WorldWideScience

Sample records for c-mod research programme

  1. Overview of Alcator C-Mod Research

    Science.gov (United States)

    White, A. E.

    2017-10-01

    Alcator C-Mod, a compact (R =0.68m, a =0.21m), high magnetic field, Bt Research spans the topics of core transport and turbulence, RF heating and current drive, pedestal physics, scrape-off layer, divertor and plasma wall interactions. In the last experimental campaign, Super H-mode was explored and featured the highest pedestal pressures ever recorded, pped 90 kPa (90% of ITER target), consistent with EPED predictions. Optimization of naturally ELM-suppressed EDA H-modes accessed the highest volume averaged pressures ever achieved (〈p〉>2 atm), with pped 60 kPa. The SOL heat flux width has been measured at Bpol = 1.25T, confirming the Eich scaling over a broader poloidal field range than before. Multi-channel transport studies focus on the relationship between momentum transport and heat transport with perturbative experiments and new multi-scale gyrokinetic simulation validation techniques were developed. U.S. Department of Energy Grant No. DE-FC02-99ER54512.

  2. Overview of the Alcator C-MOD Research Program

    International Nuclear Information System (INIS)

    Scott; S.; Bader, A.; Bakhtiari, M.; Basse, N.; Beck, W.; Biewer, T.; Bernabei, S.; Bonoli, P.

    2007-01-01

    Recent research on the high-field, high-density diverted Alcator C-MOD tokamak has focused on the plasma physics and plasma engineering required for ITER and for attractive fusion reactors. Experimental campaigns over the past two years have focused on understanding the physical mechanisms that affect the plasma performance realized with all-molybdenum walls versus walls with low-Z coatings. RF sheath rectification along flux tubes that intersect the RF antenna is found to be a major cause of localized boron erosion and impurity generation. Initial lower-hybrid current drive (LHCD) experiments (PLH p ∼ 1.0 MA with good efficiency, I drive = 0.4P LH /n eo R (MA,MW, 10 20 m -3 ,m). Disruption mitigation via massive gas-jet impurity puffing has proven successful at high plasma pressure, indicating this technique has promise for implementation on ITER. Pressure gradients in the near SOL of Ohmic L-mode plasmas are observed to scale consistently as I p 2 , and show a significant dependence on X-point topology. Modeling of H-mode edge fueling indicates high self-screening to neutrals in the pedestal and scrape-off layer (SOL), and reproduces experimental density pedestal response to changes in neutral source. Detailed measurements of the temperature and density profiles in the near sol and fast framing movies of the turbulent structures provide improved understanding of the mechanisms that control transport in the edge region.

  3. Overview of recent Alcator C-Mod research

    International Nuclear Information System (INIS)

    Marmar, E.S.; Bai, B.; Boivin, R.L.

    2003-01-01

    Research on the Alcator C-Mod tokamak is focused on high particle- and power-density plasma regimes to understand particle and energy transport in the core, the dynamics of the H-mode pedestal, and scrape-off layer and divertor physics. The auxiliary heating is provided exclusively by RF waves, and both the physics and technology of RF heating and current drive are studied. The momentum which is manifested in strong toroidal rotation, in the absence of direct momentum input, has been shown to be transported in from the edge of the plasma following the L to H transition, with time scale comparable to that for energy transport. In discharges which develop internal transport barriers (ITBs), the rotation slows first inside the barrier region, and then subsequently outside of the barrier foot. Heat pulse propagation studies using sawteeth indicate a very narrow region of strongly reduced energy transport, located near r/a = 0.5. Addition of on-axis ICRF heating arrests the buildup of density and impurities, leading to quasi-steady conditions. The quasi-coherent mode associated with EDA H-mode appears to be due to a resistive ballooning instability. As the pedestal pressure gradient and temperature are increased in EDA H-mode, small ELMs appear; detailed modeling indicates that these are due to intermediate n peeling-ballooning modes. Phase Contrast Imaging (PCI) has been used to directly detect density fluctuations driven by ICRF waves in the core of the plasma, and mode conversion to an intermediate wavelength Ion Cyclotron Wave has been observed for the first time. The bursty turbulent density fluctuations, observed to drive rapid cross-field particle transport in the edge plasma, appear to play a key role the dynamics of the density limit. Preparations for quasi-steady-state Advanced Tokamak studies with lower hybrid current drive are well underway, and time dependent modeling indicates that regimes with high bootstrap fraction can be produced. (author)

  4. Twenty Years of Research on the Alcator C-Mod Tokamak

    Science.gov (United States)

    Greenwald, Martin

    2013-10-01

    Alcator C-Mod is a compact, high-field tokamak, whose unique design and operating parameters have produced a wealth of new and important results since its start in 1993, contributing data that extended tests of critical physical models into new parameter ranges and into new regimes. Using only RF for heating and current drive with innovative launching structures, C-Mod operates routinely at very high power densities. Research highlights include direct experimental observation of ICRF mode-conversion, ICRF flow drive, demonstration of Lower-Hybrid current drive at ITER-like densities and fields and, using a set of powerful new diagnostics, extensive validation of advanced RF codes. C-Mod spearheaded the development of the vertical-target divertor and has always operated with high-Z metal plasma facing components--an approach adopted for ITER. C-Mod has made ground-breaking discoveries in divertor physics and plasma-material interactions at reactor-like power and particle fluxes and elucidated the critical role of cross-field transport in divertor operation, edge flows and the tokamak density limit. C-Mod developed the I-mode and EDA H-mode regimes which have high performance without large ELMs and with pedestal transport self-regulated by short-wavelength electromagnetic waves. C-Mod has carried out pioneering studies of intrinsic rotation and found that self-generated flow shear can be strong enough to significantly modify transport. C-Mod made the first quantitative link between pedestal temperature and H-mode performance, showing that the observed self-similar temperature profiles were consistent with critical-gradient-length theories and followed up with quantitative tests of nonlinear gyrokinetic models. Disruption studies on C-Mod provided the first observation of non-axisymmetric halo currents and non-axisymmetric radiation in mitigated disruptions. Work supported by U.S. DoE

  5. Highlights of the Alcator C-Mod Research Campaign

    Science.gov (United States)

    Greenwald, Martin; Alcator Team

    2011-10-01

    Alcator C-Mod has completed an experimental campaign focusing on broad scientific issues with particular emphasis on ITER needs and requests. Experiments with no NBI torque have investigated spontaneous flow reversal, creation of transport barriers aided by the shear of intrinsic rotation and a variety of RF flow drive schemes. Studies of I-mode have found conditions where a wide operating regime opens up, allowing easy access to long-lived, high-performance discharges with L-mode like particle confinement. We are validating the EPED and BOUT++ models for pedestal height/width and ELM onset using extended parameter scans in ELMy H-mode. The challenge of high-Z impurity generation with ICRF is being addressed first by deployment of a novel antenna whose current straps and antenna box are perpendicular to the total magnetic field -second by studies of the modification of edge impurity transport, where fine-scale Er structures in the SOL in the presence of ICRF heating have been found. LH current drive has produced non-inductive reversed shear regimes at n ~ 5x1019 which exhibit electron temperature ITBs. The first observations have been made of in-tokamak production of divertor tungsten nano-structures (fuzz), which had previously been seen only in linear laboratory experiments. Supported by DoE DE-FC02-99ER54512.

  6. 20 years of research on the Alcator C-Mod tokamak

    International Nuclear Information System (INIS)

    Greenwald, M.; Baek, S.; Barnard, H.; Beck, W.; Bonoli, P.; Brunner, D.; Burke, W.; Ennever, P.; Ernst, D.; Faust, I.; Fiore, C.; Fredian, T.; Gao, C.; Golfinopoulos, T.; Granetz, R.; Hartwig, Z.; Hubbard, A.; Hughes, J.; Hutchinson, I.; Irby, J.

    2014-01-01

    The object of this review is to summarize the achievements of research on the Alcator C-Mod tokamak [Hutchinson et al., Phys. Plasmas 1, 1511 (1994) and Marmar, Fusion Sci. Technol. 51, 261 (2007)] and to place that research in the context of the quest for practical fusion energy. C-Mod is a compact, high-field tokamak, whose unique design and operating parameters have produced a wealth of new and important results since it began operation in 1993, contributing data that extends tests of critical physical models into new parameter ranges and into new regimes. Using only high-power radio frequency (RF) waves for heating and current drive with innovative launching structures, C-Mod operates routinely at reactor level power densities and achieves plasma pressures higher than any other toroidal confinement device. C-Mod spearheaded the development of the vertical-target divertor and has always operated with high-Z metal plasma facing components—approaches subsequently adopted for ITER. C-Mod has made ground-breaking discoveries in divertor physics and plasma-material interactions at reactor-like power and particle fluxes and elucidated the critical role of cross-field transport in divertor operation, edge flows and the tokamak density limit. C-Mod developed the I-mode and the Enhanced Dα H-mode regimes, which have high performance without large edge localized modes and with pedestal transport self-regulated by short-wavelength electromagnetic waves. C-Mod has carried out pioneering studies of intrinsic rotation and demonstrated that self-generated flow shear can be strong enough in some cases to significantly modify transport. C-Mod made the first quantitative link between the pedestal temperature and the H-mode's performance, showing that the observed self-similar temperature profiles were consistent with critical-gradient-length theories and followed up with quantitative tests of nonlinear gyrokinetic models. RF research highlights include direct experimental

  7. 20 years of research on the Alcator C-Mod tokamaka)

    Science.gov (United States)

    Greenwald, M.; Bader, A.; Baek, S.; Bakhtiari, M.; Barnard, H.; Beck, W.; Bergerson, W.; Bespamyatnov, I.; Bonoli, P.; Brower, D.; Brunner, D.; Burke, W.; Candy, J.; Churchill, M.; Cziegler, I.; Diallo, A.; Dominguez, A.; Duval, B.; Edlund, E.; Ennever, P.; Ernst, D.; Faust, I.; Fiore, C.; Fredian, T.; Garcia, O.; Gao, C.; Goetz, J.; Golfinopoulos, T.; Granetz, R.; Grulke, O.; Hartwig, Z.; Horne, S.; Howard, N.; Hubbard, A.; Hughes, J.; Hutchinson, I.; Irby, J.; Izzo, V.; Kessel, C.; LaBombard, B.; Lau, C.; Li, C.; Lin, Y.; Lipschultz, B.; Loarte, A.; Marmar, E.; Mazurenko, A.; McCracken, G.; McDermott, R.; Meneghini, O.; Mikkelsen, D.; Mossessian, D.; Mumgaard, R.; Myra, J.; Nelson-Melby, E.; Ochoukov, R.; Olynyk, G.; Parker, R.; Pitcher, S.; Podpaly, Y.; Porkolab, M.; Reinke, M.; Rice, J.; Rowan, W.; Schmidt, A.; Scott, S.; Shiraiwa, S.; Sierchio, J.; Smick, N.; Snipes, J. A.; Snyder, P.; Sorbom, B.; Stillerman, J.; Sung, C.; Takase, Y.; Tang, V.; Terry, J.; Terry, D.; Theiler, C.; Tronchin-James, A.; Tsujii, N.; Vieira, R.; Walk, J.; Wallace, G.; White, A.; Whyte, D.; Wilson, J.; Wolfe, S.; Wright, G.; Wright, J.; Wukitch, S.; Zweben, S.

    2014-11-01

    The object of this review is to summarize the achievements of research on the Alcator C-Mod tokamak [Hutchinson et al., Phys. Plasmas 1, 1511 (1994) and Marmar, Fusion Sci. Technol. 51, 261 (2007)] and to place that research in the context of the quest for practical fusion energy. C-Mod is a compact, high-field tokamak, whose unique design and operating parameters have produced a wealth of new and important results since it began operation in 1993, contributing data that extends tests of critical physical models into new parameter ranges and into new regimes. Using only high-power radio frequency (RF) waves for heating and current drive with innovative launching structures, C-Mod operates routinely at reactor level power densities and achieves plasma pressures higher than any other toroidal confinement device. C-Mod spearheaded the development of the vertical-target divertor and has always operated with high-Z metal plasma facing components—approaches subsequently adopted for ITER. C-Mod has made ground-breaking discoveries in divertor physics and plasma-material interactions at reactor-like power and particle fluxes and elucidated the critical role of cross-field transport in divertor operation, edge flows and the tokamak density limit. C-Mod developed the I-mode and the Enhanced Dα H-mode regimes, which have high performance without large edge localized modes and with pedestal transport self-regulated by short-wavelength electromagnetic waves. C-Mod has carried out pioneering studies of intrinsic rotation and demonstrated that self-generated flow shear can be strong enough in some cases to significantly modify transport. C-Mod made the first quantitative link between the pedestal temperature and the H-mode's performance, showing that the observed self-similar temperature profiles were consistent with critical-gradient-length theories and followed up with quantitative tests of nonlinear gyrokinetic models. RF research highlights include direct experimental

  8. Alcator C-Mod Tokamak

    Data.gov (United States)

    Federal Laboratory Consortium — Alcator C-Mod at the Massachusetts Institute of Technology is operated as a DOE national user facility. Alcator C-Mod is a unique, compact tokamak facility that uses...

  9. Tungsten impurity transport experiments in Alcator C-Mod to address high priority research and development for ITER

    Energy Technology Data Exchange (ETDEWEB)

    Loarte, A.; Polevoi, A. R.; Hosokawa, M. [ITER Organization, Route de Vinon-sur-Verdon, CS 90 046, 13067 St Paul Lez Durance Cedex (France); Reinke, M. L. [York Plasma Institute, Department of Physics, University of York, Heslington, York YO10 5DD (United Kingdom); Chilenski, M.; Howard, N.; Hubbard, A.; Hughes, J. W.; Rice, J. E.; Walk, J. [Plasma Science and Fusion Center, Massachusetts Institute of Technology, Cambridge, Massachusetts 02139 (United States); Köchl, F. [Technische Universität Wien, Atominstitut, Stadionallee 2, 1020 Vienna (Austria); Pütterich, T.; Dux, R. [Max-Planck-Institut für Plasmaphysik, Boltzmanstraße 2, D-85748 Garching (Germany); Zhogolev, V. E. [NRC “Kurchatov Institute,” Kurchatov Square 1, 123098 Moscow (Russian Federation)

    2015-05-15

    Experiments in Alcator C-Mod tokamak plasmas in the Enhanced D-alpha H-mode regime with ITER-like mid-radius plasma density peaking and Ion Cyclotron Resonant heating, in which tungsten is introduced by the laser blow-off technique, have demonstrated that accumulation of tungsten in the central region of the plasma does not take place in these conditions. The measurements obtained are consistent with anomalous transport dominating tungsten transport except in the central region of the plasma where tungsten transport is neoclassical, as previously observed in other devices with dominant neutral beam injection heating, such as JET and ASDEX Upgrade. In contrast to such results, however, the measured scale lengths for plasma temperature and density in the central region of these Alcator C-Mod plasmas, with density profiles relatively flat in the core region due to the lack of core fuelling, are favourable to prevent inter and intra sawtooth tungsten accumulation in this region under dominance of neoclassical transport. Simulations of ITER H-mode plasmas, including both anomalous (modelled by the Gyro-Landau-Fluid code GLF23) and neoclassical transport for main ions and tungsten and with density profiles of similar peaking to those obtained in Alcator C-Mod show that accumulation of tungsten in the central plasma region is also unlikely to occur in stationary ITER H-mode plasmas due to the low fuelling source by the neutral beam injection (injection energy ∼ 1 MeV), which is in good agreement with findings in the Alcator C-Mod experiments.

  10. The alcator C-MOD control system

    International Nuclear Information System (INIS)

    Bosco, J.; Fairfax, S.

    1992-01-01

    The Alcator C-MOD experiment includes over 30 engineering and diagnostic subsystems. The control system hardware and software is a mixture of custom and commercial products which includes sensors, signal conditioners, hard-wired controls, programmable logic controllers, displays, a hybrid analog/digital computer, networked personal computers, and networked VAX workstations. This paper describes the computer-based portions of the control system. The control system coordinates all C-MOD systems including power, vacuum, heating and cooling, access control, plasma shape and position control, and diagnostics. Programmable logic controllers (PLC's) are located near each subsystem. The control room is isolated by fiber optics. Functions that are essential to personnel or equipment safety (e.g. access control) are implemented in hardwired logic and monitored but not controlled by the PLC's. The initial configuration will include over 25 Allen-Bradley PLC-5 units. The PLCs in each subsystem are connected to personal computers (PC's) in the control room. The PC's provide graphical displays and operator interface. The Pc's are networked and share process data with each other and with a master control console and a large mimic panel

  11. Alcator C-MOD proposal addendum

    International Nuclear Information System (INIS)

    Bonoli, P.; Greenwald, M.; Gwinn, D.

