of safe use of nuclear power, for developing new know-how and for participation in international co-operation. The SAFIR2014 Steering Group, responsible of the strategic alignements of the programme, consists of representatives of the Finnish Nuclear Safety Authority (STUK), Ministry of Employment and the Economy (MEE), Technical Research Centre of Finland (VTT), Teollisuuden Voima Oyj (TVO), Fortum Power and Heat Oy (Fortum), Fennovoima Oy, Lappeenranta University of Technology (LUT), Aalto University (Aalto), Finnish Funding Agency for Technology and Innovation (Tekes), Finnish Institute of Occupational Health (TTL) and the Swedish Radiation Safety Authority (SSM). The research programme is divided into nine areas: Man, organisation and society, Automation and control room, Fuel research and reactor analysis, Thermal hydraulics, Severe accidents, Structural safety of reactor circuits, Construction safety, Probabilistic risk analysis (PRA), and Development of research infrastructure. A reference group is assigned to each of these areas to respond for the strategic planning and to supervise the projects in its respective field. Research projects are selected annually based on a public call for proposals. Most of the projects are planned for the entire duration of the programme, but there can also be shorter one- or two-year projects. The annual volume of the SAFIR2014 programme in 2011-2012 has been 9,5-9,9 M euro. Main funding organisations were the State Nuclear Waste Management Fund (VYR) with over 5 M euro and

SAFIR2014. The Finnish Research Programme on Nuclear Power Plant Safety 2011-2014. Interim Report

International Nuclear Information System (INIS)

Simola, K.

2013-02-01

The Finnish Nuclear Power Plant Safety Research Programme 2011-2014, SAFIR2014, is a 4-year publicly funded national technical and scientific research programme on the safety of nuclear power plants. The programme is funded by the State Nuclear Waste Management Fund (VYR), as well as other key organisations operating in the area of nuclear energy. The programme provides the necessary conditions for retaining knowledge needed for ensuring the continuance of safe use of nuclear power, for developing new know-how and for participation in international co-operation. The SAFIR2014 Steering Group, responsible of the strategic alignements of the programme, consists of representatives of the Finnish Nuclear Safety Authority (STUK), Ministry of Employment and the Economy (MEE), Technical Research Centre of Finland (VTT), Teollisuuden Voima Oyj (TVO), Fortum Power and Heat Oy (Fortum), Fennovoima Oy, Lappeenranta University of Technology (LUT), Aalto University (Aalto), Finnish Funding Agency for Technology and Innovation (Tekes), Finnish Institute of Occupational Health (TTL) and the Swedish Radiation Safety Authority (SSM). The research programme is divided into nine areas: Man, organisation and society, Automation and control room, Fuel research and reactor analysis, Thermal hydraulics, Severe accidents, Structural safety of reactor circuits, Construction safety, Probabilistic risk analysis (PRA), and Development of research infrastructure. A reference group is assigned to each of these areas to respond for the strategic planning and to supervise the projects in its respective field. Research projects are selected annually based on a public call for proposals. Most of the projects are planned for the entire duration of the programme, but there can also be shorter one- or two-year projects. The annual volume of the SAFIR2014 programme in 2011-2012 has been 9,5-9,9 M euro. Main funding organisations were the State Nuclear Waste Management Fund (VYR) with over 5 M euro and

Functional overview of the Production Planning Model (ProdMod)

International Nuclear Information System (INIS)

Gregory, M.V.; Paul, P.K.

1995-09-01

The Production Planning Model (ProdMod) has been developed by SRTC for use by High Level Waste Program Management and High Level Waste Engineering as a fast running, integrated, comprehensive model of the entire SRS high level waste (HLW) complex. ProdMod can simulate the response of the HLW complex from its current state to the end of tank clean-up or to any intermediate point. The present document describes the initial release of ProdMod at the end of FY95: a model version that contains all the significant elements from the High-level Waste System Plan Revision 5 and is capable of running the simulation all the way to the postulated completion of waste removal. For the scenario represented by this release, that simulates approximately 70 years of operation of the HLW complex (out to FY2065). This initial release of ProdMod will serve as the immediate starting point for the modeling of the High-Level Waste System Plan Revision 6. Thus ProdMod is expected to be in a state of continuous change and improvement.the initial goal has been to generate a simulation of the processes of interest, with the emphasis on mass and volume balances tracked throughout the HLW complex. That has been accomplished. Future development will add a set of cost equations to the process equations and extend the model for use as a linear programming (optimization) application. The goal of this later phase will be to free the ProdMod user to some extent from the need to set up detailed simulation scenarios: the model will automatically make operational choices which minimize or maximize a given objective function. Appendix A contains the source code

Analysis of the VVER-440 reactor steam generator secondary side with the RELAP5/MOD3 code

International Nuclear Information System (INIS)

Tuunanen, J.

1993-01-01

Nuclear Engineering Laboratory of the Technical Research Centre of Finland has widely used RELAP5/MOD2 and -MOD3 codes to simulate horizontal steam generators. Several models have been developed and successfully used in the VVER-safety analysis. Nevertheless, the models developed have included only rather few nodes in the steam generator secondary side. The secondary side has normally been divided into about 10 to 15 nodes. Since the secondary side at the steam generators of VVER-440 type reactors consists of a rather large water pool, these models were only roughly capable to predict secondary side flows. The paper describes an attempt to use RELAP5/MOD3 code to predict secondary side flows in a steam generator of a VVER-440 reactor. A 2D/3D model has been developed using RELAP5/MOD3 codes cross-flow junctions. The model includes 90 volumes on the steam generator secondary side. The model has been used to calculate steady state flow conditions in the secondary side of a VVER-440 reactor steam generator. (orig.) (1 ref., 9 figs., 2 tabs.)

Bioenergy Research Programme. Yearbook 1994. Utilization of bioenergy and biomass conversion

International Nuclear Information System (INIS)

Alakangas, E.

1995-01-01

BIOENERGIA Research Programme is one of energy technology programmes of the Finnish Ministry of Trade and Industry (in 1995 TEKES, Technology Development Center). The aim of Bioenergy Research Programme is to increase the use of economically profitable and environmentally sound bioenergy by improving the competitiveness of present peat and wood fuels. Research and development projects will also develop new economically competitive biofuels and new equipment and methods for production, handling and using of biofuels. The funding for 1994 was nearly 50 million FIM and project numbered 60. The research area of biomass conversion consisted of 8 projects in 1994, and the research area of bioenergy utilization of 13 projects. The results of these projects carried out in 1994 are presented in this publication. The aim of the biomass conversion research is to produce more bio-oils and electric power as well at wood processing industry as at power plants. The conversion research was pointed at refining of the waste liquors of pulping industry and the extracts of them into fuel oil and liquid engine fuels, on production of wood oil via flash pyrolysis, and on combustion tests. Other conversion studies dealt with production of fuel-grade ethanol. For utilization of agrobiomass in various forms of energy, a system study is introduced where special attention is how to use rapeseed oil unprocessed in heating boilers and diesel engines. Possibilities to produce agrofibre in investigated at a laboratory study

The Communities' research and development programme on decommissioning of nuclear power plants

International Nuclear Information System (INIS)

1981-01-01

This is the first progress report of the European Community's programme (1979-1983) of research on the decommissioning of nuclear power plants. It shows the status of the programme on 31 December 1980. The programme seeks to promote a number of research and development projects as well as the identification of guiding principles. The projects concern the following subjects: long-term integrity of buildings and systems; decontamination for decommissioning purposes; dismantling techniques; treatment of specific waste materials: steel, concrete and graphite; large transport containers for radioactive was produced in the dismantling of nuclear power plants; estimation of the quantities of radioactive wastes arising from decommissioning of nuclear power plants in the Community; influence of nuclear power plant design features on decommissioning