    1986-04-01

    Since the design concept and overall purpose of the Alcator C-MOD device are similar to that proposed in October 1985, we have chosen in this document only to highlight areas where changes or additions have been made. Chapters in the Addendum correspond to those in the Proposal, except Chapter 9 which describes a number of toroidal improvement concepts which are being considered for inclusion in the Alcator C-MOD experimental program. A description of the redesign and a discussion of the objectives of the experimental program are given

  12. The LHCD Launcher for Alcator C-Mod - Design, Construction, Calibration and Testing

    International Nuclear Information System (INIS)

    Hosea, J.; Beals, D.; Beck, W.; Bernabei, S.; Burke, W.; Childs, R.; Ellis, R.; Fredd, E.; Greenough, N.; Grimes, M.; Gwinn, D.; Irby, J.; Jurczynski, S.; Koert, P.; Kung, C.C.; Loesser, G.D.; Marmar, E.; Parker, R.; Rushinski, J.; Schilling, G.; Terry, D.; Vieira, R.; Wilson, J.R.; Zaks, J.

    2005-01-01

    MIT and PPPL have joined together to fabricate a high-power lower hybrid current drive (LHCD) system for supporting steady-state AT regime research on Alcator C-Mod. The goal of the first step of this project is to provide 1.5 MW of 4.6 GHz rf [radio frequency] power to the plasma with a compact launcher which has excellent spectral selectivity and fits into a single C-Mod port. Some of the important design, construction, calibration and testing considerations for the launcher leading up to its installation on C-Mod are presented here

  13. Alcator C-MOD final safety analysis

    International Nuclear Information System (INIS)

    Fiore, C.L.

    1989-06-01

    This document is designed to address the safety issues involved with the Alcator C-Mod project. This report will begin with a brief description of the experimental objectives which will be followed by information concerning the site. The Alcator C-Mod experiment is a pulsed fusion experiment in which a plasma formed from small amounts of hydrogen or deuterium gas is confined in a magnetic field for short periods (∼1 s). No radioactive fuels or fissile materials are used in the device, so that no criticality hazard exists and no credible nuclear accident can occur. During deuterium operation, the production of a small number of neutrons from a short pulse could result in a small amount of short- and intermediate-lived radioactive isotopes being produced inside the experimental cell. This report will demonstrate that this does not pose an additional hazard to the general population. The health and safety hazards resulting from Alcator C-Mod occur to the workers on the experiment, each of which is described in its own chapter with the steps taken to minimize the risk to employees. These hazards include fire, chemicals and cryogenics, air quality, electrical, electromagnetic radiation, ionizing radiation, and mechanical and natural phenomena. None of these hazards is unique to the facility, and methods of protection from them are well defined and are discussed in the chapter which describes each hazard. The quality assurance program, critical to ensuring the safety aspects of the program, will also be described

  14. 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.

  15. 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.

  16. 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

  17. 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)

  18. Gas jet disruption mitigation studies on Alcator C-Mod

    International Nuclear Information System (INIS)

    Granetz, R.; Whyte, D.G.; Izzo, V.A.; Biewer, T.; Reinke, M.L.; Terry, J.; Bader, A.; Bakhtiari, M.; Jernigan, T.; Wurden, G.

    2006-01-01

    Damaging effects of disruptions are a major concern for Alcator C-Mod, ITER and future tokamak reactors. High-pressure noble gas jet injection is a mitigation technique which potentially satisfies the operational requirements of fast response time and reliability, while still being benign to subsequent discharges. Disruption mitigation experiments using an optimized gas jet injection system are being carried out on Alcator C-Mod to study the physics of gas jet penetration into high pressure plasmas, as well as the ability of the gas jet impurities to convert plasma energy into radiation on timescales consistent with C-Mod's fast quench times, and to reduce halo currents given C-Mod's high-current density. The dependence of impurity penetration and effectiveness on noble gas species (He, Ne, Ar, Kr) is also being studied. It is found that the high-pressure neutral gas jet does not penetrate deeply into the C-Mod plasma, and yet prompt core thermal quenches are observed on all gas jet shots. 3D MHD modelling of the disruption physics with NIMROD shows that edge cooling of the plasma triggers fast growing tearing modes which rapidly produce a stochastic region in the core of the plasma and loss of thermal energy. This may explain the apparent effectiveness of the gas jet in C-Mod despite its limited penetration. The higher-Z gases (Ne, Ar, Kr) also proved effective at reducing halo currents and decreasing thermal deposition to the divertor surfaces. In addition, noble gas jet injection proved to be benign for plasma operation with C-Mod's metal (Mo) wall, actually improving the reliability of the startup in the following discharge

  19. 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!”

  20. 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.

  1. 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.

  2. 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

  3. 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.

  4. 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

  5. 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

  6. 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, ...

  7. 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

  8. 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

  9. Nonaxisymmetric field effects on Alcator C-Mod

    International Nuclear Information System (INIS)

    Wolfe, S.M.; Hutchinson, I.H.; Granetz, R.S.; Rice, J.; Hubbard, A.; Lynn, A.; Phillips, P.; Hender, T.C.; Howell, D.F.; La Haye, R.J.; Scoville, J.T.

    2005-01-01

    A set of external coils (A-coils) capable of producing nonaxisymmetric, predominantly n=1, fields with different toroidal phase and a range of poloidal mode m spectra has been used to determine the threshold amplitude for mode locking over a range of plasma parameters in Alcator C-Mod [I. H. Hutchinson, R. Boivin, F. Bombarda, P. Bonoli, S. Fairfax, C. Fiore, J. Goetz, S. Golovato, R. Granetz, M. Greenwald et al., Phys. Plasmas 1, 1511 (1994)]. The threshold perturbations and parametric scalings, expressed in terms of (B 21 /B T ), are similar to those observed on larger, lower field devices. The threshold is roughly linear in density, with typical magnitudes of order 10 -4 . This result implies that locked modes should not be significantly more problematic for the International Thermonuclear Experimental Reactor [I. P. B. Editors, Nucl. Fusion 39, 2286 (1999)] than for existing devices. Coordinated nondimensional identity experiments on the Joint European Torus [Fusion Technol. 11, 13 (1987)], DIII-D [Fusion Technol. 8, 441 (1985)], and C-Mod, with matching applied mode spectra, have been carried out to determine more definitively the field and size scalings. Locked modes on C-Mod are observed to result in braking of core toroidal rotation, modification of sawtooth activity, and significant reduction in energy and particle confinement, frequently leading to disruptions. Intrinsic error fields inferred from the threshold studies are found to be consistent in amplitude and phase with a comprehensive model of the sources of field errors based on 'as-built' coil and bus-work details and coil imperfections inferred from measurements using in situ magnetic diagnostics on dedicated test pulses. Use of the A-coils to largely cancel the 2/1 component of the intrinsic nonaxisymmetric field has led to expansion of the accessible operating space in C-Mod, including operation up to 2 MA plasma current at 8 T

  10. Rotation and transport in Alcator C-Mod ITB plasmas

    Science.gov (United States)

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

    2010-06-01

    Internal transport barriers (ITBs) are seen under a number of conditions in Alcator C-Mod plasmas. Most typically, radio frequency power in the ion cyclotron range of frequencies (ICRFs) is injected with the second harmonic of the resonant frequency for minority hydrogen ions positioned off-axis at r/a > 0.5 to initiate the ITBs. They can also arise spontaneously in ohmic H-mode plasmas. These ITBs typically persist tens of energy confinement times until the plasma terminates in radiative collapse or a disruption occurs. All C-Mod core barriers 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. The strongly co-current intrinsic central plasma rotation that is observed following the H-mode transition has a profile that is peaked in the centre of the plasma and decreases towards the edge if the ICRF power deposition is in the plasma centre. When the ICRF resonance is placed off-axis, the rotation develops a well in the core region. The central rotation continues to decrease as long as the central density peaks when an ITB develops. This rotation profile is flat in the centre (0 ITB density profile is observed (0.5 ITB foot that is sufficiently large to stabilize ion temperature gradient instabilities that dominate transport in C-Mod high density plasmas.

  11. 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

  12. 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

  13. 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

  14. 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

  15. 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

  16. 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.

  17. 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.

  18. 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

  19. 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)

  20. 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

  1. 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.

  2. 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.

  3. 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.

  4. 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

  5. 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.

  6. 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

  7. 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.

  8. 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

  9. 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...

  10. 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...

  11. Flux-driven turbulence GDB simulations of the IWL Alcator C-Mod L-mode edge compared with experiment

    Science.gov (United States)

    Francisquez, Manaure; Zhu, Ben; Rogers, Barrett

    2017-10-01

    Prior to predicting confinement regime transitions in tokamaks one may need an accurate description of L-mode profiles and turbulence properties. These features determine the heat-flux width upon which wall integrity depends, a topic of major interest for research aid to ITER. To this end our work uses the GDB model to simulate the Alcator C-Mod edge and contributes support for its use in studying critical edge phenomena in current and future tokamaks. We carried out 3D electromagnetic flux-driven two-fluid turbulence simulations of inner wall limited (IWL) C-Mod shots spanning closed and open flux surfaces. These simulations are compared with gas puff imaging (GPI) and mirror Langmuir probe (MLP) data, examining global features and statistical properties of turbulent dynamics. GDB reproduces important qualitative aspects of the C-Mod edge regarding global density and temperature profiles, within reasonable margins, and though the turbulence statistics of the simulated turbulence follow similar quantitative trends questions remain about the code's difficulty in exactly predicting quantities like the autocorrelation time A proposed breakpoint in the near SOL pressure and the posited separation between drift and ballooning dynamics it represents are examined This work was supported by DOE-SC-0010508. This research used resources of the National Energy Research Scientific Computing Center (NERSC).

  12. 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

  13. 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

  14. 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.

  15. 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.))

  16. 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

  17. 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

  18. 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.

  19. 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)

  20. Three-dimensional Simulation of Gas Conductance Measurement Experiments on Alcator C-Mod

    International Nuclear Information System (INIS)

    Stotler, D.P.; LaBombard, B.

    2004-01-01

    Three-dimensional Monte Carlo neutral transport simulations of gas flow through the Alcator C-Mod subdivertor yield conductances comparable to those found in dedicated experiments. All are significantly smaller than the conductance found with the previously used axisymmetric geometry. A benchmarking exercise of the code against known conductance values for gas flow through a simple pipe provides a physical basis for interpreting the comparison of the three-dimensional and experimental C-Mod conductances

  1. 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

  2. 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...

  3. Research programme on radioactive wastes

    International Nuclear Information System (INIS)

    Eckhardt, A.; Hufschmid, P.; Jordi, S.; Schanne, M.; Vigfusson, J.

    2009-11-01

    This report for the Swiss Federal Department of the Environment, Transport, Energy and Communication (DETEC) takes a look at work done within the framework of the research programme on radioactive wastes. The paper discusses the development of various projects and the associated organisations involved. Both long-term and short-term topics are examined. The long-term aspects of handling radioactive wastes include organisation and financing as well as the preservation of know-how and concepts for marking the repositories. Communication with the general public on the matter is looked at along with public perception, opinion-making and acceptance. Waste storage concepts are looked at in detail and aspects such as environmental protection, monitoring concepts, retrievability and encasement materials are discussed. Finally, ethical and legal aspects of radioactive waste repositories are examined. The paper is completed with appendixes dealing with planning, co-ordination and the responsibilities involved

  4. 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.)

  5. Disruption Warning Database Development and Exploratory Machine Learning Studies on Alcator C-Mod

    Science.gov (United States)

    Montes, Kevin; Rea, Cristina; Granetz, Robert

    2017-10-01

    A database of about 1800 shots from the 2015 campaign on the Alcator C-Mod tokamak is assembled, including disruptive and non-disruptive discharges. The database consists of 40 relevant plasma parameters with data taken from 160k time slices. In order to investigate the possibility of developing a robust disruption prediction algorithm that is tokamak-independent, we focused machine learning studies on a subset of dimensionless parameters such as βp, n /nG , etc. The Random Forests machine learning algorithm provides insight on the available data set by ranking the relative importance of the input features. Its application on the C-Mod database, however, reveals that virtually no one parameter has more importance than any other, and that its classification algorithm has a low rate of successfully predicted samples, as well as poor false positive and false negative rates. Comparing the analysis of this algorithm on the C-Mod database with its application to a similar database on DIII-D, we conclude that disruption prediction may not be feasible on C-Mod. This conclusion is supported by empirical observations that most C-Mod disruptions are caused by radiative collapse due to molybdenum from the first wall, which happens on just a 1-2ms timescale. Supported by the US Dept. of Energy under DE-FC02-99ER54512 and DE-FC02-04ER54698.

  6. Summer Research Fellowship Programme 2018

    Indian Academy of Sciences (India)

    Date of birth: 2 September 1957. Specialization: Cosmic Magnetic Fields, Structure Formation, Cosmology Address: Distinguished Professor & Dean, Visitor Academic Programmes, Inter-University Centre for Astronomy & Astrophysics, Post Bag 4, Ganeshkhind, Pune 411 007, Maharashtra Contact: Office: (020) 2560 4101

  7. 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.

  8. 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)

  9. 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

  10. 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...

  11. 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 ...

  12. 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)

  13. 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)

  14. 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)

  15. 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] .

  16. Summer Research Fellowship Programme 2018

    Indian Academy of Sciences (India)

    Date of birth: 25 June 1941. Specialization: Nuclear Magnetic Resonance Spectroscopy, NMR Techniques & its Applications to Biomolecules and Quantum Computing Address: Department of Physics, NMR Research Centre, Indian Institute of Science, Bengaluru 560 012, Karnataka Contact: Office: (080) 2293 2724

  17. 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)

  18. 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.

  19. 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

  20. 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.

  1. 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...

  2. 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.

  3. Research programme 1978-1980

    International Nuclear Information System (INIS)

    1979-01-01

    Description of basic and application-minded research projects on dispersion and transport processes in flows: A) Turbulent diffusion processes in bodies of water, B) transport processes in bodies of water, C) diffusion and transport processes in dammed-up water and groundwater, D) development of new methods of measurement for turbulent flows. (GL) [de

  4. 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

  5. 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)

  6. 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.

  7. 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

  8. 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

  9. 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

  10. 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

  11. Plutonium contaminated materials research programme

    International Nuclear Information System (INIS)

    Higson, S.G.

    1986-01-01

    The paper is a progress report for 1985 from the Plutonium Contaminated Materials Working Party (PCMWP). The PCMWP co-ordinates research and development on a national basis in the areas of management, treatment and immobilisation of plutonium contaminated materials, for the purpose of waste management. The progress report contains a review of the development work carried out in eight areas, including: reduction of arisings, plutonium measurement, sorting and packaging, washing of shredded combustible PCM, decommissioning and non-combustible PCM treatment, PCM immobilisation, treatment of alpha bearing liquid wastes, and engineering objectives. (UK)

  12. 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 ...

  13. 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...

  14. 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)

  15. 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

  16. 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.

  17. 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...

  18. 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.

  19. Electron Temperature Fluctuation Measurements and Transport Model Validation at Alcator C-Mod

    Energy Technology Data Exchange (ETDEWEB)

    White, Anne [Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)

    2017-06-22

    for studying core turbulence are needed in order to assess the accuracy of gyrokinetic models for turbulent-driven particle, heat and momentum transport. New core turbulence diagnostics at the world-class tokamaks Alcator C-Mod at MIT and ASDEX Upgrade at the Max Planck Institute for Plasma Physics have been designed, developed, and operated over the course of this project. These new instruments are capable of measuring electron temperature fluctuations and the phase angle between density and temperature fluctuations locally and quantitatively. These new data sets from Alcator C-Mod and ASDEX Upgrade are being used to fill key gaps in our understanding of turbulent transport in tokamaks. In particular, this project has results in new results on the topics of the Transport Shortfall, the role of ETG turbulence in tokamak plasmas, profile stiffness, the LOC/SOC transition, and intrinsic rotation reversals. These data are used in a rigorous process of “Transport model validation”, and this group is a world-leader on using turbulence models to design new hardware and new experiments at tokamaks. A correlation electron cyclotron emission (CECE) diagnostic is an instrument used to measure micro-scale fluctuations (mm-scale, compared to the machine size of meters) of electron temperature in magnetically confined fusion plasmas, such as those in tokamaks and stellarators. These micro-scale fluctuations are associated with drift-wave type turbulence, which leads to enhanced cooling and mixing of particles in fusion plasmas and limits achieving the required temperatures and densities for self-sustained fusion reactions. A CECE system can also be coupled with a reflectometer system that measured micro-scale density fluctuations, and from these simultaneous measurements, one can extract the phase between the density (n) and temperature (T) fluctuations, creating an nT phase diagnostic. Measurements of the fluctuations and the phase angle between them are extremely useful for

  20. 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

  1. 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)

  2. 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

  3. 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

  4. 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.