Programme budget 1981

International Nuclear Information System (INIS)

1980-01-01

There are 11 main fields of KfK R + D activities which are connected with one or more of the research goals of a) assurance of nuclear fuel supply, b) nuclear waste management, c) safety of nuclear facilities, d) basic research and research on new technologies. The scientific and technical tasks connected with these goals in 1981 and on a medium-term basis as well as the financial requirements are presented in the programme budget. (orig.) [de

Comparision of calculations for the ROSA-IV LSTF with RELAP5/MOD0 and RELAP5/MOD1 (cycle 1)

International Nuclear Information System (INIS)

Fineman, C.P.; Tanaka, Mitsugu; Tasaka, Kanji

1982-03-01

10% and 2.5% cold leg break analyses have been completed for the ROSA-IV Large Scale Test Facility (LSTF) with the RELAP5/MOD0 and RELAP5/MOD1, cycle 1, computer codes. Comparisons between the calculations were made to determine any differences in the results obtained from the two versions of RELAP5. Differences in the two calculations were found which can be attributed to changes in the flow regime maps and critical flow model. (author)

Studies of Turbulence and Transport in Alcator C-Mod H-Mode Plasmas with Phase Contrast Imaging and Comparisons with GYRO

Science.gov (United States)

Porkolab, M.; Lin, L.; Edlund, E. M.; Rost, J. C.; Fiore, C. L.; Greenwald, M.; Mikkelsen, D.

2008-11-01

We present recent experimental measurements of turbulence and transport in C-Mod H-Mode plasmas with and without internal transport barriers (ITB) using the phase contrast imaging (PCI) diagnostic and compare the results with GYRO predictions. In plasmas without ITB, the fluctuation above 300 kHz observed by PCI agrees with ITG in GYRO simulation, including the direction of propagation, wavenumber spectrum, and absolute intensity within experimental uncertainly (+/-75%). After transition to ITBs, the observed overall fluctuation intensity increases. GYRO simulation in the core shows that ITG dominates in ITBs but its intensity is lower than the overall experimental measurements which may also include contributions from the plasma edge. These results, as well as the impact of varying ∇Ti, ∇n, and ExB shear on turbulence will be discussed. C.L. Fiore et al., Fusion Sci. Technol., 51, 303 (2007). M. Porkolab et al., IEEE Trans. Plasma Sci. 34, 229 (2006). J. Candy et al., Phys. Rev. Lett., 91, 045001 (2003).

PREFACE: Modern Technologies in Industrial Engineering (ModTech2015)

Science.gov (United States)

Oanta, E.; Comaneci, R.; Carausu, C.; Placzek, M.; Cohal, V.; Topala, P.; Nedelcu, D.

2015-11-01

The dominant feature of the current stage of society development is the update, refinement and innovation of the technological processes and products whose ultimate goal is to satisfy the market requirements. New and modern technologies should be considered in terms of their applicability in industry while the materials can lead to an increase in the quality of the end products. Replacing the existing technologies with innovative and eco-efficient technologies can contribute to an added value increase in the production of new materials. Materials are one of the most dynamic and prospective fields, with applications in all other fields. The development of new advanced materials and technologies shall contribute to the procurement of a wide range of reliable products, with competitive prices and worldwide performance, high sensitivity and functionality, user-friendly and reduced energy consumption, for different industrial applications. Research in the field of advanced/intelligent materials supposes a fundamental, experimental, laboratory and technological research and its approach has to be linked to the application. This involves, even for the niche fields, complex projects which result in scientific issues in top journals, patents and functional models. The third edition of ModTech International Conference was held in Mamaia, Romania, between June 17-20, with the Professional Association in Modern Manufacturing Technologies, ModTech, as main organizer, and the Constanta Maritime University, Constanta, Romania, Silesian University of Technology, Gliwice, Poland, the Technical University of Chisinau, Republic of Moldova and the Donetsk National Technical University, Donetsk, Ukraine as co-organizers. The ModTech2015 International Conference brought together representatives of technology and materials manufacturers, various universities, professional associations and research institutes that exchanged the latest knowledge on the conference topics. This edition was

Ny vaccine mod ledbetændelse er ikke effektiv

DEFF Research Database (Denmark)

Nielsen, Elisabeth Okholm; Lauritsen, Klara Tølbøll

2013-01-01

En ny mulighed for at vaccinere mod mykoplasma-ledbetændelse er undersøgt hos en slagtesvineproducent. Vaccinen kunne desværre ikke forebygge halthed eff ektivt.......En ny mulighed for at vaccinere mod mykoplasma-ledbetændelse er undersøgt hos en slagtesvineproducent. Vaccinen kunne desværre ikke forebygge halthed eff ektivt....

Detached divertor plasmas in Alcator C-Mod: A study of the role of atomic physics

International Nuclear Information System (INIS)

Lipschultz, B.; Boswell, C.; Goetz, J.A.

1999-01-01

Detailed profiles of the volumetric recombination occurring in Alcator C-Mod plasmas are presented. During detachment the recombination sink is compared to the divertor plate sink as well as the divertor ion source. Depending on plasma conditions, volume recombination removes between 10 and 75% of the ions before they reach the plates. A second, equally important process that leads to a drop in plate ion current is inferred to be a reduction in divertor ion source, which is correlated with a drop in power flowing into the ionization region and the pressure loss of detachment. For high n e the divertor recombination can cross the separatrix near the x-point, cool the core and lead to a disruption. Experimental measurements show a difference in ion and neutral velocities for H-mode detached plasmas. The resulting ion-neutral collisions are found to be more efficacious than recombination in removing momentum from the ions. The neutral component of volumetric power emission from the divertor has been measured by means of a novel filtering technique to be substantial (∼ 20% of the total divertor volumetric emission). (author)

Adaptation de l'agriculture aux politiques de gestion de l'eau et aux changements globaux : l'apport des modèles de programmation mathématique

OpenAIRE

Graveline, Nina

2013-01-01

Cette thèse développe et discute différentes approches micro-économiques de modélisation de l’agriculture pour représenter l’effet de changements globaux et de politiques de gestion de l’eau sur l’adaptation de l’agriculture et sur les ressources en eau. Après un chapitre de synthèse et une revue de la littérature, quatre essais sont présentés. Le premier essai décrit la représentation du comportement de dix exploitations agricoles en Alsace et en Bade (Allemagne) à partir de modèles de progr...

Advanced energy systems and technologies research in Finland. NEMO-2 Programme Annual Report 1996-1997

International Nuclear Information System (INIS)

1998-01-01

Advanced energy technologies were linked to the national energy research in the beginning of 1988 when energy research was reorganised in Finland. The Ministry of Trade and Industry established several energy research programmes and NEMO was one of them. Major objectives of the programme were to assess the potential of new energy systems for the national energy supply system and to promote industrial activities. Within the NEMO 2 programme for the years 1993-1998, research was focused on a few promising technological solutions. In the beginning of 1995, the national energy research activities were passed on to the Technology Development Centre TEKES. The NEMO 2 programme is directed towards those areas that have particular potential for commercial exploitation or development. Emphasis is placed particularly on solar and wind energy, as well as supporting technologies, such as energy storage and hydrogen technology. Resources have been focused on three specific areas: arctic wind technology, wind turbine components, and the integration of solar energy into applications (including thin film solar cells). In Finland, the growth of the new energy technology industry is concentrated on these areas. The turnover of the Finnish industry has been growing considerably due to the national research activities and support of technology development. The sales have increased more than 10 times compared with the year 1987 and is now over 300 million FIM. The support to industries and their involvement in the program has grown considerably. In this report, the essential research projects of the programme during 1996-1997 are described. The total funding for these projects was about 30 million FIM per year, of which the TEKES's share was about 40 per cent. The programme consists of 10 research projects, some 15 joint development projects, and 9 EU projects. In case the research projects and joint development projects are acting very closely, the description of the project is

Advanced energy systems and technologies research in Finland. NEMO-2 Programme Annual Report 1996-1997

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-10-01

Advanced energy technologies were linked to the national energy research in the beginning of 1988 when energy research was reorganised in Finland. The Ministry of Trade and Industry established several energy research programmes and NEMO was one of them. Major objectives of the programme were to assess the potential of new energy systems for the national energy supply system and to promote industrial activities. Within the NEMO 2 programme for the years 1993-1998, research was focused on a few promising technological solutions. In the beginning of 1995, the national energy research activities were passed on to the Technology Development Centre TEKES. The NEMO 2 programme is directed towards those areas that have particular potential for commercial exploitation or development. Emphasis is placed particularly on solar and wind energy, as well as supporting technologies, such as energy storage and hydrogen technology. Resources have been focused on three specific areas: arctic wind technology, wind turbine components, and the integration of solar energy into applications (including thin film solar cells). In Finland, the growth of the new energy technology industry is concentrated on these areas. The turnover of the Finnish industry has been growing considerably due to the national research activities and support of technology development. The sales have increased more than 10 times compared with the year 1987 and is now over 300 million FIM. The support to industries and their involvement in the program has grown considerably. In this report, the essential research projects of the programme during 1996-1997 are described. The total funding for these projects was about 30 million FIM per year, of which the TEKES`s share was about 40 per cent. The programme consists of 10 research projects, some 15 joint development projects, and 9 EU projects. In case the research projects and joint development projects are acting very closely, the description of the project is

From the Last Interglacial to the Anthropocene: Modelling a Complete Glacial Cycle (PalMod)

Science.gov (United States)

Brücher, Tim; Latif, Mojib

2017-04-01

We will give a short overview and update on the current status of the national climate modelling initiative PalMod (Paleo Modelling, www.palmod.de). PalMod focuses on the understanding of the climate system dynamics and its variability during the last glacial cycle. The initiative is funded by the German Federal Ministry of Education and Research (BMBF) and its specific topics are: (i) to identify and quantify the relative contributions of the fundamental processes which determined the Earth's climate trajectory and variability during the last glacial cycle, (ii) to simulate with comprehensive Earth System Models (ESMs) the climate from the peak of the last interglacial - the Eemian warm period - up to the present, including the changes in the spectrum of variability, and (iii) to assess possible future climate trajectories beyond this century during the next millennia with sophisticated ESMs tested in such a way. The research is intended to be conducted over a period of 10 years, but with shorter funding cycles. PalMod kicked off in February 2016. The first phase focuses on the last deglaciation (app. the last 23.000 years). From the ESM perspective PalMod pushes forward model development by coupling ESM with dynamical ice sheet models. Computer scientists work on speeding up climate models using different concepts (like parallelisation in time) and one working group is dedicated to perform a comprehensive data synthesis to validate model performance. The envisioned approach is innovative in three respects. First, the consortium aims at simulating a full glacial cycle in transient mode and with comprehensive ESMs which allow full interactions between the physical and biogeochemical components of the Earth system, including ice sheets. Second, we shall address climate variability during the last glacial cycle on a large range of time scales, from interannual to multi-millennial, and attempt to quantify the relative contributions of external forcing and processes

Forschungszentrum Karlsruhe Technik und Umwelt. Research and development programme 1999

International Nuclear Information System (INIS)

1999-01-01

The Karlsruhe Research Center is a national research establishment placed under the responsibility of the Federal Republic of Germany and the Federal Land of Baden-Wuerttemberg, and as a member of the Hermann von Helmholtz-Gemeinschaft Deutscher Forschungszentren belongs to the most important and independent research centers in Germany working in the fields of the natural sciences and engineering sciences. The center's research and development activities are defined in coordination with the policy and programmes of the two responsible Federal and Land Governments and span the range from pre-industrial research through to product and process development, research of a provident nature, and fundamental scientific research work, with almost all R and D activities of the center relating in one way or other to technology and the environment. The research programme of the center today covers subjects and aspects relating to the environment, energy, key technologies, and fundamental research, whereas at the time the center was founded, nuclear science and engineering was the dominating field of activities. The current spectrum of activities reflects the evolution in the past and is characterized by a great complexity of problems involved, which requires cross-disciplinary cooperation, and foresight in the definition of tasks and time horizons. (orig./CB) [de

Development of wide area reaction system for Reel-to-Reel TFA-MOD process

International Nuclear Information System (INIS)

Nomoto, Sukeharu; Aoki, Yuji; Teranishi, Ryo; Sato, Akihiro; Izumi, Teruo; Shiohara, Yuh

2006-01-01

The previously developed numerical simulation method for the TFA-MOD process, which calculated the YBCO growth kinetics, gas element diffusion and gas flow, was applied to study the suitable gas flow mode for a multi-turning Reel-to-Reel tape conveyance system of a long YBCO coated conductors. The high YBCO production rate with uniform J c distribution among tape lines is desired in the system. It was found by the numerical simulation for the vertical gas flow onto the tape surface to realize the above demands even in a wider reaction area. We developed a new wide area reaction tube for the Reel-to-Reel TFA-MOD process according to the numerically designed gas flow configuration. The demand for the new tube was confirmed to be satisfied by experiments

The European Community's research and development programme on the decommissioning of nuclear installations

International Nuclear Information System (INIS)

Skupinski, E.

1988-01-01

The Commission of the European Communities (CEC) continued with a second research programme on the decommissioning of nuclear installations (1984-88), after having completed a first programme on the decommissioning of nuclear power plants (1979-83). The programme, which has about 70 research contracts with organisations or private firms in the member states, includes the development and testing of advanced techniques, such as decontamination and dismantling, and the consideration of the radioactive waste arising therefrom. Work is done at laboratory scale or in the context of large-scale decommissioning operations. The paper will give an overview on the technical content and on some selected results. (author)

EDISON - research programme on electricity distribution automation 1993-1997. Interim report 1995

Energy Technology Data Exchange (ETDEWEB)

Lehtonen, M. [ed.] [VTT Energy, Espoo (Finland). Energy Systems

1996-12-31

The report comprises a summary of the results of the first three years of the research programme EDISON on distribution automation in Finnish electrical utilities. The five year research programme (1993-1997) is conducted under the leadership of VTT Energy, in cooperation with universities, distribution companies and the manufacturing industry. The main part of funding is from the Technology Development Centre (Tekes) and from manufacturing companies. The goal of the research programme is to develop a new scheme for a complete distribution automation system, including the network automation, computer systems in the control centre and the customer automation functions. In addition, the techniques for demand side management are developed and integrated into the automation scheme. The final aim is to demonstrate the automation functions and systems of the scheme in real distribution systems. The results of thirteen projects are now given. These results should be considered intermediate, since most projects will be continued in 1996. (orig.)