  5. 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)

  6. 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.

  7. 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.

  8. 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

  9. 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.

  10. 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)

  11. 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.)

  12. 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)

  13. 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.

  14. 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

  15. 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)

  16. 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)

  17. 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.

  18. 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)

  19. 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).

  20. 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)

  1. 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

  2. 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.

  3. 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.

  4. 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

  5. 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.

  6. 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.

  7. 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.

  8. 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.

  9. 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.

  10. 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

  11. 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...

  12. 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.

  13. Nirex Safety Assessment Research Programme bibliography, 1988

    International Nuclear Information System (INIS)

    Cooper, M.J.

    1988-05-01

    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. All work referred to has been funded, or partly funded, by UK Nirex Limited, previously known as the Nuclear Industry Radioactive Waste Executive (NIREX). The bibliography has been divided into two sections, a List of Publications in roughly chronological order and an Author Index. The topics involved include near-field and far-field studies. The near-field includes the waste, its immobilising medium, its container, the engineered structure in which the containers are emplaced, and the immediately adjacent geological formation disturbed by the construction of the repository. The far-field is the undisturbed geological formation between the near-field and the biosphere. (author)

  14. Nirex Safety Assessment Research Programme bibliography, 1987

    International Nuclear Information System (INIS)

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

    1987-06-01

    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). All work referred to has been funded, or partly funded, by UK Nirex Limited, previously known as the Nuclear Industry Radioactive Waste Executive (NIREX). The bibliography has been divided into two sections, a List of Publications in roughly chronological order and an Author Index. The topics involved include near-field and far-field studies. The near-field includes the waste, its immobilising medium, its container, the engineered structure in which the containers are emplaced, and the immediately adjacent geological formation disturbed by the construction of the repository. The far-field is the undisturbed geological formation between the near-field and the biosphere. (author)

  15. Overview of the Electricity Research Programme 2002

    Energy Technology Data Exchange (ETDEWEB)

    Brueniger, R.

    2003-07-01

    This publication of the Swiss Federal Office of Energy (SFOE) presents a review in English of the SFOE's Electricity Research Programme's main areas of activity in 2002. These include electricity distribution, high-temperature superconductors, energy and information technology, electric drives and motors and appliances. Tasks accomplished and results obtained are quoted. In the electricity distribution area these include educational topics, modelling of power lines, independent energy producers and corrosion in pipelines caused by alternating current. High-temperature superconductors, their impact and market impact are discussed. In the energy and information area, a competence centre is introduced, the energy efficiency of computer networks is looked at, including documentation for requests for tender for personal computers. Also, uninterruptible power supplies are looked at. Further the efficiency of an 'intelligent' house is reviewed and the power consumption of process control units is examined. As far as drives and electric motors are concerned, an industry convention is examined and work in the European Motor Challenge Programme is looked at. Gearless drives are looked at as are energy-efficient motors in general. In the devices area, topics range from heat-pump tumble-dryers, the GreenLight Contact Points project, electric band heaters and the optimal use of energy in refrigerated water, beverage and food dispensers as well as in dispensers providing hot drinks. The stand-by consumption of household appliances is also discussed. National and international co-operation is reviewed and various pilot and demonstration projects in the above-mentioned areas are briefly presented. The report is completed with a list of research and development projects and a list of pilot and demonstration work.

  16. ONKALO. Underground characterisation and research programme (UCRP)

    International Nuclear Information System (INIS)

    2003-09-01

    The purpose of the ONKALO Underground Characterisation and Research Programme (UCRP) is to explore Olkiluoto rock conditions and thereby enhance the current geoscientific understanding of the site, to allow the submission of an application for a construction licence for the deep repository. The characterisation programme has the following geoscientific goals: to develop and demonstrate techniques for detailed characterising volumes of rock from the underground, to update the current descriptive model of Olkiluoto bedrock and to increase confidence in this model such that it will serve the needs of construction and the Preliminary Safety Assessment Report (PSAR) in the construction licence application, and to identify volumes of rock that could be suitable for housing parts of the repository. The development of ONKALO will be based on coordinated investigation, design and construction activities. Mapping data from the tunnel front and data obtained from short probe holes will constitute most of the data needed to control the construction of ONKALO. Pilot holes will be drilled along the tunnel profile as the excavation proceeds and investigations will be carried out for geological, rock mechanics, hydrogeological and hydrogeochemical characterisation. Investigations cover more detailed mapping and sampling in parts of the tunnel, mapping and sampling of potential groundwater inflows to the tunnel and investigations from characterisation bore holes drilled from ONKALO. In addition, monitoring is planned in surface-drilled boreholes, in boreholes drilled from ONKALO, and in ONKALO itself. Monitoring will reveal changes in bedrock conditions and thus provide important information for site characterisation. The information collected by characterisation and monitoring will all be assessed in an integrated modelling effort. The aim of this modelling is both to successively enhance the description and understanding of the rock volume around ONKALO and to assess potential

  17. 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.)

  18. 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 ...

  19. 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.).

  20. 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...

  1. 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

  2. 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

  3. Southern Ocean - South African cooperative research programme.

    CSIR Research Space (South Africa)

    SANCOR

    1979-05-01

    Full Text Available and elsewhere- and to ensure the most efficient possible utilization of limited manpower and facilities, a national programme had to be formulated to achieve the required coordination and cooperation. Such a programme is presented in this report, compiled...

  4. Nirex safety assessment research programme bibliography, 1991

    International Nuclear Information System (INIS)

    Cooper, M.J.

    1991-09-01

    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. The bibliography has been divided into two sections, a list of Publications in roughly chronological order and an Author Index. The topics involved include near-field and far-field studies. The near-field includes the waste package, filling or sealing materials, and those parts of the host medium whose characteristics have been or could be altered by the repository or its content. The far-field is the rock formation outside the repository, including the surrounding strata, at a distance from the waste disposal site such that, for modelling purposes, the site may be considered as a single entity, and the effects of individual waste packages are indistinguishable in the effects of the whole. The far-field includes also the biosphere, into which radionuclides from the waste could conceivably migrate in the future. (author)

  5. 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.

  6. 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

  7. 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)

  8. 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

  9. 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.

  10. 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.

  11. 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.

  12. 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.

  13. 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.

  14. 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

  15. 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

  16. 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

  17. 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

  18. 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)

  19. 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

  20. 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.

  1. 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.

  2. 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.

  3. 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.

  4. 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)

  5. 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.

  6. 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.

  7. 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.

  8. 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)

  9. 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.)

  10. 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

  11. 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)

  12. 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.

  13. 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...

  14. GSI research and development programme 1992 (including programme budget)

    International Nuclear Information System (INIS)

    1992-01-01

    The main points on UNILAC will be preparatory experiments on the synthesis of the element 110 and the study of e + e 1 - pair generation for heavy ion impacts on the Coulomb barrier. Experiments on beam fragmentation, to generate and apply radioactive beams and for producing mesons and antiprotons below the threshold will be to the fore at SIS. The central detector of the 4 π detector for exclusive particle production studies will also be set to work. Up to now, the electron cooling and storage experiments have shown, in the main, how heavy ion beams such as 20 Ne, 40 Ar, 86 Kr, 136 Xe and 209 Bi are stored and can be cooled with electron beams to the highest phase space densities (Δ p/p ≅ 10 -6 , ε ≅ 0.3 π mm x mrad). The cooling experiments will be continued, particularly in order to research the conditions for beam condensation. In a series of experiments, electron-ion and laser-ion interaction processes such as radiation capture, dielectric recombination and laser-induced transitions are examined. Spectroscopy experiments on hydrogen- and helium-like heavy atoms to examined QED effects are being started. (orig.) [de

  15. 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

  16. 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.

  17. 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

  18. 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)

  19. The design and performance of a twenty barrel hydrogen pellet injector for Alcator C-Mod

    International Nuclear Information System (INIS)

    Urbahn, J.A.

    1994-05-01

    A twenty barrel hydrogen pellet injector has been designed, built and tested both in the laboratory and on the Alcator C-Mod Tokamak at MIT. The injector functions by firing pellets of frozen hydrogen or deuterium deep into the plasma discharge for the purpose of fueling the plasma, modifying the density profile and increasing the global energy confinement time. The design goals of the injector are: (1) Operational flexibility, (2) High reliability, (3) Remote operation with minimal maintenance. These requirements have lead to a single stage, pipe gun design with twenty barrels. Pellets are formed by in- situ condensation of the fuel gas, thus avoiding moving parts at cryogenic temperatures. The injector is the first to dispense with the need for cryogenic fluids and instead uses a closed cycle refrigerator to cool the thermal system components. The twenty barrels of the injector produce pellets of four different size groups and allow for a high degree of flexibility in fueling experiments. Operation of the injector is under PLC control allowing for remote operation, interlocked safety features and automated pellet manufacturing. The injector has been extrusively tested and shown to produce pellets reliably with velocities up to 1400 m/sec. During the period from September to November of 1993, the injector was successfully used to fire pellets into over fifty plasma discharges. Experimental results include data on the pellet penetration into the plasma using an advanced pellet tracking diagnostic with improved time and spatial response. Data from the tracker indicates pellet penetrations were between 30 and 86 percent of the plasma minor radius

  20. 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 (ℓp 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.

  1. H-mode regimes and observators of central toroidal rotation in Alcator C-Mod

    International Nuclear Information System (INIS)

    Greenwald, M.; Rice, J.; Boivin, R.

    1999-01-01

    The Enhanced D α or EDA H-mode regime in Alcator C-Mod has been investigated and compared in detail to ELM-free plasmas. (In this paper, ELM-free will refer to discharges with no type I ELMs and with no sign of EDA, though technically, most EDA plasmas are ELM-free as well.) EDA discharges have only slightly lower energy confinement than comparable ELM-free ones, but show markedly reduced impurity confinement. Thus EDA discharges do not accumulate impurities and typically have a lower fraction of radiated power. EDA plasmas are seen to be more likely at low plasma current (q > 3.7 - 4), for moderate plasma shaping (0.35 - 0.55), and for high neutral pressures. No obvious trends were observed with input power or pressure (β). In both H-mode regimes, and in ICRF heated L-modes, central impurity toroidal rotation has been deduced, from the Doppler shifts of argon x-ray lines. Rotation velocities up to 1.3 x 10 5 m/s in the co-current direction have been observed in H-mode discharges that had no direct momentum input. There is a strong correlation between the increase in the central impurity rotation velocity and the increase in the plasma stored energy, induced by ICRF heating. In otherwise similar discharges with the same stored energy increase, plasmas with lower current rotate faster. The ion pressure gradient is an unimportant contributor to the central impurity rotation and the presence of a substantial core radial electric field is inferred during the ICRF pulse. An inward shift of ions induced by ICRF waves could give rise to a non-ambipolar electric field in the plasma core. Comparisons with a neo-classical ion orbit shift model show good agreement with the observations, both in magnitude, and in the scaling with plasma current. (author)

  2. Lower hybrid wave edge power loss quantification on the Alcator C-Mod tokamak

    Science.gov (United States)

    Faust, I. C.; Brunner, D.; LaBombard, B.; Parker, R. R.; Terry, J. L.; Whyte, D. G.; Baek, S. G.; Edlund, E.; Hubbard, A. E.; Hughes, J. W.; Kuang, A. Q.; Reinke, M. L.; Shiraiwa, S.; Wallace, G. M.; Walk, J. R.

    2016-05-01

    For the first time, the power deposition of lower hybrid RF waves into the edge plasma of a diverted tokamak has been systematically quantified. Edge deposition represents a parasitic loss of power that can greatly impact the use and efficiency of Lower Hybrid Current Drive (LHCD) at reactor-relevant densities. Through the use of a unique set of fast time resolution edge diagnostics, including innovative fast-thermocouples, an extensive set of Langmuir probes, and a Lyα ionization camera, the toroidal, poloidal, and radial structure of the power deposition has been simultaneously determined. Power modulation was used to directly isolate the RF effects due to the prompt ( t Radiofrequency (LHRF) power. LHRF power was found to absorb more strongly in the edge at higher densities. It is found that a majority of this edge-deposited power is promptly conducted to the divertor. This correlates with the loss of current drive efficiency at high density previously observed on Alcator C-Mod, and displaying characteristics that contrast with the local RF edge absorption seen on other tokamaks. Measurements of ionization in the active divertor show dramatic changes due to LHRF power, implying that divertor region can be a key for the LHRF edge power deposition physics. These observations support the existence of a loss mechanism near the edge for LHRF at high density ( n e > 1.0 × 10 20 (m-3)). Results will be shown addressing the distribution of power within the SOL, including the toroidal symmetry and radial distribution. These characteristics are important for deducing the cause of the reduced LHCD efficiency at high density and motivate the tailoring of wave propagation to minimize SOL interaction, for example, through the use of high-field-side launch.

  3. 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

  4. 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.

  5. 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

  6. 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

  7. 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.

  8. 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.

  9. Loyalty Programmes : Current Knowledge and Research Directions

    NARCIS (Netherlands)

    Dorotic, Matilda; Bijmolt, Tammo H. A.; Verhoef, Peter C.

    Loyalty programmes (LPs) have increased in number and popularity, but their effects on customer behaviour remain equivocal, due to a lack of understanding of the drivers of LP effectiveness and insufficient generalizable conclusions across prior studies. This paper synthesizes current knowledge

  10. 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

  11. 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

  12. 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

  13. 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

  14. 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.)

  15. 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

  16. 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.

  17. 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

  18. 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)

  19. 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)

  20. 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.

  1. 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.

  2. Research reactor utilization in chemistry programmes

    International Nuclear Information System (INIS)

    Bautista, E.

    1983-01-01

    The establishment and roles of the Philippines Atomic Energy Commission in promoting and regulating the use of atomic energy are explained. The research reactor, PRR-1 is being converted to TRIGA to meet the increasing demands of high-flux. The activities of PAEC in chemistry research programs utilizing reactor are discussed in detail. The current and future plans of Research and Development programs are also included. (A.J.)

  3. A proposed programme for energy risk research

    International Nuclear Information System (INIS)

    1979-01-01

    The report consists of two parts. Part I presents an overview of technological risk management, noting major contributions and current research needs. Part II details a proposed program of energy research, including discussions of some seven recommended projects. The proposed energy risk research program addresses two basic problem areas: improving the management of energy risks and energy risk communication and public response. Specific recommended projects are given for each. (Auth.)

  4. 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.)

  5. 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.))

  6. 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.

  7. 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

  8. Research interface on a programmable ultrasound scanner.

    Science.gov (United States)

    Shamdasani, Vijay; Bae, Unmin; Sikdar, Siddhartha; Yoo, Yang Mo; Karadayi, Kerem; Managuli, Ravi; Kim, Yongmin

    2008-07-01

    Commercial ultrasound machines in the past did not provide the ultrasound researchers access to raw ultrasound data. Lack of this ability has impeded evaluation and clinical testing of novel ultrasound algorithms and applications. Recently, we developed a flexible ultrasound back-end where all the processing for the conventional ultrasound modes, such as B, M, color flow and spectral Doppler, was performed in software. The back-end has been incorporated into a commercial ultrasound machine, the Hitachi HiVision 5500. The goal of this work is to develop an ultrasound research interface on the back-end for acquiring raw ultrasound data from the machine. The research interface has been designed as a software module on the ultrasound back-end. To increase the amount of raw ultrasound data that can be spooled in the limited memory available on the back-end, we have developed a method that can losslessly compress the ultrasound data in real time. The raw ultrasound data could be obtained in any conventional ultrasound mode, including duplex and triplex modes. Furthermore, use of the research interface does not decrease the frame rate or otherwise affect the clinical usability of the machine. The lossless compression of the ultrasound data in real time can increase the amount of data spooled by approximately 2.3 times, thus allowing more than 6s of raw ultrasound data to be acquired in all the modes. The interface has been used not only for early testing of new ideas with in vitro data from phantoms, but also for acquiring in vivo data for fine-tuning ultrasound applications and conducting clinical studies. We present several examples of how newer ultrasound applications, such as elastography, vibration imaging and 3D imaging, have benefited from this research interface. Since the research interface is entirely implemented in software, it can be deployed on existing HiVision 5500 ultrasound machines and may be easily upgraded in the future. The developed research

  9. The IAEA programme on research reactor safety

    International Nuclear Information System (INIS)

    Abou Yehia, H.

    2007-01-01

    According to the research reactor database of IAEA (RRDB), 250 reactors are operating worldwide, 248 have been shut down and 170 have been decommissioned. Among the 248 reactors that do not run, some will resume their activities, others will be dismantled and the rest do not face a clear future. The analysis of reported incidents shows that the ageing process is a major cause of failures, more than two thirds of operating reactors are over 30 years old. It also appears that the lack of adequate regulations or safety standards for research reactors is an important issue concerning reactor safety particularly when reactors are facing re-starting or upgrading or modifications. The IAEA has launched a 4-axis program: 1) to set basic safety regulations and standards for research reactors, 2) to provide IAEA members with an efficient help for the application of these safety regulations to their reactors, 3) to foster international exchange of information on research reactor safety, and 4) to provide IAEA members with a help concerning safety issues linked to malicious acts or sabotage on research reactors

  10. 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°.

  11. 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

  12. 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

  13. 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

  14. Rationale for energy research and development programme

    Energy Technology Data Exchange (ETDEWEB)

    1976-04-01

    This paper describes the rationale for the expenditure of government money on energy research and development. The Committee, organized in 1974, established the following order of project priorities: projects to determine current and future energy demand; projects concerned with the conservation and more efficient use of energy; projects concerned with the assessment of indigenous energy resources; projects concerned with the assessment of the human, financial, and organizational resources for energy production and use; and projects concerned with economic, technological, social, and environmental aspects of energy use and production over the next 15 years and beyond the next 15 years. Significant factors affecting the national energy economy, the strategy for energy research and development, and the results of committee activities are summarized. An energy scenario research is laid out. (MCW)

  15. 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.

  16. 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 ...

  17. 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.

  18. Landmine Detection Technology Research Programme at TNO

    NARCIS (Netherlands)

    Schleijpen, H.M.A.

    2003-01-01

    This presentation gives an overview of most of the activities on research and development in the technology area for landmine detection at TNO in the Netherlands. The projects cover the range from military applications to humanitarian demining. In the “conventional” detection systems area the

  19. 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

  20. 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)

  1. Karlsruhe Nuclear Research Centre. Programme budget 1988

    International Nuclear Information System (INIS)

    1987-01-01

    Following a general survey of tasks, planned activities and developmental trends of the nuclear research centre, the report gives an account of the activities to be performed in the subject fields of main interest, showing the budgeting figures for annual expenditure (for personnel, investments, operating costs) up to the year 1991. Further information explains the infrastructure of the centre and the distribution of overall expenditure as well as the budgetary planning. (UA) [de

  2. Euratom contributions in Fast Reactor research programmes

    International Nuclear Information System (INIS)

    Fanghänel, Th.; Somers, J.

    2013-01-01

    The Sustainable Nuclear Initiative: • demonstrate long-term sustainability of nuclear energy; • demonstration reactors of Gen IV: •more efficient use of resources; • closed fuel cycle; • reduced proliferation risks; • enhanced safety features. • Systems pursued in Europe: • Sodium-cooled fast reactor SFR; • Lead-cooled fast reactor LFR; • Gas-cooled fast reactor GFR. Sustainable Nuclear Energy Technology Platform SNE-TP promotes research, development and demonstration of the nuclear fission technologies necessary to achieve the SET-Plan goals

  3. 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)

  4. Biomass - Overview of Swiss Research Programme 2003

    International Nuclear Information System (INIS)

    Binggeli, D.; Guggisberg, B.

    2003-01-01

    This overview for the Swiss Federal Office of Energy (SFOE) discusses the results obtained in 2003 in various research projects worked on in Switzerland on the subject of biomass. In the biomass combustion area, subjects discussed include system optimisation for automatic firing, combustion particles, low-particle pellet furnaces, design and optimisation of wood-fired storage ovens, efficiency of filtering techniques and methane generation from wood. Also, an accredited testing centre for wood furnaces is mentioned and measurements made on an installation are presented. As far as the fermentation of biogenic wastes is concerned, biogas production from dairy-product wastes is described. Other projects discussed include a study on eco-balances of energy products, certification and marketing of biogas, evaluation of membranes, a measurement campaign for solar sludge-drying, the operation of a percolator installation for the treatment of bio-wastes, the effects of compost on the environment and the fermentation of coffee wastes. Also, statistics on biogas production in 2002 is looked at. Finally, a preliminary study on biofuels is presented

  5. 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

  6. 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.

  7. 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

  8. 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.

  9. 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 ...

  10. 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

  11. 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

  12. 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.

  13. 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.

  14. 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)

  15. 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.

  16. 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)

  17. 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

  18. Recent Activities on the Experimental Research Programme Using Small Tokamaks

    International Nuclear Information System (INIS)

    Gryaznevich, M. P.; Bosco, E. del; Malaquias, A.; Mank, G.; Oost, G. van

    2006-01-01

    A new concept of interactive co-ordinated research using small tokamaks in the mainstream fusion science areas, in testing of new diagnostics, materials and technologies as well as in education, training and broadening of the geography of fusion research in the scope of the IAEA Co-ordinated Research Project (CRP) is discussed in this paper. Besides the presentation of the recent activities on the experimental research programme using small tokamaks and scientific results achieved at the participating laboratories, information is provided about the organisation of the co-ordinated research project. Future plans of the co-ordinated activities within the CRP are discussed

  19. 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)].

  20. 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.

  1. 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

  2. Programme

    OpenAIRE

    Hobday, E, fl. 1905, artist

    2003-01-01

    A photograph of an illustrated programme listing dances. The illustration shows a snake charmer playing to a snake while another man watches. Buildings and trees can be seen behind a wall in the distance. In the lower right-hand corner of the programme is the signature 'E. Hobday'. The programme is almost certainly related to the Punjab Ball, Lahore. It is placed next to the Punjab Ball Menu in the album and the Menu is also illustrated by 'E. Hobday'.

  3. 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…

  4. 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

  5. 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.

  6. The South African National Accelerator Centre and its research programme

    Energy Technology Data Exchange (ETDEWEB)

    Watanabe, Y. [Kyushu Univ., Fukuoka (Japan)

    1997-03-01

    An overview of the South African National Accelerator Centre and its research activities is given with emphasis on medium energy nuclear physics and nuclear data measurements for medical use. Also presented is a preliminary result of {sup 40}Ca(p,p`x) spectrum measurement for 392 MeV which has been carried out at RCNP, Osaka University, under the South Africa-Japan collaborative programme. (author)

  7. Combustion chemistry - activities in the CHEK research programme

    Energy Technology Data Exchange (ETDEWEB)

    Dam-Johansen, K.; Johnsson, J.E.; Glarborg, P.; Frandsen, F.; Jensen, A.; Oestberg, M. [Technical Univ. of Denmark, Lyngby (Denmark). Dept. of Chemical Engineering

    1997-10-01

    The combustion chemistry in the oxidation of fossil fuels and biofuels determines together with mixing and heat transfer the required size of a furnace, the emission of gaseous pollutants, and the formation of ash and deposits on surfaces. This presentation describes technologies for solid fuels combustion and gives a summary of the fuels, the pollutant chemistry and the inorganic chemistry in combustion processes. Emphasis is put on the work carried out in the CHEC (Combustion and Harmful Emission Control) Research Programme. (orig.)

  8. 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)

  9. 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.

  10. 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.

  11. 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

  12. 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

  13. Building Digital Economy - The Research Councils Programme and the Vision

    Science.gov (United States)

    Hand, John

    We at the Research Councils believe that there are many aspects of society and business that could be transformed by the innovative design and use of digital technologies. This has led to the Digital Economy Programme. The Digital Economy is an RCUK Cross-Research Council Programme, led by the EPSRC, but working closely with ESRC, MRC, AHRC and TSB. What is Digital Economy? Digital Economy is the novel design or use of information and communication technology to help transform the lives of individuals, society or business. All Digital Economy research involves the user community. This can include industry, government, society, charities or other groups as applicable. The research will understand the technologies and also why change is needed, what the impacts will be and who will benefit. Research in this cross-research council area can be driven by economic, social or technical need. The early involvement of the user community is vital if new technologies are to be integrated successfully into business opportunities, technical solutions or commercial products and processes. Challenges in the Digital Economy will require multi-disciplinary academic input, including, but not limited to, the arts and humanities, economic and social sciences and medical sciences, in addition to engineering and physical sciences.

  14. 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.

  15. 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

  16. Karlsruhe Nuclear Research Center. Research and development programme 1988

    International Nuclear Information System (INIS)

    1987-01-01

    A general survey of planned activities and developmental trends of the nuclear research centre is followed by a more detailed account of projects and goals. The various institutes and laboratories are presented together with their specific task schedules. (UA) [de

  17. Karlsruhe Nuclear Research Center. Research and development programme 1989

    International Nuclear Information System (INIS)

    1988-01-01

    The R and D activities of the KfK are classified in 10 main research activities: 1) Project fast breeder; 2) separation nozzle method; 3) project nuclear fusion; 4) project reprocessing and waste processing; 5) ultimate storage; 6) environment and safety; 7) solid-state and materials research; 8) nuclear and elementary particle physics; 9) microtechnics e.g. X-ray lithography; 10) materials handling. (HP) [de

  18. Present status of research reactor decommissioning programme in Indonesia

    International Nuclear Information System (INIS)

    Suripto, A.; Mulyanto, N.

    2002-01-01

    At present Indonesia has 3 research reactors, namely the 30 MW MTR-type multipurpose reactor at Serpong Site, two TRIGA-type research reactors, the first one being 1 MW located at Bandung Site and the second one a small reactor of 100 kW at Yogyakarta Site. The TRIGA Reactor at the Bandung Site reached its first criticality at 250 kW in 1964, and then was operated at 1000 kW since 1971. In October 2000 the reactor power was successfully upgraded to 2 MW. This reactor has already been operated for 38 years. There is not yet any decision for the decommissioning of this reactor. However it will surely be an object for the near future decommissioning programme and hence anticipation for the above situation becomes necessary. The regulation on decommissioning of research reactor is already issued by the independent regulatory body (BAPETEN) according to which the decommissioning permit has to be applied by the BATAN. For Indonesia, an early decommissioning strategy for research reactor dictates a restricted re-use of the site for other nuclear installation. This is based on high land price, limited availability of radwaste repository site, and other cost analysis. Spent graphite reflector from the Bandung TRIGA reactor is recommended for a direct disposal after conditioning, without any volume reduction treatment. Development of human resources, technological capability as well as information flow from and exchange with advanced countries are important factors for the future development of research reactor decommissioning programme in Indonesia. (author)

  19. Discrepancies between soft x-ray emissivity contours and magnetic flux surfaces in Alcator C-Mod

    International Nuclear Information System (INIS)

    Borras, M.C.; Granetz, R.S.

    1996-01-01

    The soft x-ray diagnostic system of Alcator C-Mod, equipped with 152 detectors distributed in four arrays, is used to obtain iso-emissivity surfaces. These surfaces have been characterized by giving their elongation and relative shift from the centre of the tokamak as functions of plasma radius. Flux surfaces, provided by magnetic diagnostics, have also been described with elongation and shift. Results from the comparison of the two sets of geometric parameters obtained from magnetic and x-ray diagnostics are presented. We find that, whereas the shifts obtained from these two diagnostic methods are always in good agreement, the corresponding elongation curves show different patterns. An agreement between elongations better than 2% is only found in a range of about 2 cm in minor radius. On the other hand, the elongations can differ by 10% towards the plasma edge and the plasma centre. Error bars for the x-ray diagnostic are obtained by propagating the effect of ± 1% random errors at the detector signals, and can amount to ± 1-2% of the estimated values near the edge and the centre of the plasma. The estimated uncertainties in the determination of elongation from magnetic flux surfaces are of the order of 4%. A series of tests and simulations performed to verify the accuracy of the X-ray diagnostic system is presented. The discrepancies found could imply the existence of asymmetries in impurity concentration. (Author)

  20. Intermittent fluctuations in the Alcator C-Mod scrape-off layer for ohmic and high confinement mode plasmas

    Science.gov (United States)

    Garcia, O. E.; Kube, R.; Theodorsen, A.; LaBombard, B.; Terry, J. L.

    2018-05-01

    Plasma fluctuations in the scrape-off layer of the Alcator C-Mod tokamak in ohmic and high confinement modes have been analyzed using gas puff imaging data. In all cases investigated, the time series of emission from a single spatially resolved view into the gas puff are dominated by large-amplitude bursts, attributed to blob-like filament structures moving radially outwards and poloidally. There is a remarkable similarity of the fluctuation statistics in ohmic plasmas and in edge localized mode-free and enhanced D-alpha high confinement mode plasmas. Conditionally averaged waveforms have a two-sided exponential shape with comparable temporal scales and asymmetry, while the burst amplitudes and the waiting times between them are exponentially distributed. The probability density functions and the frequency power spectral densities are similar for all these confinement modes. These results provide strong evidence in support of a stochastic model describing the plasma fluctuations in the scrape-off layer as a super-position of uncorrelated exponential pulses. Predictions of this model are in excellent agreement with experimental measurements in both ohmic and high confinement mode plasmas. The stochastic model thus provides a valuable tool for predicting fluctuation-induced plasma-wall interactions in magnetically confined fusion plasmas.

  1. 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.

  2. Plasma profiles and flows in the high-field side scrape-off layer in Alcator C-Mod

    Energy Technology Data Exchange (ETDEWEB)

    Smick, N. [MIT Plasma Science and Fusion Center, NW17-170, 175 Albany St., Cambridge, MA 02139 (United States)]. E-mail: nsmick@mit.edu; LaBombard, B. [MIT Plasma Science and Fusion Center, NW17-170, 175 Albany St., Cambridge, MA 02139 (United States); Pitcher, C.S. [132 Bowood Ave., Toronto, M4N1Y5 (Canada)

    2005-03-01

    A novel, magnetically-driven swing probe was recently installed near the midplane on the high-field side SOL in Alcator C-Mod. The probe collects plasma from co- and counter-current directions during its respective 0-90 deg and 90-180 deg of motion, thus providing profiles of density, electron temperature and plasma flow parallel to magnetic field lines (Mach number, M{sub parallel}) up to the separatrix. Results are reported from discharges with different magnetic topologies: lower single-null, upper single-null, and double-null. In single-null, a strong parallel flow (vertical bar M{sub parallel} vertical bar {approx} 1) is detected, which is always directed from the low- to high-field SOL. In double-null discharges, e-folding lengths in the high-field SOL are a factor of {approx}4 shorter than the low-field SOL. Thus, plasma appears to 'fill-in' the high-field SOL in single-null plasmas, not by cross-field transport but by parallel flow from the low-field SOL - a picture consistent with a very strong ballooning-like component to the cross-field transport.

  3. Electron critical gradient scale length measurements of ICRF heated L-mode plasmas at Alcator C-Mod tokamak

    Science.gov (United States)

    Houshmandyar, S.; Hatch, D. R.; Horton, C. W.; Liao, K. T.; Phillips, P. E.; Rowan, W. L.; Zhao, B.; Cao, N. M.; Ernst, D. R.; Greenwald, M.; Howard, N. T.; Hubbard, A. E.; Hughes, J. W.; Rice, J. E.

    2018-04-01

    A profile for the critical gradient scale length (Lc) has been measured in L-mode discharges at the Alcator C-Mod tokamak, where electrons were heated by an ion cyclotron range of frequency through minority heating with the intention of simultaneously varying the heat flux and changing the local gradient. The electron temperature gradient scale length (LTe-1 = |∇Te|/Te) profile was measured via the BT-jog technique [Houshmandyar et al., Rev. Sci. Instrum. 87, 11E101 (2016)] and it was compared with electron heat flux from power balance (TRANSP) analysis. The Te profiles were found to be very stiff and already above the critical values, however, the stiffness was found to be reduced near the q = 3/2 surface. The measured Lc profile is in agreement with electron temperature gradient (ETG) models which predict the dependence of Lc-1 on local Zeff, Te/Ti, and the ratio of the magnetic shear to the safety factor. The results from linear Gene gyrokinetic simulations suggest ETG to be the dominant mode of turbulence in the electron scale (k⊥ρs > 1), and ion temperature gradient/trapped electron mode modes in the ion scale (k⊥ρs < 1). The measured Lc profile is in agreement with the profile of ETG critical gradients deduced from Gene simulations.

  4. Upgraded PMI diagnostic capabilities using Accelerator-based In-situ Materials Surveillance (AIMS) on Alcator C-Mod

    Science.gov (United States)

    Kesler, Leigh; Barnard, Harold; Hartwig, Zachary; Sorbom, Brandon; Lanza, Richard; Terry, David; Vieira, Rui; Whyte, Dennis

    2014-10-01

    The AIMS diagnostic was developed to rapidly and non-invasively characterize in-situ plasma material interactions (PMI) in a tokamak. Recent improvements are described which significantly expand this measurement capability on Alcator C-Mod. The detection time at each wall location is reduced from about 10 min to 30 s, via improved hardware and detection geometry. Detectors are in an augmented re-entrant tube to maximize the solid angle between detectors and diagnostic locations. Spatial range is expanded by using beam dynamics simulation to design upgraded B-field power supplies to provide maximal poloidal access, including a ~20° toroidal range in the divertor. Measurement accuracy is improved with angular and energy resolved cross section measurements obtained using a separate 0.9 MeV deuteron ion accelerator. Future improvements include the installation of recessed scintillator tiles as beam targets for calibration of the diagnostic. Additionally, implanted depth marker tiles will enable AIMS to observe the in-situ erosion and deposition of high-Z plasma-facing materials. This work is supported by U.S. DOE Grant No. DE-FG02-94ER54235 and Cooperative Agreement No. DE-FC02-99ER54512.