The Commission's research action programme on the development of nuclear fission energy

International Nuclear Information System (INIS)

1984-01-01

For its 'Framework Programme 1984-1987' the Commission has defined the major goals for a European Scientific and Technical Strategy. One of the means to reduce the energy dependence of the Community, which is an important objective, is to favour the development of nuclear fission energy. As electricity production by nuclear reactors has reached industrial maturity, the Community activities are directed mainly to safety aspects, in order to ensure the protection of workers and the general public, against hazards linked to operations in the nuclear fuel cycle. A description of the main features of the five sub-programmes on nuclear fission energy is given below; these programmes are: reactor safety; nuclear fuels and actinides research; management of radioactive waste; safeguarding and management of fissile materials; decommissioning of nuclear installations. The research and development work is carried out either by the Commission's Joint Research Center or by organizations and companies of the Member Countries, with the Commission's financial support. (author)

EDISON - research programme on electricity distribution automation 1993-1997. Interim report 1996

Energy Technology Data Exchange (ETDEWEB)

Lehtonen, M. [ed.] [VTT Energy, Espoo (Finland). Energy Systems

1997-12-31

The report comprises a summary of the results of the first four years of the research programme EDISON on distribution automation in Finnish utilities. The five year research programme (1993-1997) is conducted under the leadership of VTT Energy, in cooperation with universities, distribution companies and the manufacturing industry. The main part of the funding is from the Technology Development Centre TEKES and from manufacturing companies. The goal of the research programme is to develop a new scheme for a complete distribution automation system, including the network automation, computer systems in the control centre and the customer associated automation functions. In addition, the techniques for demand side management are developed and integrated into the automation scheme. The final aim is to demonstrate the automation functions and systems of the scheme in real distribution systems. The results of fifteen projects are now given. These results should be considered intermediate, since most projects will be continued in 1997. (orig.) 43 refs.

EDISON - research programme on electricity distribution automation 1993-1997. Interim report 1995

Energy Technology Data Exchange (ETDEWEB)

Lehtonen, M [ed.; VTT Energy, Espoo (Finland). Energy Systems

1997-12-31

The report comprises a summary of the results of the first three years of the research programme EDISON on distribution automation in Finnish electrical utilities. The five year research programme (1993-1997) is conducted under the leadership of VTT Energy, in cooperation with universities, distribution companies and the manufacturing industry. The main part of funding is from the Technology Development Centre (Tekes) and from manufacturing companies. The goal of the research programme is to develop a new scheme for a complete distribution automation system, including the network automation, computer systems in the control centre and the customer automation functions. In addition, the techniques for demand side management are developed and integrated into the automation scheme. The final aim is to demonstrate the automation functions and systems of the scheme in real distribution systems. The results of thirteen projects are now given. These results should be considered intermediate, since most projects will be continued in 1996. (orig.)

Assessment and improvement of condensation models in RELAP5/MOD3.2

Energy Technology Data Exchange (ETDEWEB)

Choi, Ki Yong; Park, Hyun Sik; Kim, Sang Jae; No, Hee Chen [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)

1998-12-31

The condensation models in the standard RELAP5/MOD3.2 code are assessed and improved based on the database, which is constructed from the previous experimental data on various condensation phenomena. The default model of the laminar film condensation in RELAP5/MOD3.2 does not give any reliable predictions, and its alternative model always predicts higher values than the experimental data. Therefore, it is needed to develop a new correlation based on the experimental data of various operating ranges in the constructed database. The Shah correlation, which is used to calculate the turbulent film condensation heat transfer coefficients in the standard RELAP5/MOD3.2, well predicts the experimental data in the database. The horizontally stratified condensation model of RELAP5/MOD3.2 overpredicts both cocurrent and countercurrent experimental data. The correlation proposed by H.J.Kim predicts the database relatively well compared with that of RELAP6/MOD3.2. The RELAP5/MOD3.2 model should use the liquid velocity for the calculation of the liquid Reynolds number and be modified to consider the effects of the gas velocity and the film thickness. 2 refs., 5 figs., 1 tab. (Author)

Assessment and improvement of condensation models in RELAP5/MOD3.2

Energy Technology Data Exchange (ETDEWEB)

Choi, Ki Yong; Park, Hyun Sik; Kim, Sang Jae; No, Hee Chen [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)

1997-12-31

The condensation models in the standard RELAP5/MOD3.2 code are assessed and improved based on the database, which is constructed from the previous experimental data on various condensation phenomena. The default model of the laminar film condensation in RELAP5/MOD3.2 does not give any reliable predictions, and its alternative model always predicts higher values than the experimental data. Therefore, it is needed to develop a new correlation based on the experimental data of various operating ranges in the constructed database. The Shah correlation, which is used to calculate the turbulent film condensation heat transfer coefficients in the standard RELAP5/MOD3.2, well predicts the experimental data in the database. The horizontally stratified condensation model of RELAP5/MOD3.2 overpredicts both cocurrent and countercurrent experimental data. The correlation proposed by H.J.Kim predicts the database relatively well compared with that of RELAP6/MOD3.2. The RELAP5/MOD3.2 model should use the liquid velocity for the calculation of the liquid Reynolds number and be modified to consider the effects of the gas velocity and the film thickness. 2 refs., 5 figs., 1 tab. (Author)

Radon transport modelling: User's guide to RnMod3d

International Nuclear Information System (INIS)

Andersen, C.E.

2000-08-01

RnMod3d is a numerical computer model of soil-gas and radon transport in porous media. It can be used, for example, to study radon entry from soil into houses in response to indoor-outdoor pressure differences or changes in atmospheric pressure. It can also be used for flux calculations of radon from the soil surface or to model radon exhalation from building materials such as concrete. The finite-volume model is a technical research tool, and it cannot be used meaningfully without good understanding of the involved physical equations. Some understanding of numerical mathematics and the programming language Pascal is also required. Originally, the code was developed for internal use at Risoe only. With this guide, however, it should be possible for others to use the model. Three-dimensional steady-state or transient problems with Darcy flow of soil gas and combined generation, radioactive decay, diffusion and advection of radon can be solved. Moisture is included in the model, and partitioning of radon between air, water and soil grains (adsorption) is taken into account. Most parameters can change in time and space, and transport parameters (diffusivity and permeability) may be anisotropic. This guide includes benchmark tests based on simple problems with known solutions. RnMod3d has also been part of an international model intercomparison exercise based on more complicated problems without known solutions. All tests show that RnMod3d gives results of good quality. (au)

Co-ordinated research programme on nuclear techniques for toxic elements in foodstuffs

International Nuclear Information System (INIS)

1990-01-01

This Co-ordinated Research Programme (CRP) was started by the Agency in 1985, within the framework of the Regional Cooperative Agreement for Research, Development and Training Related to Nuclear Science and Technology in the Asia and Pacific Region (RCA). Its main purpose has been to obtain comparative data on existing elemental concentrations of potentially toxic elements in foodstuffs in various Asian countries. The elements to be studied include the potentially most toxic trace elements (As, Cd, Hg, Pb, Se) as well as others of relevance to national monitoring programmes, such as Br, Cr, Cu, Fe, I, Mn, Sb, Tl, and Zn. An important supplementary purpose of the programme is to help establish analytical expertise for work of this kind in the individual countries. Scientists from several RCA Member States have participated in it, namely from Australia, Bangladesh, China, India, Indonesia, Japan, Malaysia, Pakistan, Thailand, and also from institutes in several countries outside the region, i.e., Argentina, Brazil, Jamaica and The Netherlands. This report summarizes the discussions that took place during the third and final Research Co-ordination Meeting (RCM) for the programme from 20-24 November 1989, in Jakarta, Indonesia. This document includes the progress reports presented by the participants as well as discussions and conclusions drawn from the meeting

The effects of placing an operational research fellow within the Viet Nam National Tuberculosis Programme.

Science.gov (United States)

Hoa, N B; Nhung, N V; Kumar, A M V; Harries, A D

2016-12-21

In April 2009, an operational research fellow was placed within the Viet Nam National Tuberculosis Control Programme (NTP). Over the 6 years from 2010 to 2015, the OR fellow co-authored 21 tuberculosis research papers (as principal author in 15 [71%]). This constituted 23% of the 91 tuberculosis papers published in Viet Nam during this period. Of the 21 published papers, 16 (76%) contributed to changes in policy ( n = 8) and practice ( n = 8), and these in turn improved programme performance. Many papers also contributed important evidence for better programme planning. Highly motivated OR fellows embedded within NTPs can facilitate high-quality research and research uptake.