  5. Changes in core electron temperature fluctuations across the ohmic energy confinement transition in Alcator C-Mod plasmas

    International Nuclear Information System (INIS)

    Sung, C.; White, A.E.; Howard, N.T.; Oi, C.Y.; Rice, J.E.; Gao, C.; Ennever, P.; Porkolab, M.; Parra, F.; Ernst, D.; Walk, J.; Hughes, J.W.; Irby, J.; Kasten, C.; Hubbard, A.E.; Greenwald, M.J.; Mikkelsen, D.

    2013-01-01

    The first measurements of long wavelength (k y ρ s < 0.3) electron temperature fluctuations in Alcator C-Mod made with a new correlation electron cyclotron emission diagnostic support a long-standing hypothesis regarding the confinement transition from linear ohmic confinement (LOC) to saturated ohmic confinement (SOC). Electron temperature fluctuations decrease significantly (∼40%) crossing from LOC to SOC, consistent with a change from trapped electron mode (TEM) turbulence domination to ion temperature gradient (ITG) turbulence as the density is increased. Linear stability analysis performed with the GYRO code (Candy and Waltz 2003 J. Comput. Phys. 186 545) shows that TEMs are dominant for long wavelength turbulence in the LOC regime and ITG modes are dominant in the SOC regime at the radial location (ρ ∼ 0.8) where the changes in electron temperature fluctuations are measured. In contrast, deeper in the core (ρ < 0.8), linear stability analysis indicates that ITG modes remain dominant across the LOC/SOC transition. This radial variation suggests that the robust global changes in confinement of energy and momentum occurring across the LOC/SOC transition are correlated to local changes in the dominant turbulent mode near the edge. (paper)

  6. Intermittent electron density and temperature fluctuations and associated fluxes in the Alcator C-Mod scrape-off layer

    Science.gov (United States)

    Kube, R.; Garcia, O. E.; Theodorsen, A.; Brunner, D.; Kuang, A. Q.; LaBombard, B.; Terry, J. L.

    2018-06-01

    The Alcator C-Mod mirror Langmuir probe system has been used to sample data time series of fluctuating plasma parameters in the outboard mid-plane far scrape-off layer. We present a statistical analysis of one second long time series of electron density, temperature, radial electric drift velocity and the corresponding particle and electron heat fluxes. These are sampled during stationary plasma conditions in an ohmically heated, lower single null diverted discharge. The electron density and temperature are strongly correlated and feature fluctuation statistics similar to the ion saturation current. Both electron density and temperature time series are dominated by intermittent, large-amplitude burst with an exponential distribution of both burst amplitudes and waiting times between them. The characteristic time scale of the large-amplitude bursts is approximately 15 μ {{s}}. Large-amplitude velocity fluctuations feature a slightly faster characteristic time scale and appear at a faster rate than electron density and temperature fluctuations. Describing these time series as a superposition of uncorrelated exponential pulses, we find that probability distribution functions, power spectral densities as well as auto-correlation functions of the data time series agree well with predictions from the stochastic model. The electron particle and heat fluxes present large-amplitude fluctuations. For this low-density plasma, the radial electron heat flux is dominated by convection, that is, correlations of fluctuations in the electron density and radial velocity. Hot and dense blobs contribute only a minute fraction of the total fluctuation driven heat flux.

  7. Gas research programme in Sweden 1994-1996. Evaluation report

    Energy Technology Data Exchange (ETDEWEB)

    Hustad, J E [Norwegian Univ. of Science and Technology, Trondheim (Norway); Jahkola, A [Helsinki Univ. of Technology (Finland); Norhammar, U [STOSEB (Sweden)

    1997-05-01

    This evaluation report is written by an international committee at the request of the Swedish National Board for Industrial and Technical Development (NUTEK). The committee was invited to look into the quality of a research programme funded jointly by Svenskt Gastekniskt Center SGC (Swedish Gas Technical Centre) and NUTEK. Criteria`s considered in the evaluation have in short been as follows: scientific value of the projects and of the results obtained; merits of the methods; capability of research groups and adequacy of resources; quality of research in the view of problem oriented applied research; necessity of future financial support. Although the projects are the main elements to be evaluated, the evaluators have paid attention to structural and other problems wherever such a need has been seen.

  8. Combustion chemistry. Activities in the CHEC research programme

    Energy Technology Data Exchange (ETDEWEB)

    Dam-Johansen, K; Johnsson, J E; Glarborg, P; Frandsen, F; Jensen, A; Oestberg, M [Technical Univ. of Denmark, Dept. of Chemical Engineering, Lyngby (Denmark)

    1996-12-01

    The combustion chemistry in the oxidation of fossil fuels and biofuels determines together with mixing and heat transfer the required size of a furnace, the emission of gaseous pollutants, and the formation of ash and deposits on surfaces. This paper describes technologies for solid fuels combustion and gives a summary of the fuels, the pollutant chemistry and the inorganic chemistry in combustion processes. Emphasis is put on the work carried out in the CHEC (Combustion and Harmful Emission Control Research Programme). (au) 173 refs.

  9. Research programme on radioactive wastes - Synthesis report 2009

    International Nuclear Information System (INIS)

    Brander, S.

    2010-02-01

    This short synthesis report for the Swiss Federal Office of Energy (SFOE) issued by the head of the programme on radioactive wastes reports on activities during the year 2009. Background information on the definition of topics to be focussed on is briefly presented. In particular, topics such as communication with the general public, knowledge-saving and marking concepts for radioactive wastes are noted. Work done in these areas as well as on waste management in general are discussed. Conferences held and the transfer of know-how are noted, as is cooperation with foreign organisations active in the area of nuclear research and waste management. Finally, work planned for 2010 is noted

  10. Research and technology programmes supporting waste management in BNFL

    International Nuclear Information System (INIS)

    Fairhall, G.A.; Horner, A.M.

    2000-01-01

    Waste Management is a major activity of BNFL in the UK and at various locations internationally. To support these activities extensive programmes of Research and Technology have been undertaken for many years. This involves practical studies involving active and non-active work at laboratory and pilot plant scale. Extensive use is also made of theoretical and modelling techniques. Current work is aimed at underpinning and improving current operations supporting the design and safety cases of new plant and addressing waste management activities of the future including decommissioning. (authors)

  11. 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

  12. Detailed programme for research and development 1999-2004

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-09-01

    This report is a background to RD and D-Programme 98. The report gives an account of most of the research and development being conducted by SKB. The current state of knowledge is described, along with the goals and programmes that govern the continued work. The period of immediate concern comprises the next three years, 1999-2001. Chapters 2 and 3 give an account of the development of the safety assessment, and the methods and models used to assess long-term safety. Then follow a number of chapters that give an account of the R and D with primary purpose to support the safety assessment. There is also a description of some technical development of the deep repository and its components, as well as review of alternative methods such as partitioning and transmutation. Methods for investigation and evaluation of sites for the deep repository are also being further examined and developed, with sights set on the commencement of a site investigation by no earlier than 2001. A large part of SKBs research, development and demonstration is conducted in the form of projects. The majority of the projects have international participation. The Aespoe HRL (Hard Rock Laboratory) is an excellent example of this. A considerable portion of SKBs project-oriented R and D is concentrated to the Aespoe HRL. An important task for the Aespoe HRL is to test and demonstrate parts of the disposal system on a full scale. Finally, there is a chapter on scientific information. We want to communicate our scientific findings to the public and to local politicians and community leaders to obtain acceptance for a deep repository. It is the purpose of the safety assessment to develop and administer the methods and models for calculations employed by the safety assessment (Chapters 2 and 3). The topic-specific programmes serve to develop a better understanding of the processes dealt with in the safety assessment, to develop and review alternative models and to compile background data for the safety

  13. Detailed programme for research and development 1999-2004

    International Nuclear Information System (INIS)

    1998-09-01

    This report is a background to RD and D-Programme 98. The report gives an account of most of the research and development being conducted by SKB. The current state of knowledge is described, along with the goals and programmes that govern the continued work. The period of immediate concern comprises the next three years, 1999-2001. Chapters 2 and 3 give an account of the development of the safety assessment, and the methods and models used to assess long-term safety. Then follow a number of chapters that give an account of the R and D with primary purpose to support the safety assessment. There is also a description of some technical development of the deep repository and its components, as well as review of alternative methods such as partitioning and transmutation. Methods for investigation and evaluation of sites for the deep repository are also being further examined and developed, with sights set on the commencement of a site investigation by no earlier than 2001. A large part of SKBs research, development and demonstration is conducted in the form of projects. The majority of the projects have international participation. The Aespoe HRL (Hard Rock Laboratory) is an excellent example of this. A considerable portion of SKBs project-oriented R and D is concentrated to the Aespoe HRL. An important task for the Aespoe HRL is to test and demonstrate parts of the disposal system on a full scale. Finally, there is a chapter on scientific information. We want to communicate our scientific findings to the public and to local politicians and community leaders to obtain acceptance for a deep repository. It is the purpose of the safety assessment to develop and administer the methods and models for calculations employed by the safety assessment (Chapters 2 and 3). The topic-specific programmes serve to develop a better understanding of the processes dealt with in the safety assessment, to develop and review alternative models and to compile background data for the safety

  14. Sustainable energy systems and the EURATOM research programme

    International Nuclear Information System (INIS)

    Webster, S.; Van Goethem, G.; )

    2007-01-01

    We are at a turning point in European research. With the launch of the EU's 7th Framework Programme, committing some Euro 53 billion of public funds to the European research effort over the next 7 years, Europe has finally woken up to the importance of Research and Development in the realisation of the most fundamental objectives defining the Union: growth, competitiveness, and knowledge. At the same time, and with strong links to growth and competitiveness but also to environmental protection, the Union is in the throws of an intense debate on future energy policy and climate change. Part of the research budget, some would say too small a part, is earmarked for energy - in particular the technological aspects of low carbon systems such renewables. This effort, together with measures to improve the EU's security and independence of supply, are essential if Europe is to respond effectively to solve the future energy conundrum. But where does nuclear fit in all this? What will the Union be doing in the area of nuclear research? Indeed, does nuclear figure at all in the long-term plans of the Union? Through the EURATOM part of the Framework Programme, the EU is maintaining important support to up-stream research in the area of advanced reactor technologies. This effort is being coordinated at the global level through EURATOM's membership of the Generation-IV International Forum. Though EU research in this field still has its critics among the Member States, and despite the relatively small sums currently committed, the leverage effect of current actions is significant and this is set to grow in the future. The imminent setting up of a Strategic Energy Technology Plan, as part of the European Commission on-going activities in the field of energy policy, and the feedback from independent experts in the Advisory Group on Energy and the EURATOM Scientific and Technical Committee all point to following conclusions: EU support for research on advanced nuclear fission

  15. Local gas injection as a scrape-off layer diagnostic on the Alcator C-Mod tokamak

    International Nuclear Information System (INIS)

    Jablonski, D.F.

    1996-05-01

    A capillary puffing array has been installed on Alcator C-Mod which allows localized introduction of gaseous species in the scrape-off layer. This system has been utilized in experiments to elucidate both global and local properties of edge transport. Deuterium fueling and recycling impurity screening are observed to be characterized by non-dimensional screening efficiencies which are independent of the location of introduction. In contrast, the behavior of non-recycling impurities is seen to be characterized by a screening time which is dependent on puff location. The work of this thesis has focused on the use of the capillary array with a camera system which can view impurity line emission plumes formed in the region of an injection location. The ionic plumes observed extend along the magnetic field line with a comet-like asymmetry, indicative of background plasma ion flow. The flow is observed to be towards the nearest strike-point, independent of x-point location, magnetic field direction, and other plasma parameters. While the axes of the plumes are generally along the field line, deviations are seen which indicate cross-field ion drifts. A quasi-two dimensional fluid model has been constructed to use the plume shapes of the first charge state impurity ions to extract information about the local background plasma, specifically the temperature, parallel flow velocity, and radial electric field. Through comparisons of model results with those of a three dimensional Monte Carlo code, and comparisons of plume extracted parameters with scanning probe measurements, the efficacy of the model is demonstrated. Plume analysis not only leads to understandings of local edge impurity transport, but also presents a novel diagnostic technique

  16. Verification of GENE and GYRO with L-mode and I-mode plasmas in Alcator C-Mod

    Science.gov (United States)

    Mikkelsen, D. R.; Howard, N. T.; White, A. E.; Creely, A. J.

    2018-04-01

    Verification comparisons are carried out for L-mode and I-mode plasma conditions in Alcator C-Mod. We compare linear and nonlinear ion-scale calculations by the gyrokinetic codes GENE and GYRO to each other and to the experimental power balance analysis. The two gyrokinetic codes' linear growth rates and real frequencies are in good agreement throughout all the ion temperature gradient mode branches and most of the trapped electron mode branches of the kyρs spectra at r/a = 0.65, 0.7, and 0.8. The shapes of the toroidal mode spectra of heat fluxes in nonlinear simulations are very similar for kyρs ≤ 0.5, but in most cases GENE has a relatively higher heat flux than GYRO at higher mode numbers. The ratio of ion to electron heat flux is similar in the two codes' simulations, but the heat fluxes themselves do not agree in almost all cases. In the I-mode regime, GENE's heat fluxes are ˜3 times those from GYRO, and they are ˜60%-100% higher than GYRO in the L-mode conditions. The GYRO under-prediction of Qe is much reduced in GENE's L-mode simulations, and it is eliminated in the I-mode simulations. This largely improved agreement with the experimental electron heat flux is offset, however, by the large overshoot of GENE's ion heat fluxes, which are 2-3 times the experimental level, and its electron heat flux overshoot at r/a = 0.80 in the I-mode. Rotation effects can explain part of the difference between the two codes' predictions, but very significant differences remain in simulations without any rotation effects.

  17. Local gas injection as a scrape-off layer diagnostic on the Alcator C-Mod tokamak

    Energy Technology Data Exchange (ETDEWEB)

    Jablonski, David F. [Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)

    1996-05-01

    A capillary puffing array has been installed on Alcator C-Mod which allows localized introduction of gaseous species in the scrape-off layer. This system has been utilized in experiments to elucidate both global and local properties of edge transport. Deuterium fueling and recycling impurity screening are observed to be characterized by non-dimensional screening efficiencies which are independent of the location of introduction. In contrast, the behavior of non-recycling impurities is seen to be characterized by a screening time which is dependent on puff location. The work of this thesis has focused on the use of the capillary array with a camera system which can view impurity line emission plumes formed in the region of an injection location. The ionic plumes observed extend along the magnetic field line with a comet-like asymmetry, indicative of background plasma ion flow. The flow is observed to be towards the nearest strike-point, independent of x-point location, magnetic field direction, and other plasma parameters. While the axes of the plumes are generally along the field line, deviations are seen which indicate cross-field ion drifts. A quasi-two dimensional fluid model has been constructed to use the plume shapes of the first charge state impurity ions to extract information about the local background plasma, specifically the temperature, parallel flow velocity, and radial electric field. Through comparisons of model results with those of a three dimensional Monte Carlo code, and comparisons of plume extracted parameters with scanning probe measurements, the efficacy of the model is demonstrated. Plume analysis not only leads to understandings of local edge impurity transport, but also presents a novel diagnostic technique.

  18. 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

  19. 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)

  20. 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.

  1. 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

  2. Energy policy fundamentals research programme - Activities and projects in 2002

    International Nuclear Information System (INIS)

    Meier, R.; Previdoli, P.