Programme on radioactive waste management of the C.E.C.: orientations, motivations, organization and evolution

International Nuclear Information System (INIS)

Bishop, G.R.

1980-01-01

The Commission of the European Communities favours the development of nuclear energy to contribute to the solution of the energy problems. The Commission favours also the development of a complete nuclear fuel cycle including reprocessing and fast breeders. Thus the Commission is interested in the setting-up of effective solutions to problems of radioactive waste management. The Commission is operating by means of a Direct Action Programme, developed in the Joint Research Centre, and of an Indirect Action Programme, developed under contracts with national laboratories and industries. The programmes of the Commission cover all of the most important aspects of radioactive waste conditioning and disposal. The Commission is operating in strict connection with international organizations; collaboration agreements are in preparation with non-Community countries. The Plan of Action (1980 to 1992) in the Field of Radioactive Waste Management, recently approved by the Council, entrusts to the Commission a wider role in the implementation of the waste management policies

Geotechnical aspects of the UK DOE-sponsored radioactive waste disposal research programme

International Nuclear Information System (INIS)

Cooling, C.M.; Hudson, J.A.

1987-01-01

One of the crucial factors for underground repository design is understanding the engineering properties and behaviour of the host rock. To develop this understanding, the Department of the Environment has sponsored a continuing programme of geotechnical research from 1979 to the present day. The authors describe the structure of the research programme, highlight some of the individual projects, indicate the most important conclusions and provide an overview of both the current state of knowledge and 'the way ahead'. 9 refs.; 9 figs.; 1 table

Using computer program RELAP5/MOD2 on microcomputers

International Nuclear Information System (INIS)

Grgic, D.; Bajs, T; Cavlina, N.; Debrecin, N.

1990-01-01

Our work on installation of RELAP5/MOD2 code on IBM4341, mVAX 11, MGT-386 and COMPAQ-386/20e computers is described. Main characteristics of RELAP5/MOD2 structure programming style and differences between FORTRAN VS, VAX-11 FORTRAN and NDP FORTRAN 386 are presented. We discussed basic philosophy used in modification and testing and test results. (author)

Characterization of the Hamamatsu 8" R5912-MOD Photomultiplier tube

Science.gov (United States)

Kaptanoglu, Tanner

2018-05-01

Current and future neutrino and direct detection dark matter experiments hope to take advantage of improving technologies in photon detection. Many of these detectors are large, monolithic optical detectors that use relatively low-cost, large-area, and efficient photomultiplier tubes (PMTs). A candidate PMT for future experiments is a newly developed prototype Hamamatsu PMT, the R5912-MOD. In this paper we describe measurements made of the single photoelectron time and charge response of the R5912-MOD, as well as detail some direct comparisons to similar PMTs. Most of these measurements were performed on three R5912-MOD PMTs operating at gains close to 1 × 107. The transit time spread (σ) and the charge peak-to-valley were measured to be on average 680ps and 4.2 respectively. The results of this paper show the R5912-MOD is an excellent candidate for future experiments in several regards, particularly due to its narrow spread in timing.

Brazilian Irradiation Project: CAFE-MOD1 validation experimental program

International Nuclear Information System (INIS)

Mattos, Joao Roberto Loureiro de; Costa, Antonio Carlos L. da; Esteves, Fernando Avelar; Dias, Marcio Soares

1999-01-01

The Brazilian Irradiation Project whose purpose is to provide Brazil with a minimal structure to qualify the design, fabrication and quality procedures of nuclear fuels, consists of three main facilities: IEA-R1 reactor of IPEN-CNEN/SP, CAFE-MOD1 irradiation device and a unit of hot cells. The CAFE-MOD1 is based on concepts successfully used for more than 20 years in the main nuclear institutes around the world. Despite these concepts are already proved it should be adapted to each reactor condition. For this purpose, there is an ongoing experimental program aiming at the certification of the criteria and operational limits of the CAFE-MOD1 in order to get the allowance for its installation at the IEA-R1 reactor. (author)

RELAP5/MOD2: for PWR transient analysis

International Nuclear Information System (INIS)

Ransom, V.H.

1983-01-01

RELAP5 is a light water reactor system transient simulation code for use in nuclear plant safety analysis. Development of a new version, RELAP5/MOD2, has been completed and will be released to the United States Nuclear Regulatory Commission during September of 1983. The new and improved modeling capability of RELAP5/MOD2 is described and some developmental assessment results are presented. The future plans for extension to severe accident modeling are briefly discussed

A review of the HDR research programme

International Nuclear Information System (INIS)

Talja, H.; Koski, K.; Rintamaa, R.; Keskinen, R.

1995-10-01

In the German HDR (Heissdampfreaktor, hot steam reactor) reactor safety programme, experiments and simulating numerical analyses have been undertaken since 1976 to study the integrity and safety of light water reactors under operational and faulted conditions. The last experiments of the programme were conducted in 1991. The post test analyses have been finished by March 1994 and the last final reports were obtained a few months later. The report aims to inform the utilities and the regulatory body of Finland about the contents of the lokset HDR research programme and to consider the applicability of the results to safety analyses of Finnish nuclear power plants. The report centers around the thermal shock and piping component experiments within the last or third phase of the HDR programme. Investigations into severe reactor accidents, fire safety and non-destructive testing, also conducted during the third phase, are not considered. The report presents a review of the following experiment groups: E21 (crack growth under corrosive conditions, loading due to thermal stratification), E22 (leak rate and leak detection experiments of through-cracked piping), E23 (thermal transient and stratification experiments for a pipe nozzle), E31 (vibration of cracked piping due to blow down and closure of isolation valve), E32 (seismically induced vibrations of cracked piping), E33 (condensation phenomena in horizontal piping during emergency cooling). A comprehensive list of reference reports, received by VTT and containing a VTT more detailed description, is given for each experiment group. The review is focused on the loading conditions and their theoretical modelling. A comparison of theoretical and experimental results is presented for each experiment group. The safety margins are finally assessed with special reference to leak-before-break, a well known principle for assuring the integrity of primary circuit piping of nuclear power plants. (orig.) (71 figs., 5 tabs.)

A Self-Management Programme of Activity Coping and Education - SPACE for COPD(C) - in primary care: The protocol for a pragmatic trial.

Science.gov (United States)

Bourne, Claire LA; Kanabar, Pratiksha; Mitchell, Katy; Schreder, Sally; Houchen-Wolloff, Linzy; Bankart, M John G; Apps, Lindsay; Hewitt, Stacey; Harvey-Dunstan, Theresa; Singh, Sally J

2017-07-10

National guidance for chronic obstructive pulmonary disease (COPD) suggests that self-management support be provided for patients. Our institution has developed a standardised, manual-based, supported self-management programme: Self-Management Programme of Activity Coping and Education (SPACE for COPD(C)). SPACE was previously piloted on a 1-2-1 basis, delivered by researchers, to individuals with COPD. Discussions with stakeholders highlighted considerable interest in delivering the SPACE for COPD(C) intervention as a group-based self-management programme facilitated by healthcare professionals (HCPs) in primary care settings. The study aims are to explore the feasibility, acceptability and efficacy for the intervention to be delivered and supported by HCPs and to examine whether group-based delivery of SPACE for COPD(C), with sustained support, improves patient outcomes following the SPACE for COPD(C) intervention. A prospective, multi-site, single-blinded randomised controlled trial (RCT) will be conducted, with follow-up at 6 and 9 months. Participants will be randomly assigned to either the control group (usual care) or intervention group (a six-session, group-based SPACE for COPD(C)self-management programme delivered over 5 months). The primary outcome is change in COPD assessment test at 6 months.A discussion session will be conducted with HCPs who deliver the intervention to discuss and gain insight into any potential facilitators/barriers to implementing the intervention in practice. Furthermore, we will conduct semi-structured focus groups with intervention participants to understand feasibility and acceptability. All qualitative data will be analysed thematically. The project has received a favourable opinion from South Hampshire B Research Ethics Committee, REC reference: 14/SC/1169 and full R&D approval from the University Hospitals of Leicester NHS Trust: 152408.Study results will be disseminated through appropriate peer-reviewed journals, national