    2003-01-01

    This annual report for the Swiss Federal Office of Energy reviews the activities and projects carried out within the Swiss Confederation's Energy Policy Fundamentals Research programme during 2002. The programme's main centres of activity are described, including projects involving the acquisition of data on indicators of selected cantonal energy saving measures, the possibility of reducing carbon dioxide emissions by influencing fuel prices, new construction instead of refurbishment of buildings, internalisation of risks involved with nuclear power and the marginal costs of intensified energy-efficiency measures. In the technology monitoring area, the results of studies concerning combined heat and power systems, heat pumps and fuel cells are reviewed. Further projects are described in the building and fuel supply areas and the influence of wind power on European peak power requirements is examined. Marketing aspects concerning the thermal use of solar energy and low energy consumption housing are discussed, as is the promotion of energy efficiency in housing and industry. Also local and regional efforts being made in the energy policy area are described. The report is rounded off with a list of the various projects mentioned in the report and appropriate contact information

  3. 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

  4. Research programme on radioactive wastes; Forschungsprogramm Radioaktive Abfaelle

    Energy Technology Data Exchange (ETDEWEB)

    Eckhardt, A. [Eidgenoessische Kommission fuer die Sicherheit der Kernanlagen (KSA), Brugg (Switzerland); Hufschmid, P. [Kommission Nukleare Entsorgung (KNE), Bern (Switzerland); Jordi, S. [Swiss Federal Office of Energy, Berne (Switzerland); Schanne, M. [Institut fuer Angewandte Medienwissenschaft (IAM), Zuercher Hochschule, Winterthur (Switzerland); Vigfusson, J. [Hauptabteilung fuer die Sicherheit der Kernanlagen (HSK), Brugg (Switzerland)

    2009-11-15

    This report for the Swiss Federal Department of the Environment, Transport, Energy and Communication (DETEC) takes a look at work done within the framework of the research programme on radioactive wastes. The paper discusses the development of various projects and the associated organisations involved. Both long-term and short-term topics are examined. The long-term aspects of handling radioactive wastes include organisation and financing as well as the preservation of know-how and concepts for marking the repositories. Communication with the general public on the matter is looked at along with public perception, opinion-making and acceptance. Waste storage concepts are looked at in detail and aspects such as environmental protection, monitoring concepts, retrievability and encasement materials are discussed. Finally, ethical and legal aspects of radioactive waste repositories are examined. The paper is completed with appendixes dealing with planning, co-ordination and the responsibilities involved

  5. Power requirements for superior H-mode confinement on Alcator C-Mod: experiments in support of ITER

    International Nuclear Information System (INIS)

    Hughes, J.W.; Reinke, M.L.; Terry, J.L.; Brunner, D.; Greenwald, M.; Hubbard, A.E.; LaBombard, B.; Lipschultz, B.; Ma, Y.; Wolfe, S.; Wukitch, S.J.; Loarte, A.

    2011-01-01

    Power requirements for maintaining sufficiently high confinement (i.e. normalized energy confinement time H 98 ≥ 1) in H-mode and its relation to H-mode threshold power scaling, P th , are of critical importance to ITER. In order to better characterize these power requirements, recent experiments on the Alcator C-Mod tokamak have investigated H-mode properties, including the edge pedestal and global confinement, over a range of input powers near and above P th . In addition, we have examined the compatibility of impurity seeding with high performance operation, and the influence of plasma radiation and its spatial distribution on performance. Experiments were performed at 5.4 T at ITER relevant densities, utilizing bulk metal plasma facing surfaces and an ion cyclotron range of frequency waves for auxiliary heating. Input power was scanned both in stationary enhanced D α (EDA) H-modes with no large edge localized modes (ELMs) and in ELMy H-modes in order to relate the resulting pedestal and confinement to the amount of power flowing into the scrape-off layer, P net , and also to the divertor targets. In both EDA and ELMy H-mode, energy confinement is generally good, with H 98 near unity. As P net is reduced to levels approaching that in L-mode, pedestal temperature diminishes significantly and normalized confinement time drops. By seeding with low-Z impurities, such as Ne and N 2 , high total radiated power fractions are possible, along with substantial reductions in divertor heat flux (>4x), all while maintaining H 98 ∼ 1. When the power radiated from the confined versus unconfined plasma is examined, pedestal and confinement properties are clearly seen to be an increasing function of P net , helping to unify the results with those from unseeded H-modes. This provides increased confidence that the power flow across the separatrix is the correct physics basis for ITER extrapolation. The experiments show that P net /P th of one or greater is likely to lead to H

  6. [PRIER II. The Emilia-Romagna Research and Innovation Programme].

    Science.gov (United States)

    Addis, Antonio; Papini, Donato; Bassi, Maria Chiara; Grilli, Roberto

    2015-09-01

    The Emilia-Romagna Programme for Research and Innovation "PRIER" was born in 2005 with the aim of increasing cultural and operational conditions for the development of clinical research, useful both to the Regional Health Service (SSR) and to the private sectors of pharmaceutical and biomedical areas. In this context, the PRIER had from the beginning a double connotation: a space where the SSR can explore issues related to the development of its own research capacity; and a context where new possible ways of relating and comparison with the pharmaceutical and biomedical industry are tested. Over the years the activities of PRIER were defined by: initiatives to strengthen the system of research in SSR; development of tools to monitor activities of the research; production of clinical-organizational recommendations for the governance of innovation. In 2013 a new area of discussion and a common interest have been identified on the subject of clinical registries. In particular, it wanted to build a path of work able to identify all the possible critical and relevant points (points to consider), indispensable, necessary or useful to the construction and use of clinical registries, taking into account the points of view of all actors involved. The course began with defining the rules of the game and continued with workshops that allowed to analyse together the matter. At the end of the second workshop it was decided to make the work carried out visible: first, not to miss the opportunity offered by the past but recent discussion; secondly, to facilitate the discussion both on the issue of registers and to the adopted methodology, which sees the different actors (public and private ones) to reason together in a context for once not influenced by necessities of negotiation and government resources.

  7. Open Air Laboratories (OPAL): A community-driven research programme

    Energy Technology Data Exchange (ETDEWEB)

    Davies, L., E-mail: l.davies@imperial.ac.uk [Imperial College London, London SW7 2AZ (United Kingdom); Bell, J.N.B.; Bone, J.; Head, M.; Hill, L. [Imperial College London, London SW7 2AZ (United Kingdom); Howard, C. [Natural History Museum, London SW7 5BD (United Kingdom); Hobbs, S.J. [Environment Department, University of York, Heslington, York YO10 5DD (United Kingdom); Jones, D.T. [Imperial College London, London SW7 2AZ (United Kingdom); Natural History Museum, London SW7 5BD (United Kingdom); Power, S.A. [Imperial College London, London SW7 2AZ (United Kingdom); Rose, N. [Department of Geography, University College London, London WC1E 6BT (United Kingdom); Ryder, C.; Seed, L. [Imperial College London, London SW7 2AZ (United Kingdom); Stevens, G. [Natural History Museum, London SW7 5BD (United Kingdom); Toumi, R.; Voulvoulis, N. [Imperial College London, London SW7 2AZ (United Kingdom); White, P.C.L. [Environment Department, University of York, Heslington, York YO10 5DD (United Kingdom)

    2011-08-15

    OPAL is an English national programme that takes scientists into the community to investigate environmental issues. Biological monitoring plays a pivotal role covering topics of: i) soil and earthworms; ii) air, lichens and tar spot on sycamore; iii) water and aquatic invertebrates; iv) biodiversity and hedgerows; v) climate, clouds and thermal comfort. Each survey has been developed by an inter-disciplinary team and tested by voluntary, statutory and community sectors. Data are submitted via the web and instantly mapped. Preliminary results are presented, together with a discussion on data quality and uncertainty. Communities also investigate local pollution issues, ranging from nitrogen deposition on heathlands to traffic emissions on roadside vegetation. Over 200,000 people have participated so far, including over 1000 schools and 1000 voluntary groups. Benefits include a substantial, growing database on biodiversity and habitat condition, much from previously unsampled sites particularly in urban areas, and a more engaged public. - Highlights: > Environmental research conducted jointly by the public and scientists. > Over 200,000 people involved, 8000 sites surveyed, uncertainty minimised. > New insights into urban pollution. > A more engaged and informed society. - Research is enriched where the public and scientists work together.

  8. Open Air Laboratories (OPAL): A community-driven research programme

    International Nuclear Information System (INIS)

    Davies, L.; Bell, J.N.B.; Bone, J.; Head, M.; Hill, L.; Howard, C.; Hobbs, S.J.; Jones, D.T.; Power, S.A.; Rose, N.; Ryder, C.; Seed, L.; Stevens, G.; Toumi, R.; Voulvoulis, N.; White, P.C.L.

    2011-01-01

    OPAL is an English national programme that takes scientists into the community to investigate environmental issues. Biological monitoring plays a pivotal role covering topics of: i) soil and earthworms; ii) air, lichens and tar spot on sycamore; iii) water and aquatic invertebrates; iv) biodiversity and hedgerows; v) climate, clouds and thermal comfort. Each survey has been developed by an inter-disciplinary team and tested by voluntary, statutory and community sectors. Data are submitted via the web and instantly mapped. Preliminary results are presented, together with a discussion on data quality and uncertainty. Communities also investigate local pollution issues, ranging from nitrogen deposition on heathlands to traffic emissions on roadside vegetation. Over 200,000 people have participated so far, including over 1000 schools and 1000 voluntary groups. Benefits include a substantial, growing database on biodiversity and habitat condition, much from previously unsampled sites particularly in urban areas, and a more engaged public. - Highlights: → Environmental research conducted jointly by the public and scientists. → Over 200,000 people involved, 8000 sites surveyed, uncertainty minimised. → New insights into urban pollution. → A more engaged and informed society. - Research is enriched where the public and scientists work together.

  9. 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...

  10. Leadership as a Health Research Policy Intervention: An Evaluation of the NIHR Leadership Programme (Phase 2).

    Science.gov (United States)

    Marjanovic, Sonja; Cochrane, Gavin; Manville, Catriona; Harte, Emma; Chataway, Joanna; Jones, Molly Morgan

    2016-01-29

    In early 2012, the National Institute for Health Research (NIHR) leadership programme was re-commissioned for a further three years following an evaluation by RAND Europe. During this new phase of the programme, we conducted a real-time evaluation, the aim of which was to allow for reflection on and adjustment of the programme on an on-going basis as events unfold. This approach also allowed for participants on the programme to contribute to and positively engage in the evaluation. The study aimed to understand the outputs and impacts from the programme, and to test the underlying assumptions behind the NIHR Leadership Programme as a science policy intervention. Evidence on outputs and impacts of the programme were collected around the motivations and expectations of participants, programme design and individual-, institutional- and system-level impacts.

  11. 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.

  12. 3rd programme 'Energy research and energy technologies'

    International Nuclear Information System (INIS)

    1990-01-01

    In the light of developments in the 80s, the questions of dependence and available resources seem less grave in the long and medium term; on the other hand, a further problem has arisen which might prove even more serious with a view to the safeguarding of long-term energy supply: the use of fossil energy sources such as coal; petroleum, and natural gas involves effects constituting a considerable threat to the environment and the world climate. Examples are acid rain and the greenhouse effect. Furthermore, new safety issues and, to a larger extent, also acceptance issues have arisen as regards nuclear energy utilization. To contribute towards solving these problems by research and development is the main objective of this programme. The strategy adopted comprices two approaches complementary to each other: elaboration of scientific bases, system connections, and new techniques permitting - continued use of primary and secondary energy sources to the extent required while taking into account the needs of an increasingly more vulnerable environment; - to ensure the lowest possible energy consumption in the future, reducing, at the same time, considerably the amount of greenhouse gases emitted. (orig./UA) [de

  13. 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

  14. 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

  15. 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

  16. 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).

  17. The Finnish research programme on climate change SILMU

    International Nuclear Information System (INIS)

    Heikinheimo, P.; Kanninen, M.

    1995-01-01

    SILMU, which runs from 1990 to 1995, aims at studying climate change and its impacts. It also seeks to provide information to Finnish policy makers on adaptation and mitigation. The topics range from air chemistry to sociology, and the total number of projects is 74. Interim evaluation of the programme was carried out in 1992. During the second half of SILMU, 10% of the total budget (total: 14 Million ECU) has been devoted to programme integration. 8 refs

  18. Research programme on controlled thermonuclear fusion. Synthesis report 2011

    International Nuclear Information System (INIS)

    Vaucher, C.; Tran, M. Q.; Villard, L.; Marot, L.

    2012-01-01

    Since 1978, research on thermonuclear fusion in Switzerland is closely related to the research programme of the European Atomic Energy Community (EURATOM). The Swiss projects tackle aspects of plasma physics and fusion technology. Switzerland participates to the construction and operation of the Joint European Torus (JET), which started operation again in 2011. The International Thermonuclear Experimental Reactor (ITER) is the last step before DEMO, a prototype fusion reactor able to deliver electricity and demonstrate the economic viability of fusion energy. The 'Centre de Recherches en Physique des Plasmas' (CRPP) of the EPFL went on with its participation to the scientific and technological programme of EURATOM. Researches are carried out essentially on 2 sites: (i) at EPFL, where topics dealt with include the physics of magnetic confinement studied using the Variable Configuration Tokamak (TCV), the basic experiment TORPEX, theory and numerical modelling, and the technology of plasma heating and current generation by hyper-frequency waves; (ii) at the Paul Scherrer Institute (PSI), where activities are devoted to superconductivity and structure materials. Thanks to the large flexibility of the TCV design and operation modus, plasmas of different shapes can be created and controlled, what is a very useful option to verify numerical simulation results. Besides, the injection of millimetre waves allows directing the injected power according to specific profiles. In the TCV it could be demonstrated for the first time that the injection of Electronic Cyclotronic Heating (ECH) waves is able to double the frequency of so-called 'Edge Localized Modes' (ELM), reducing by a factor of 2 the energy expelled by each ELM. In particular, it was possible to considerably reduce the statistical dispersion of the repetition frequency of ELM, and to avoid the appearance of gigantic ELM that are particularly harmful for reactor operation. The effect of plasma internal relaxation

  19. 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.

  20. 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.

  1. Research programme on controlled thermonuclear fusion - Synthesis report 2008

    International Nuclear Information System (INIS)

    Werthmueller, A.

    2009-06-01

    (SINQ). Various research projects at CRPP are directly related to ITER, like the development of the gyrotrons, the hyper-frequency wave launcher and the SULTAN facility to test the superconductors of ITER. Besides, the CRPP organized the 22 nd IAEA Fusion Energy Conference in Geneva in October 2008. The interest for rhodium as a material for the first mirror in ITER is growing. At the Basel University, thin layers of rhodium have been deposited on a polished surface by magnetron sputtering. The gas pressure during the deposition has an influence on the optical properties of the rhodium film. The layer survived under erosion conditions in real tokamaks but the reflectivity decreased after exposure. The mirror surface is cleaned by hydrogen glow discharges before detailed optical characterization. In the case of a molybdenum mirror exposed in the tokamak TEXTOR, the reflectivity could not be completely recovered because of the presence of molybdenum carbide at the interface between the molybdenum substrate and the carbon film. At the international level, the various research programmes on fusion are coordinated in the framework of EURATOM. The 'Implemented Agreements' (IA) of the International Energy Agency (IEA) cover numerous studies related to plasma physics, materials and socio-economical aspects of fusion energy. The Swiss researchers are involved in two of these IA, one on material research (EPFL and PSI) and the other on the interaction between plasma and reactor walls (Basel University)

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

    International Nuclear Information System (INIS)

    1992-01-01

    This document provides a very brief report on the final Research Co-ordination Meeting of this Co-ordinated Research Project (CRP): the final report on the CRP will be published by the IAEA in the IAEA-TECDOC series. The present document contains a detailed proposal for a new Co-ordinated Research Programme on ''Stable Isotope Tracer Techniques for Studies on Protein-Energy Interactions'', and a brief series of notes on stable isotopic methods for investigating protein and amino-acid metabolism in man. Refs

  3. Insider Research as Part of a Master's Programme: Opportunities Lost and Found within Action Learning Sets

    Science.gov (United States)

    Milano, Chloe; Lawless, Aileen; Eades, Elaine

    2015-01-01

    This account explores the role of action learning during and after an educational programme. We focus on the final stage of a master's programme and the insider research that is a key feature in many UK universities. Researching within one's own organization should lead to individual and organizational learning. However, there is relatively little…

  4. 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

  5. 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

  6. 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

  7. 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

  8. An IPSN research programme to resolve pending LOCA issues

    International Nuclear Information System (INIS)

    Mailliat, A.; Grandjean, C.; Clement, B.

    2001-01-01

    Studies performed in IPSN and elsewhere pointed out that high burnup may induce specific effects under LOCA conditions, especially those related with fuel relocation. Uncertainties exist regarding how much these effects might affect the late evolution of the accident transient and the associated safety issues. IPSN estimates that a better knowledge of specific phenomena is required in order to resolve the pending uncertainties related to LOCA criteria. IPSN is preparing the so called APRP-Irradie (High Burnup fuel LOCA) programme. One of the important aspect of this programme is in-pile experiments involving bundle geometries in the PHEBUS facility located at Cadarache, France. A feasibility study for such an experimental programme is underway and should provide soon, a finalized project including cost and schedule aspects. (authors)

  9. 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

  10. 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.

  11. 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)

  12. 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.