L'utilisation d'un modèle spécifique: l'exemple de la Bolivie

Directory of Open Access Journals (Sweden)

1996-01-01

Full Text Available La modélisation graphique connaît aujourd’hui un essor certain depuis la publication de la Géographie Universelle sous la direction de R. Brunet en France. Les utilisations en sont diverses, qu’elles aient des fins pédagogiques, expérimentales ou prospectives, mais il n’en demeure pas moins qu’à la différence du langage mathématique, la pratique du langage graphique constitue un handicap lorsqu’il s’agit de valider ce type de modèles. Pourtant cette démarche est non seulement possible mais souhaitable, un modèle non validable n’étant plus un modèle. Cependant les tests de validation/vérification et de validation/exploration utilisés pour analyser le modèle de l’espace bolivien sont globalement satisfaisants. LA UTILIZACIÓN DE UN MODELO ESPECÍFICO: EL EJEMPLO DE BOLIVIA. La modelización gráfica tiene en Francia un verdadero desarrollo con la publicación de la Geografía Universal dirigida por R. Brunet. Las utilizaciones son variadas: pedagógicas, experimentales o de investigación pero la práctica del código gráfico es mucho más problemático que la práctica del código matemático cuando se necesita validar un modelo. Sin embargo las pruebas de validación/comprobación y de validación/investigación utilizadas para analizar el modelo del espacio boliviano son bastante satisfactorias. USING SPECIFIC MODELIZATION IN THE CASE OF BOLIVIA. The use of grafic modelization has grown to be acknowledged in France since the publishing of Géographie Universelle edited by R. Brunet. However, in spite of its various applications, whether pedagogical, experimental or prospective, evidence is there to show that graphic models do not as yet compare with mathematical models as regards the validating process. Nonetheless, the two-step testing based on validation/verification and validation/ exploration carried out here on a Bolivian space model does give quite satisfying results.

RELAP5/MOD2 calculation of OECD LOFT test LP-FW-01

International Nuclear Information System (INIS)

Croxfod, M.G.; Harwood, C.; Hall, P.C.

1992-04-01

RELAP5/MOD2 is being used by GDCD for calculation of certain small break loss-of-coolant accidents and pressurized transients in the Sizewell ''B'' PWR. To test the ability of RELAP5/MOD2 to model the primary feed-and-bleed recovery procedure following a complete loss- of-feedwater event, post test calculations have been carried out of OECD LOFT test LP-FW-01. This report describes the comparison between the code calculations and the test data. It is found that although the standard version of RELAP5/MOD2 gives a reasonable prediction of the experimental transient, the long term pressure history is better calculated with a modified code version containing a revised horizontal stratification entrainment model. The latter allows an improved calculation of entrainment of liquid from the hot leg into the surge line. RELAP5/MOD2 is found to give a more accurate simulation of the experimental transient than was achieved in previous UK studies using RETRAN-02/MOD2

Evaluation of the medical student research programme in Norwegian medical schools. A survey of students and supervisors

Directory of Open Access Journals (Sweden)

Tømmerås Karin

2009-07-01

Full Text Available Abstract Background The Medical Student Research Programme is a national education and grant scheme for medical students who wish to carry out research in parallel with their studies. The purpose of the programme is to increase recruitment of people with a standard medical degree to medical research. The Research Programme was established in 2002 and underwent a thorough evaluation during the spring of 2007. The evaluation should investigate if the programme had fulfilled its objectives of increased recruitment to medical research, in addition to the students' and supervisors' satisfaction of the programme, and unwanted differences between the universities. Methods Data was collected from students, supervisors and administrative staff via web-based questionnaires. Information about admission, implementation, results achieved and satisfaction was analysed and compared between the four Norwegian medical schools. In addition, the position of the scheme in relation to the national Quality Reform of Higher Education was analysed. Results At the end of 2006, the Medical Student Research Programme had recruited 265 medical students to research. These consisted of 214 active students, 35 who had completed their studies and only 17 who had dropped out. Both students and supervisors were generally very satisfied with the scheme, including the curriculum, the results achieved and the administrative service. The majority of students wanted to continue their research towards a PhD and, of those who had completed the Medical Student Research Programme, practically all had published one or several scientific papers. The survey showed only small differences between the four medical schools, despite their choice of somewhat different solutions in terms of administration and organisation. The Medical Student Research Programme satisfies the majority of the demands of the Quality Reform, however as an integrated research programme aimed at a PhD it presupposes

Evaluation of the medical student research programme in Norwegian medical schools. A survey of students and supervisors

Science.gov (United States)

Hunskaar, Steinar; Breivik, Jarle; Siebke, Maje; Tømmerås, Karin; Figenschau, Kristian; Hansen, John-Bjarne

2009-01-01

Background The Medical Student Research Programme is a national education and grant scheme for medical students who wish to carry out research in parallel with their studies. The purpose of the programme is to increase recruitment of people with a standard medical degree to medical research. The Research Programme was established in 2002 and underwent a thorough evaluation during the spring of 2007. The evaluation should investigate if the programme had fulfilled its objectives of increased recruitment to medical research, in addition to the students' and supervisors' satisfaction of the programme, and unwanted differences between the universities. Methods Data was collected from students, supervisors and administrative staff via web-based questionnaires. Information about admission, implementation, results achieved and satisfaction was analysed and compared between the four Norwegian medical schools. In addition, the position of the scheme in relation to the national Quality Reform of Higher Education was analysed. Results At the end of 2006, the Medical Student Research Programme had recruited 265 medical students to research. These consisted of 214 active students, 35 who had completed their studies and only 17 who had dropped out. Both students and supervisors were generally very satisfied with the scheme, including the curriculum, the results achieved and the administrative service. The majority of students wanted to continue their research towards a PhD and, of those who had completed the Medical Student Research Programme, practically all had published one or several scientific papers. The survey showed only small differences between the four medical schools, despite their choice of somewhat different solutions in terms of administration and organisation. The Medical Student Research Programme satisfies the majority of the demands of the Quality Reform, however as an integrated research programme aimed at a PhD it presupposes access to PhD courses before the

Electricity research programme - Overview report on activities in 2005; Programm Elektrizitaet. Ueberblicksbericht zum Forschungsprogramm 2005

Energy Technology Data Exchange (ETDEWEB)

Brueniger, R.

2006-07-01

This overview-report for the Swiss Federal Office of Energy (SFOE) summarises the work done in 2005 in the various research areas covered by the Swiss Electricity Research programme. Work done in the programme's two main areas - technologies and efficient applications - is reviewed. In the technologies area, high-temperature superconductivity - and especially its use in power-generation facilities - is looked at, as are the topics of energy conversion and thermo-electric power generation. Further, energy storage using compressed-air is discussed. Power distribution and the use of controllable storage in the low-voltage mains is briefly commented on, as is distributed power generation. Information and communications technologies are reviewed, as is work done in the electrical drives area. Work in other areas summarised includes lighting and uninterruptible power-supplies. Co-operation with Swiss institutions and international organisations such as the IEA is reviewed. Implementation work in the pilot and demonstration area is commented on. This includes work in various areas ranging from set-top boxes through to the optimisation of compressed-air systems and electrical drives as well as codes of conduct and agreements for water-dispensers and cooling systems in retail applications and the optimisation of wastewater treatment plant. The report is completed with a list of current research and development projects.

RELAP5/MOD1-EUR evaluation. Comparison with the INEL original version

International Nuclear Information System (INIS)

Mazzantini, O.A.

1990-01-01

In this work, the values calculated from two versions of the RELAP5/MOD1 code are compared with those measured in different tests. The first version of RELAP5 is the cycle 19 of the original version of INEL (RELAP5/MOD1-INEL) and the second version improved by EURATOM (RELAP5/MOD1-EUR) which was transferred to ENACE through agreements made with SIEMENS/KWU. (Author) [es

Control system design for the MOD-5A 7.3 mW wind turbine generator

Science.gov (United States)

Barton, Robert S.; Hosp, Theodore J.; Schanzenbach, George P.

1995-01-01

This paper provides descriptions of the requirements analysis, hardware development and software development phases of the Control System design for the MOD-5A 7.3 mW Wind Turbine Generator. The system, designed by General Electric Company, Advanced Energy Programs Department, under contract DEN 3-153 with NASA Lewis Research Center and DOE, provides real time regulation of rotor speed by control of both generator torque and rotor torque. A variable speed generator system is used to provide both airgap torque control and reactive power control. The wind rotor is designed with segmented ailerons which are positioned to control blade torque. The central component of the control system, selected early in the design process, is a programmable controller used for sequencing, alarm monitoring, communication, and real time control. Development of requirements for use of aileron controlled blades and a variable speed generator required an analytical simulation that combined drivetrain, tower and blade elastic modes with wind disturbances and control behavior. An orderly two phase plan was used for controller software development. A microcomputer based turbine simulator was used to facilitate hardware and software integration and test.

Public sector's research programme on spent fuel management in Finland supporting the authorities

International Nuclear Information System (INIS)

Vuori, S.; Rasilainen, K.

2000-01-01

A multiphase research program launched in 1989 to support Finnish authorities in their activities concerning spent fuel management is reviewed. The Finnish program for spent fuel management has so far managed to keep its original time schedule at least partly due to clearly defined responsibilities between the nuclear energy producing industry and the authorities. It appears that the public sector's research programme has been successful in its supporting role, because authorities have had good possibilities to adjust the emphasis and volume of the research programme from the very beginning. (author)

Inventory of Dutch National Research on Global Climate Change: Inside and outside the National Research Programme

International Nuclear Information System (INIS)

Smythe, K.D.; Bernabo, C.; Kingma, J.; Vrakking, W.

1993-04-01

This report contains brief descriptions of research projects in the field of global climate change, performed both within and outside the Dutch National Research Programme on Global Air Pollution and Climate Change (NRP). The descriptions result from a survey of the major research institutions in The Netherlands, conducted by two consultancies (Science and Policy Associates, SPA and Holland Consulting Group, HCG) at the request of the NRP. The inventory had to be completed within a relatively brief period; it is thus unavoidable that one or more projects may sometimes contain inaccuracies. Taken as a whole, this report presents a good picture of the Dutch research activities in this area. The scope and structure of this survey and the contents of this report are based on a request for information from the World Meteorological Organization (WMO) for an intergovernmental meeting on the World Climate Programme (WCP), held on 14-16 April 1993. The WMO request emphasised activities related to the WCP and its associated programmes. The database resulting from this exercise will be a useful tool for organisations which sponsor and conduct research into global climate change in their efforts to stimulate cooperation and to promote coordination between the research groups in The Netherlands and abroad. There are plans to update the inventory in the future and to provide the information to participating organisations in The Netherlands, as well as to research organisations in other countries. An overview of the current research is provided in Volume 1, a list of projects being provided in Annex 3. The projects are presented according to the themes and subthemes which are used in the NRP

The scientific research programmes of Lakatos and applications in parasitology

Directory of Open Access Journals (Sweden)

Cabaret J.

2008-09-01

Full Text Available The methodology of scientific research programme (MSRP proposed by Lakatos was in the line of the proposals made by Popper. MSRP were intended for constructing and evaluating research programme, which is unique among philosophers of science. Surprisingly, scientists dedicated to research in mathematics, physic or biology have not used much MRSP. This could be due to the fact that scientists are not aware of the existence of MSRP, or they find it difficult to apply to their own investigations. That is why we present firstly the main characteristics of this methodology (hard core – the group of hypothesis that are admitted by experts in the field, auxiliary hypotheses – which are intended to protect and refine the hypotheses of the hard-core, and heuristics for mending and evaluating the MSRP and, secondly, propose an example in helminthology. We think that the methodology of Lakatos, is a useful tool, but it cannot encompass the large flexibility of investigations pathways.

The Community's research and development programme on decommissioning of nuclear installations: First annual progress report (year 1985)

International Nuclear Information System (INIS)

1986-01-01

This is the first Annual Progress Report of the European Community's 1984-88 programme of research on the decommissioning of nuclear installations. It shows the status of implementation reached on 31 December 1985. The 1984-88 programme has the following contents: A. Research and development projects concerning the following subjects: Project No 1: Long-term integrity of building and systems; Project No 2: Decontamination for decommissioning purposes; Project No 3: Dismantling techniques; Project No 4: Treatment of specific waste materials: steel, concrete and graphite; Project No 5: Large containers for radioactive waste produced in the dismantling of nuclear installations; Project No 6: Estimation of the quantities of radioactive wastes arising from the decommissioning of nuclear installations in the Community; Project No 7: Influence of installation design features on decommissioning. B. Identification of guiding principles, namely: - certain guiding principles in the design and operation of nuclear installations with a view to simplifying their subsequent decommissioning, - guiding principles in the decommissioning of nuclear installations which could form the initial elements of a Community policy in this field. C. Testing of new techniques under real conditions, within the framework of large-scale decommissioning operations undertaken in Member States. This first progress report, covering the period of putting the programme into action, describes the work to be carried out under the 27 research contracts concluded, as well as initial work performed and first results obtained

The European fusion research and development programme and the ITER Project

International Nuclear Information System (INIS)

Green, B.J.

2004-01-01

The EURATOM fusion R and D programme is a well integrated and co-ordinated programme a good example of a European Research Area. Its goal is 'the joint creation of prototype reactors for power stations to meet the needs of society: operational safety, environmental compatibility, economic viability'. The programme is focussed on the magnetic confinement approach to fusion energy and supports 21 associated laboratories and a range of experimental and fusion technology facilities. The paper will briefly describe this programme and how it is organised and implemented. Its success and that of other national programmes has defined the international ITER Project, which is the next logical step in fusion R and D. The paper will describe ITER, its aims, its design, and the supporting manufacture of prototype components. The European contribution to ITER, as well as the exploitation of the Joint European Torus (JET) and long-term fusion reactor technology R and D are carried out under the European Fusion Development Agreement (EFDA). Finally, the potential advantages of fusion as an energy source will be presented. (author)

MOD-5A wind turbine generator program design report: Volume 1: Executive Summary

Science.gov (United States)

1984-01-01

The design, development and analysis of the 7.3 MW MOD-5A wind turbine generator covering work performed between July 1980 and June 1984 is discussed. The report is divided into four volumes: Volume 1 summarizes the entire MOD-5A program, Volume 2 discusses the conceptual and preliminary design phases, Volume 3 describes the final design of the MOD-5A, and Volume 4 contains the drawings and specifications developed for the final design. Volume 1, the Executive Summary, summarizes all phases of the MOD-5A program. The performance and cost of energy generated by the MOD-5A are presented. Each subsystem - the rotor, drivetrain, nacelle, tower and foundation, power generation, and control and instrumentation subsystems - is described briefly. The early phases of the MOD-5A program, during which the design was analyzed and optimized, and new technologies and materials were developed, are discussed. Manufacturing, quality assurance, and safety plans are presented. The volume concludes with an index of volumes 2 and 3.