  13. Aeroelastic Research Programme EFP-2000; Forskning i Aeroelasticitet - EFP-2000

    Energy Technology Data Exchange (ETDEWEB)

    Aagaard Madsen, H. (ed.)

    2001-07-01

    The report presents the main results achieved within (Program for forskning i aeroelasticitet EFP-2000), which is a project carried out in collaboration between Risoe, DTU and the wind turbine industry. The project period has been 2000-2001 and it is the fourth period of a five years research program on aeroelasticity initiated in 1997. Within the present period the project has comprised the following six milestones: a.) status on 2D and 3D CFD computations b.) implementation of improved aerodynamic and structural sub models in the aeroelastic codes FLEX4 and HAWC c.) design of an airfoil family with high maximum lift d.) determination of the potential in prediction of dynamic stability e.) analysis of the uncertainty in computation of design loads f.) guidelines for optimised blade dynamics Within the project important results have been obtained and in particular within the following three main ares: 1) verification, development and application of 2D and 3D CFD computation on airfoils an rotors; 2) dynamic stability of a complete wind turbine structure; 3) importance of non-linearity's related to big blade deflections. The development of rotor computations with the 3D CFD code EllipSys3D has been an important research area since the start of the aeroelastic research programme in 1997, where initial results of 3D computations on a rotor were presented. However, first within the present project a verification of these 3D rotor computations has been possible. A blind test of rotor codes was carried out by NREL in USA using experimental data from a comprehensive wind tunnel experiment on a 10 m rotor. Out of about 20 different codes EllipSys3D gave results with the best correlation with the experimental data and in particular the 3D effect on the airfoil characteristics was well predicted. Within the research area on dynamic stability a simple, linear structural model has been developed enabling the computation of a Cambell diagram within a few seconds. Such a

  14. Embedding operational research into national disease control programme: lessons from 10 years of experience in Indonesia

    Directory of Open Access Journals (Sweden)

    Yodi Mahendradhata

    2014-10-01

    Full Text Available There is growing recognition that operational research (OR should be embedded into national disease control programmes. However, much of the current OR capacity building schemes are still predominantly driven by international agencies with limited integration into national disease control programmes. We demonstrated that it is possible to achieve a more sustainable capacity building effort across the country by establishing an OR group within the national tuberculosis (TB control programme in Indonesia. Key challenges identified include long-term financial support, limited number of scientific publications, and difficulties in documenting impact on programmatic performance. External evaluation has expressed concerns in regard to utilisation of OR in policy making. Efforts to address this concern have been introduced recently and led to indications of increased utilisation of research evidence in policy making by the national TB control programme. Embedding OR in national disease control programmes is key in establishing an evidence-based disease control programme.

  15. 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

  16. National programme for weather, climate and atmosphere research. Annual report 1984/85

    CSIR Research Space (South Africa)

    Louw, CW

    1984-12-01

    Full Text Available This report reviews the activities of the National Programme for Weather, Climate and Atmosphere Research (NPWCAR) for 1984/85, highlights the findings and also discusses future developments and general needs regarding research within the framework...

  17. Research programme on controlled thermonuclear fusion - Synthesis report 2010

    International Nuclear Information System (INIS)

    Vaucher, C.; Tran, M. Q.; Villard, L.; Marot, L.

    2011-01-01

    Since 1978, research on thermonuclear fusion in Switzerland is closely related to the research programme of the European Atomic Energy Community (EURATOM). The Swiss projects tackle aspects of plasma physics and fusion technology. Switzerland participates to the construction and operation of the Joint European Torus (JET). The International Thermonuclear Experimental Reactor (ITER) is being built; the first plasma is expected in 2019. The 'Centre de Recherches en Physique des Plasmas' (CRPP) of the EPFL participates to EURATOM scientific and technological projects in magnetic confinement physics, through an experimental contribution (the Variable Configuration Tokamak, TCV) and theoretical studies. Thanks to the large flexibility of the TCV design and operation modus, plasmas of different shapes can be created and controlled, what is a very useful option to verify numerical simulation results. Besides, the injection of millimetre waves allows directing the injected power according to specific profiles. A configuration of type 'snowflakes' could be created, reducing the power deposition at the edge of the plasma. Theoretical studies on turbulence have improved the plasma stability in the TCV. For the first time in the world, TCV could reach a stable plasma, the plasma current being generated using the so-called 'bootstrap' phenomenon. Besides turbulence, studies were focused on heat and particle transport in tokamaks, on an analysis of the equilibrium and magneto-hydrodynamic stability of tokamaks and stellarators, on the application of radiofrequency waves and on the optimization of new confinement configurations. Experiments in the JET facility confirmed the numerical results of theoretical simulations. The TORPEX facility, which is simpler than TCV, allows high space-temporal resolution measurements for the study of turbulences and plasma threads ('blobs'). At the Paul Scherrer Institute (PSI), research topics include superconductivity and materials. The Fusion

  18. Synthetic report 2012. Research programme on controlled thermonuclear fusion

    International Nuclear Information System (INIS)

    Vaucher, C.; Tran, M. Q.; Villard, L.; Marot, L.

    2013-01-01

    Since 1961, Switzerland participates in the research on thermonuclear fusion thanks to the creation of the Research Centre in Plasma Physics. In 1979 it entered into partnership with the European programme on fusion through its adhesion to EURATOM. The thermonuclear fusion is an interesting energy source because the basic fuel is practically inexhaustible and its use does not release any significant CO 2 quantity and very little radioactive residues. But its working up faces enormous physical and technological difficulties. The International Thermonuclear Reactor (ITER), presently in construction, has to demonstrate the technological feasibility of the controlled fusion. Il will be followed by DEMO, foreseen for 2040-2050, which must guarantee the economical rentability. At CRPP the research projects are partitioned onto several sites: at the Swiss Federal Institute of Technology (EPFL) in Lausanne, they concern the physics of the magnetic confinement with the Variable Geometry Tokamak (TCV), the development of theoretical models and the numerical simulation, the plasma heating and the generation of hyper frequency waves; the Paul Scherrer Institute (PSI) studies the superconductivity and the materials; the interactions between the plasma and the Tokamak walls are studied at the Basel University for the structures of ITER. Thanks to its large flexibility, TCV allows the creation and the control of plasmas of very different forms. The injection system of millimetric waves allows orienting the injected power according to specific profiles. By using the asymmetry of the flow in the toroidal sense, the plasma rotation could be measured with a much better accuracy than before. In TCV, by playing on the form of the plasma, it was possible to strongly reduce the energy quantity which is expelled by the Edge Localized Modes (ELM) onto the wall of the vacuum chamber. The ‘snowflake’ configuration created in TCV allows distributing the ELM energy onto several impact

  19. South African Antarctic research programme 1978-1982

    CSIR Research Space (South Africa)

    SASCAR

    1978-12-01

    Full Text Available This document provides a comprehensive review of the planned South African scientific activities in Antarctica and on the sub-Antarctic islands in the five year period starting in 1978. The scientific programmes are classified under five headings...

  20. 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

  1. 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

  2. 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

  3. 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.)

  4. 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.

  5. 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

  6. 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

  7. Moving knowledge into action for more effective practice, programmes and policy: protocol for a research programme on integrated knowledge translation.

    Science.gov (United States)

    Graham, Ian D; Kothari, Anita; McCutcheon, Chris

    2018-02-02

    Health research is conducted with the expectation that it advances knowledge and eventually translates into improved health systems and population health. However, research findings are often caught in the know-do gap: they are not acted upon in a timely way or not applied at all. Integrated knowledge translation (IKT) is advanced as a way to increase the relevance, applicability and impact of research. With IKT, knowledge users work with researchers throughout the research process, starting with identification of the research question. Knowledge users represent those who would be able to use research results to inform their decisions (e.g. clinicians, managers, policy makers, patients/families and others). Stakeholders are increasingly interested in the idea that IKT generates greater and faster societal impact. Stakeholders are all those who are interested in the use of research results but may not necessarily use them for their own decision-making (e.g. governments, funders, researchers, health system managers and policy makers, patients and clinicians). Although IKT is broadly accepted, the actual research supporting it is limited and there is uncertainty about how best to conduct and support IKT. This paper presents a protocol for a programme of research testing the assumption that engaging the users of research in phases of its production leads to (a) greater appreciation of and capacity to use research; (b) the production of more relevant, useful and applicable research that results in greater impact; and (c) conditions under which it is more likely that research results will influence policy, managerial and clinical decision-making. The research programme will adopt an interdisciplinary, international, cross-sector approach, using multiple and mixed methods to reflect the complex and social nature of research partnerships. We will use ongoing and future natural IKT experiments as multiple cases to study IKT in depth, and we will take advantage of the team

  8. Research Market Gap in Law Enforcement Technology: Lessons from Czech Security Research Funding Programmes

    Directory of Open Access Journals (Sweden)

    Luděk Moravec

    2014-12-01

    Full Text Available While security research funding schemes are nothing new to the EU (Horizon 2020 and FP7, or to several Member States, their priorities and procedures are usually decided administratively or shaped by advisory groups of varying membership. Only recently did the EU shift its focus to the role of end users in security research programmes, seeking their input in order to maximise the utility of funded solutions. Such a hint to limited usefulness of some industrial solutions is not exactly inconspicuous. This paper discusses the gap between the stated needs of law enforcement agencies in terms of R&D funding and the grant project applications in the area of law enforcement. It aims to define and describe the gap, and consequently the market opportunities, between the supply and demand sides represented by industry-driven grant project applications and end-user-formulated calls. The study is based on empirical data from two Czech security research funding programmes that have been running since 2010 and should deliver their results by 2015. It seeks to contribute some preliminary observations about the structure of both end user needs and industry capabilities in such a particular area as law enforcement technology.

  9. Measurements of Mode Converted Ion Cyclotron Wave with Phase Contrast Imaging in Alcator C-Mod and Comparisons with Synthetic PCI Simulations in TORIC

    International Nuclear Information System (INIS)

    Tsujii, N.; Porkolab, M.; Edlund, E. M.; Lin, L.; Lin, Y.; Wright, J. C.; Wukitch, S. J.

    2009-01-01

    Mode converted ion cyclotron wave (ICW) has been observed with phase contrast imaging (PCI) in D- 3 He plasmas in Alcator C-Mod. The measurements were carried out with the optical heterodyne technique using acousto-optic modulators which modulate the CO2 laser beam intensity near the ion cyclotron frequency. With recently improved calibration of the PCI system using a calibrated sound wave source, the measurements have been compared with the full-wave code TORIC, as interpreted by a synthetic diagnostic. Because of the line-integrated nature of the PCI signal, the predictions are sensitive to the exact wave field pattern. The simulations are found to be in qualitative agreement with the measurements.

  10. Radiation protection research and training programme, radiation protection programme revision 1988-89, post-Chernobyl actions executive summaries

    International Nuclear Information System (INIS)

    1990-01-01

    The CEC radiation protection research programme has taken several important initiatives to address the scientific problems created by the Chernobyl accident. It has defined additional research requirements, reoriented some existing research contracts and strategically placed some new contracts. It also asked for a revision of the current 1985-89 programme to deal with some particularly urgent issues: evaluation of data on the transfer of radionuclides in the food chain; improvement of reliable long-distance atmospheric transport models; radiological aspects of nuclear accident scenarios: (a) real-time emergency response systems, (b) the RADE-AID system; monitoring and surveillance in accident situations; underlying data for derived emergency reference levels; improvement of practical countermeasures against nuclear contamination in the agricultural environment; improvement of practical countermeasures against nuclear contamination in the urban environment; improvement of practical countermeasures: preventive medication; treatment and biological dosimetry of exposed persons; feasibility of studies on health effects due to the reactor accident at Chernobyl. This synopsis aims to present, in an easily understandable way, the rationale for and the principal results of the research undertaken in this area. As a whole, this research has considerably improved Community ability to handle such emergency situations and has developed the cohesion of Community science

  11. Abstracts of the International seminar 'Experimental possibilities of KTM tokamak and research programme'

    International Nuclear Information System (INIS)

    2005-01-01

    The International seminar 'Experimental possibilities of KTM tokamak and research programme' was held in 10-12 October 2005 in Astana city (Kazakhstan). The seminar was dedicated to problems of KTM tokamak commissioning. The Collection of abstracts comprises 45 papers

  12. The comparison and coordination of national policies and programmes in the energy research and development sector

    International Nuclear Information System (INIS)

    1978-01-01

    Inventory of programmes and expenditures in the field of energy research and development, which are financed from the public sector funds of the Member States and of the European Communities (1974-1976)

  13. Nylsvley - South African Savanna ecosystem project: objectives, organisation and research programme

    CSIR Research Space (South Africa)

    Huntley, BJ

    1978-03-01

    Full Text Available A description of the objectives, organization and research programme of the Savanna Ecosystem Project being undertaken at Nylsvley in the northern Transvaal is presented. The project is a cooperative multi-disciplinary study of the structure...

  14. Nuclear techniques for toxic elements in foodstuffs. Report on an IAEA co-ordinated research programme

    International Nuclear Information System (INIS)

    1994-01-01

    The document includes 10 final reports on the IAEA Co-ordinated Research Programme on Nuclear Techniques for Toxic Elements in Foodstuffs. A separate abstract was prepared for each report. Refs, figs and tabs

  15. Nuclear techniques for toxic elements in foodstuffs. Report on an IAEA co-ordinated research programme

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-12-31

    The document includes 10 final reports on the IAEA Co-ordinated Research Programme on Nuclear Techniques for Toxic Elements in Foodstuffs. A separate abstract was prepared for each report. Refs, figs and tabs.

  16. 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)

  17. 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

  18. Energy and environment at a crossroads - perspectives from the social studies of the SAMRAM research programme

    International Nuclear Information System (INIS)

    Roevik, Arne Oe.

    2001-01-01

    Leading abstract. The research programme SAMRAM was carried out by the Research Council of Norway in 1996-2000. The present book contains twelve articles based on the results of the programme. The articles are grouped in three main sections: (1) The energy markets - environmental effects, innovation and consumption, (2) Energy and environmental policy - international relations and national instruments, (3) Instruments of the energy- and environmental policy - motivation and behaviour

  19. Planetary physics research programme at the Facility for Antiprotons and Ion Research at Darmstadt

    Energy Technology Data Exchange (ETDEWEB)

    Tahir, N.A.; Neumayer, P.; Bagnoud, V. [Department of Plasma Physics, GSI Helmholtzzentrum fuer Schwerionenforschung, Darmstadt (Germany); Lomonosov, I.V. [Institute of Problems of Chemical Physics, Russian Academy of Sciences, Chernogolovka (Russian Federation); Tomsk University, Tomsk (Russian Federation); Lomonosov Moscow State University, Moscow (Russian Federation); Moscow Institute of Physics and Technology, Dolgoprudny (Russian Federation); Borm, B. [Department of Physics, Goethe-Universitaet Frankfurt, Frankfurt (Germany); Piriz, A.R.; Piriz, S.A. [E.T.S.I. Industrials, University of Castilla-La Mancha, Ciudad Real (Spain); Shutov, A. [Institute of Problems of Chemical Physics, Russian Academy of Sciences, Chernogolovka (Russian Federation)

    2017-11-15

    Planetary physics research is an important part of the high energy density (HED) physics programme at the Facility for Antiprotons and Ion Research (FAIR) at Darmstadt. In this paper, we report numerical simulations of a proposed experiment named LAboratory PLAnetary Sciences (LAPLAS). These simulations show that in such experiments, an Fe sample can be imploded to extreme physical conditions that are expected to exist in the interior of the Earth and in the interior of more massive rocky planets named, super-Earths. The LAPLAS experiments will thus provide very valuable information on the equation-of-state (EOS) and transport properties of HED Fe, which will help the scientists to understand the structure and evolution of the planets in our solar system and of the extrasolar system planets. (copyright 2017 WILEY-VCH Verlag GmbH and Co. KGaA, Weinheim)

  20. Planetary physics research programme at the Facility for Antiprotons and Ion Research at Darmstadt

    International Nuclear Information System (INIS)

    Tahir, N.A.; Neumayer, P.; Bagnoud, V.; Lomonosov, I.V.; Borm, B.; Piriz, A.R.; Piriz, S.A.; Shutov, A.