SIHTI 2. Energy and environmental technology. Yearbook 1994 of the research programme. Project reports

International Nuclear Information System (INIS)

Korhonen, M.; Saviharju, K.

1995-01-01

The SIHTI 2 research programme on energy and environmental technology is concentrating on areas of environmental technology that are vital to Finland or in which Finns can engage in pioneering research. The promotion of product development within the environmental technology industry produces solutions for reducing the emissions of the energy sector. It is also a way of boosting Finland's share of the world market for such technology. The objectives of the programme are to cut down harmful emissions, recycle raw materials, reduce the amount of byproducts and wastes and achieve a greater utilisation of wastes. In additions, an objective is to create basic information about the effects of environmental protection technology for the other national research programmes. The development of internationally comparable research, monitoring and measurement methods creates a basis for wide-ranging international cooperation. The area of research also covers environmental problems connected with energy in the forest and base metal industries as well as the systematic development of life-cycle analyses. The programme will be carried out in 1993 - 1998. As of 1 January 1995 the Technology development Centre TEKES took over the responsibility for energy technology research and development activities, which were previously administered by the Energy Department of the Ministry of Trade and Industry. This yearbook 1994 contains project reports of the research and joint development projects and information about the participating institutions. (orig.)

Sur la modélisation des supraconducteurs : le ``modèle de l'état critique'' de Bean, en trois dimensions

Science.gov (United States)

Bossavit, A.

1993-03-01

Macroscopic modelling of superconductors demands a substitution of some nonlinear behavior law for Ohm's law. For this, a version of Bean's “critical state” model, derived from the setting of a convex functional of the current density field, valid in dimension 3 without any previous assumption about the direction of currents, is proposed. It is shown how two standard three-dimensional finite element methods (“h-formulation” and “e-formulation”), once fitted with this model, can deal with situations were superconductors are present. La modélisation macroscopique des supraconducteurs suppose le remplacement de la loi d'Ohm par une loi de comportement non linéaire adéquate. On présente à cet effet une version du “modèle de Bean”, ou modèle de l'état critique, basée sur la construction d'une certaine fonctionnelle convexe du champ des densités de courant, qui est valable en dimension 3 sans hypothèses préalables sur la direction des courants. On montre comment adapter deux méthodes standards de calcul de courants de Foucault par élérnents finis en trois dimensions (“en h” et “en e”) à la présence de supraconducteurs, en incorporant ce modèle.

Control of substrate oxidation in MOD ceramic coating on low-activation ferritic steel with reduced-pressure atmosphere

Energy Technology Data Exchange (ETDEWEB)

Tanaka, Teruya, E-mail: teru@nifs.ac.jp; Muroga, Takeo

2014-12-15

Highlights: • A Cr{sub 2}O{sub 3} layer was produced on a ferritic steel substrate with a reduced-pressure. • The Cr{sub 2}O{sub 3} layer prevents further substrate oxidation in following coating process. • The Cr{sub 2}O{sub 3} layer has a function as a hydrogen permeation barrier. • A smooth MOD Er{sub 2}O{sub 3} coating was successfully made on the Cr{sub 2}O{sub 3} layer by dip coating. • The Cr{sub 2}O{sub 3} layer would enhance flexibility in MOD coating process and performances. - Abstract: An Er{sub 2}O{sub 3} ceramic coating fabricated using the metal–organic decomposition (MOD) method on a Cr{sub 2}O{sub 3}-covered low-activation ferritic steel JLF-1 substrate was examined to improve hydrogen permeation barrier performance of the coating. The Cr{sub 2}O{sub 3} layer was obtained before coating by heat treating the substrate at 700 °C under reduced pressures of <5 × 10{sup −3} Pa and 5 Pa. The Cr{sub 2}O{sub 3} layer was significantly stable even with heat treatment at 700 °C in air. This layer prevented further production of Fe{sub 2}O{sub 3}, which has been considered to degrade coating performance. An MOD Er{sub 2}O{sub 3} coating with a smooth surface was successfully obtained on a Cr{sub 2}O{sub 3}-covered JLF-1 substrate by dip coating followed by drying and baking. Preprocessing to obtain a Cr{sub 2}O{sub 3} layer would provide flexibility in the coating process for blanket components and ducts. Moreover, the Cr{sub 2}O{sub 3} layer suppressed hydrogen permeation through the JLF-1 substrate. While further optimization of the coating fabrication process is required, it would be possible to suppress hydrogen permeation significantly by multilayers of Cr{sub 2}O{sub 3} and MOD oxide ceramic.

The Relevance Of Research And Development (R&D) Programmes ...

African Journals Online (AJOL)

The purpose of this study was to assess the relevance of Research and Development (R&D) programmes of Nigerian universities in national development. Data was collected form 432 senior academic staff of five selected universities in Nigeria. Indicators of relevance such as quality, results, dissemination, utilization and ...

RELAP5/MOD2 assessment at Babcock and Wilcox

International Nuclear Information System (INIS)

Nithianandan, C.K.; Shah, N.H.; Schomaker, R.J.; Turk, C.

1986-01-01

Babcock and Wilcox (B and W) has been working with the code developers at EG and G Idaho, Inc. and the NRC assessing the RELAP5/MOD2 computer code by simulating selected separate effects tests. The purpose of this B and W Owners Group-sponsored assessment was to evaluate RELAP5/MOD2 for use in design calculations for the MIST and OTIS integral system tests and in predicting pressurized water reactor (PWR) transients. B and W evaluated various versions of the code and made recommendations to improve code performance. As a result, the currently released version (Cycle 36.1) has been improved considerably over earlier versions. However, further refinements to some of the constitutive models may still be needed to further improve specific predictive capabilities of RELAP5/MOD2

Plans and status of RELAP5/MOD3

International Nuclear Information System (INIS)

Weaver, W.L.

1989-01-01

RELAP5/MOD3 is a pressurized water reactor (PWR) system analysis code being developed jointly by the US Nuclear Regulatory Commission (USNRC) and consisting of several of the countries that are members of the International Code Assessment and Applications Program (ICAP). This code development program is called the ICAP Code Improvement Program. The mission of the RELAP5/MOD3 code improvement program is to develop a code version suitable for the analysis of all transients and postulated accidents in PER systems including both large and small break loss of coolant accidents (LOCA's) as well as the full range of operational transients. The emphasis of the RELAP5/MOD3 development will be on large break LOCA since previous versions of RELAP5 were developed for and assessed against small break LOCA and operation transient test data. The paper discusses the various code models to be improved and presents the results of work completed to date

The community's research and development programme on decommissioning of nuclear installations. Fourth annual progress report 1988

International Nuclear Information System (INIS)

Anon.

1989-01-01

This is the fourth annual progress report on the European Community's programme (1984-88) of research on the decommissioning of nuclear installations. It shows the status of the programme at 31 December 1988. The fourth progress report describes the objectives, scope and work programme of the 72 research contracts concluded, as well as the progress of work achieved and the results obtained in 1988

The Community's research and development programme on decommissioning of nuclear installations. Third annual progress report 1987

International Nuclear Information System (INIS)

1988-01-01

This is the third annual progress report of the European Community's programme (1984-88) of research on the decommissioning of nuclear installations. It shows the status of the programme on 31 December 1987. The third progress report describes the objectives, scope and work programme of the 69 research contracts concluded, as well as the progress of work achieved and the results obtained in 1987

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