    2017-01-01

    Planetary physics research is an important part of the high energy density (HED) physics programme at the Facility for Antiprotons and Ion Research (FAIR) at Darmstadt. In this paper, we report numerical simulations of a proposed experiment named LAboratory PLAnetary Sciences (LAPLAS). These simulations show that in such experiments, an Fe sample can be imploded to extreme physical conditions that are expected to exist in the interior of the Earth and in the interior of more massive rocky planets named, super-Earths. The LAPLAS experiments will thus provide very valuable information on the equation-of-state (EOS) and transport properties of HED Fe, which will help the scientists to understand the structure and evolution of the planets in our solar system and of the extrasolar system planets. (copyright 2017 WILEY-VCH Verlag GmbH and Co. KGaA, Weinheim)

  1. 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

  2. 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)

  3. 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

  4. The Medical Activation Analysis Research Programme of the IAEA Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Parr, R. M. [Medical Applications Section, International Atomic Energy Agency, Vienna (Austria)

    1970-07-01

    Analyses carried out under the Agency's laboratory programme in medical activation analysis commended in 1967. This paper describes the laboratory facilities and experimental methods now in use, and reports briefly on results obtained to date. The analytical scheme places greatest emphasis on non-destructive methods (i.e. without radiochemistry), and by the use of a Ge(Li) detector and a 2-parameter Nal(Tl) gamma-ray spectrometer, presently allows the determination of up to 12 elements in unprocessed tissue samples. Projects completed or underway include (i) an investigation into the uniformity of distribution of mineral elements in human liver, (ii) studies of tissue concentrations of trace elements in relation to malnutrition and cardiovascular diseases, and (iii) the determination of iodine in food, natural waters and other biological materials in relation to the epidemiology of endemic goitre. (author)

  5. 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

  6. The Ademe research programme on atmospheric emissions from composting. Research findings and literature review - final report

    International Nuclear Information System (INIS)

    Deportes, Isabelle; Mallard, Pascal; Loyon, Laurence; Guiziou, Fabrice; Fraboulet, Isaline; Clincke, Anne-Sophie; Fraboulet, Isaline; Tognet, Frederic; Bessagnet, Bertrand; Durif, Marc; Poulleau, Jean; Bacheley, Helene; Delabre, Karine; Zan-Alvarez, Patricia; Gourland, Pauline; Wery, Nathalie; Moletta-Denat, Marina; Deportes, Isabelle; Stavrakakis, Christophe; Schlosser, Olivier; Decottignies, Virginie; Akerman, Anna; Martel, Jean Luc; Senante, Elena; Givelet, Arnaud; Batton-Hubert, Mireille; Vaillant, Herve; Chovelon, Jean-Marc; Pradelle, Frederic; Sassi, Jean-Francois; Teigne, Delphine; Duchaine, Caroline; Jean, Thierry; Lavoie, Jacques; Le Cloarec, Pierre; Levasseur, Jean-Pierre; Morcet, Muriel; Rivet, Marie; Romain, Anne-Claude

    2012-07-01

    Emissions of gas and particulates (dusts, mineral and organic) linked to composting wastes essentially come from the biodegradation of organic matter by micro-organisms and from the related site management activities, especially material handling (of the raw waste, mixes and compost): movements, turning, sieving and loading. Carbon dioxide (CO 2 ) is, in terms of mass, the main gas produced (along with water vapor) during composting. However, many other gases emitted in small amounts can also have a major impact on the environment and/or health risks. Such is the case for nitrous oxide (N 2 O) and methane (CH 4 ) with respect to global warming, and also for ammonia (NH 3 ) with respect to acidification and eutrophication of the local environment, and of a wide range of sulfur-based and volatile organic compounds which can potentially lead to very unpleasant (or offensive) odors and health risks. In the case of emitted dust particles, these can often carry micro-organisms and/or biological compounds with the known health effects of inflammation, allergic reactions and infection. Thus dealing with these emissions and the evaluation of their health and environmental impacts represents key aspects in the long term sustainability of the composting option. Even if the understanding of these emissions remains incomplete, taking into account the wide range of solid wastes treated and of the methods of composting available, efforts have been made these last years to better characterize the substrate and to improve the related measurement methods. ADEME launched in 2006 a research programme specifically addressing this theme in particular, involving many research organizations, technical centres, research consultancies and industrial partners. The work carried out in this framework has enabled an improvement in the knowledge of characterizing emissions, of their sources and controlling factors, of their metrology (whether at the source or within the environment around

  7. BMFT. Partial programme ocean research. Annual report 1991

    International Nuclear Information System (INIS)

    1992-01-01

    The project sponsors 'Biology, energy, ecology' and 'Materials and raw materials research' at Forschungszentrum Juelich GmbH were charged by the Federal Ministry for Research and Technology with the supervision of the promotion of the 'Marine research' subprogram. A summary is given of marine research programs promoted in 1991. These programs covered marine pollution analysis and monitoring (research and development), marine biology (research into marine ecosystems), marine research equipment and methods, maritime meteorology (research into maritime climates), new and unconventional marine nutrition sources (aquaculture), investigation of biological and technological aspects relevant to fishery, international cooperation and marine geosciences. A general survey is given of the promoted projects, and the individual activities are briefly described on standardized data sheets. The appendix gives project and joint-project indices and a list of firms and companies. (orig./BBR) [de

  8. Aquaculture in South Africa: A cooperative research programme

    CSIR Research Space (South Africa)

    Safriel, O

    1984-06-01

    Full Text Available the industry on a sound footing. An Aquaculture Working Group was appointed by the CSIR in 1981, which developed a research strategy, identified needs and suggested priorities for research on major problem areas in aquaculture....

  9. 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

  10. 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

  11. 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.)

  12. Evaluation of the Dutch National Research Programme on Global Air Pollution and Climate Change. Final Report

    International Nuclear Information System (INIS)

    Guy, K.; Boekholt, P.; Kaellen, E.; Downing, T.; Verbruggen, A.

    2002-02-01

    During 2001, the second phase of the National Research Programme on Global Air Pollution and Climate Change (NOP2) has been evaluated. In the period 1995-2001 the budget for NOP was 47 million Dutch guilders, which supported over 30 organisations in 100 projects and studies spanning four main themes: (1) dynamics of the climate system and its component parts; (2) vulnerability of natural and societal systems to climate change; (3) societal causes and solutions; (4) integration and assessment. Later in the life of the programme, two themes were added to widen the scope of the programme and add value to existing activities. These covered projects concerned with 'cross-cutting' or 'over-arching' issues and those dealing with 'internationalisation', i.e. projects specifically designed to support various initiatives in the development of international programmes. A further proportion of the research budget was dedicated to direct policy support. The evaluation was primarily intended to: Assess the scientific quality of the work undertaken in the programme and the attainment of scientific and technical goals. Also attention was paid to the relevancy of projects and project outputs to national and international policy formulation (policy relevance); the structure and operation of the programme to see if it promoted coherence and synergy between the constituent parts (synergy); and recommendations concerning the form, content and direction of a new programme in the area (new directions)

  13. The Community's research and development programme on decommissioning of nuclear installations (1989-1993). Annual progress report 1991

    International Nuclear Information System (INIS)

    1992-01-01

    This is the second annual progress report of the European Community's programme (1989-93) of research on decommissioning of nuclear installations. It shows the status of the programme on 31 December 1991. This second progress report summarizes the objectives, scope and work programme of the 76 research contracts concluded, as well as the progress of work achieved and the results obtained in 1991

  14. Research and development programme of the EC in the field of raw materials 1982 to 1985

    International Nuclear Information System (INIS)

    Anon.

    1982-01-01

    Brussels: The EC Cabinet Council was presented a research and development programme in the field of raw materials for the years 1982 to 1985 which covers programmes already running and new actions as an overlapping raw material research programme of the EC. The new programme is divided up into 7 subprogrammes: I) metals and minerals (formerly: primary raw materials, II) uranium, III) ceramics, IV) wood as a renewable raw material, V) recycling of wastes (house and industry, VI) regaining of non-iron metals, VII) substitution. For the continuing of running actions and for beginning new projects in the 4 years plan, a total of 17 million ECU are to be allocated in the budget of the EC which will be used in cost sharing contracts or for coordinative projects. (orig./UA) [de

  15. Organisation of safety research programmes and infrastructure for existing reactors

    International Nuclear Information System (INIS)

    Micaelli, J.C.

    2008-01-01

    The author reviewed the main drivers of safety research, noting that challenging research is an excellent means to preserve know-how and professional skills. International efforts such the NEA-CSNI joint projects are an efficient means to support experimental infrastructure for safety research, while providing useful experimental results. Other initiatives, e.g. within the EU, aimed at developing networks of international expertise and infrastructure were also mentioned. (author)

  16. Research programme on the conditioning of nuclear power waste

    International Nuclear Information System (INIS)

    Hultgren, Aa.

    1981-01-01

    Main parts of this programme have included the use of zeolites and titanates to improve reactor waste treatment, the fractionation of high level reprocessing waste by extraction, and a study of liquid partition chromotographic technique for the removal of impurities from reactor cooling circuits. Preparation of large crystal zeolites has been continued and refined. For titanate production new routes are tried to produce material of a form suitable for use in a sorption process. The possibility of lithium-7 recovery from spent PWR resins in the elution process is under study. Final products from different routes of heat treatment of loaded zeolites and titanates are characterized and compared. In parallell to this work a full-scale system is under study including transport, system design, integrated process flowsheets and cost estimates. The aim is to have basis early in 1982 to decide on the merits of a plant at the planned repository for low and medium level waste (SFR), to be commissioned around 1990. In the high level waste fractionation project, a demonstration of the developed process has been performed on a fission product solution from the reprocessing of low burn-up fuel. Disregarding some equipment malfunction the design goal of better than 99.99 % actinide removal from the high level waste waste solution was reached. The basic chemistry of the process seems to be quite tolerant against reasonable flow rate deviations in the extraction cycles. Also the concluding sorption step on mordenite-titanate worked quite well. The small scale experiments on liquid partition chromatographic techniques have included studies of the capacity of various carrier materials treated with NH 4 DEHP or Aliquat-336 to sorb radioactive impurities from reactor water, both in the laboratory and at the Ringhals-1 BWR. (author)

  17. Discussion forum for researchers in nuclear geology. Programme and abstracts

    International Nuclear Information System (INIS)

    Brynard, H.J.

    1986-11-01

    The Atomic Energy Corporation of SA Ltd (AEC) sponsors research in nuclear geology at several South African universities with a view to delineating target areas for uranium prospecting by mining companies. In order to ensure the efficient co-ordination of this research an annual meeting is held where sponsored researchers and other organizations report on their progress during the year. This ensures valuable cross-pollination of ideas, and an input from the mining industry is gained as to which direction future research should take. The results of the researchers reported on at these meetings is not necessarily complete and the abstracts in this volume should therefore not be regarded as conclusive. In this discussion forum uranium in granites and uranium in sedimentory deposits are covered. The geochemical anomalies of uranium as well as the geohydrology and its application in defining uranium are also discussed

  18. The Swedish fusion research programme on magnetic confinement 1978

    International Nuclear Information System (INIS)

    Lehnert, B.

    1978-02-01

    A review is given on the activities and plans for research on plasma physics and controlled fusion at the Royal Institute of Technology in Stockholm, with descriptions and motivations of the research lines being conducted. These activities include investigations on plasma-neutral gas interaction, development of special principles for plasma stabilization, magnetic confinement schemes being based mainly on poloidal fields, as well as the generation, heating, and diagnostics of plasmas being ''impermeable'' to neutral gas. (author)

  19. Trend report Energy Research Subsidy programme (2005-2008). A report on the most important trends and effects since the start of the Energy Research Subsidy (EOS) programme

    International Nuclear Information System (INIS)

    Kimman, J.; Soeriowardojo, E.; Witte, F.; Nijdam, J.

    2009-07-01

    In 2005 the Energy Research Subsidy programme (EOS) was launched in the Netherlands. In four years' time about 500 projects were realized thanks to contributions from EOS. This report provides an overview of the main trends and effects of EOS in the period 2005-2008. One of the main conclusions is that a number of technologies have developed from invention level to market-ready level thanks to the EOS programme. The main trends since the start of EOS are: Increasing confidence of investors in EOS spearheads; increasing activity in EOS spearheads; Spearheads shifting to investment and exploitation schemes; EOS contributes to a solid patent position of Dutch parties; EOS contributes to European research. [nl

  20. 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)

  1. Seminar on the use of research reactors in fundamental and applied sciences. Programme and abstracts

    International Nuclear Information System (INIS)

    1984-01-01

    The document includes the programme and the abstracts of papers presented at the ''Seminar on the use of research reactors in fundamental and applied sciences'' organized by the Tajoura Nuclear Research Centre in cooperation with the IAEA at Tajoura, Tripoli (Libya) between 16-20 September 1984. The abstracts are grouped in seven sessions: reactor physics (five abstracts), research reactor programmes (three abstracts), solid state physics (two abstracts), nuclear physics (two abstracts), radiochemistry (eleven abstracts), activation analysis (five abstracts), diverse topics (six abstracts). Separate indexing was provided for each abstract

  2. Climate change and Finland. Summary of the Finnish research programme on climate change (SILMU)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-12-31

    Anthropogenic impacts on the Earth`s atmosphere are expected to cause significant global climate changes during the next few decades. These changes will have many consequences both in nature and on human activities. In order to investigate the implications of such changes in Finland, a six-year multidisciplinary national research programme on climate and global change, the Finnish Research Programme on Climate Change (SILMU), was initiated in 1990. The key research areas were: (1) quantification of the greenhouse effect and the magnitude of anticipated climate changes, (2) assessment of the effects of changing climate on terrestrial and aquatic ecosystems, and (3) development of mitigation and adaptation strategies

  3. 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)

  4. Climate change and Finland. Summary of the Finnish research programme on climate change (SILMU)

    International Nuclear Information System (INIS)

    1996-01-01

    Anthropogenic impacts on the Earth's atmosphere are expected to cause significant global climate changes during the next few decades. These changes will have many consequences both in nature and on human activities. In order to investigate the implications of such changes in Finland, a six-year multidisciplinary national research programme on climate and global change, the Finnish Research Programme on Climate Change (SILMU), was initiated in 1990. The key research areas were: (1) quantification of the greenhouse effect and the magnitude of anticipated climate changes, (2) assessment of the effects of changing climate on terrestrial and aquatic ecosystems, and (3) development of mitigation and adaptation strategies

  5. 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

  6. 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)

  7. Leveraging the Relationship: Knowledge Processes in School-University Research Networks of Master's Programmes

    Science.gov (United States)

    Cornelissen, Frank; Daly, Alan J.; Liou, Yi-Hwa; Van Swet, Jacqueline; Beijaard, Douwe; Bergen, Theo C. M.

    2015-01-01

    This study investigated the way developing, sharing and using of research-based knowledge occurred in the school-university research network of a master's programme for in-service teachers in the Netherlands. Over a 10-month period, a combination of quantitative and qualitative network data was collected. Data were analysed at three network…

  8. What Can the Work of Habermas Offer Educational Researcher Development Programmes?

    Science.gov (United States)

    Garland, Paul

    2014-01-01

    Although certain aspects of the work of Habermas have had much influence on emancipatory and action research, this article draws on a wider range of his thinking in order to explore how his ideas can inform the content and process of educational researcher development programmes. Habermas's theory of communicative action, his discourse ethics…

  9. Relationship between accidents and road user behaviour : an integral research programme.

    NARCIS (Netherlands)

    Noordzij, P. & Horst, A.R.A. van der

    1993-01-01

    The analysis of accident statistics and the study of road user behaviour are the traditional methods of road safety research. Neither of these involve direct observation of accidents. A research programme has been designed in order to: (1) gain insight into the generation process of traffic

  10. Relationship between accidents and road user behaviour : an integral research programme.

    NARCIS (Netherlands)

    Noordzij, P.C. & Horst, A.R.A. van der

    1996-01-01

    The analysis of accident statistics and the study of road user behaviour are the traditional methods of road safety research. Neither of these involve direct observation of accidents. A research programme has been designed to gain insight in the generation process of traffic accidents as well as to

  11. Reconciling collaborative action research with existing institutions: insights from Dutch and German climate knowledge programmes

    NARCIS (Netherlands)

    Termeer, C.J.A.M.; Buuren, van A.; Knieling, J.; Gottschick, M.

    2015-01-01

    Researchers and policymakers increasingly aim to set up collaborative research programmes to address the challenges of adaptation to climate change. This does not only apply for technical knowledge, but for governance knowledge also. Both the Netherlands and Germany have set up large scale

  12. 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)

  13. Humanities Research Methods in a Liberal Arts and Science Programme

    NARCIS (Netherlands)

    Andeweg, A.; Slob, Daphne

    2017-01-01

    The humanities research methods course at University College Utrecht is one of the graduation requirements for students who major in a humanities discipline, in law, or in politics. There are several challenges to the design of such a course in a Liberal Arts and Sciences (LA&S) context. In our

  14. GSI research and development programme 1983-85

    International Nuclear Information System (INIS)

    1982-01-01

    In this report the research program of the GSI Darmstadt is described. This program concerns heavy ion reactions, atomic collisions with heavy ions, and applications of heavy ion beams in other fields of science. Furthermore the future development of accelerators and detection methods is described. (HSI) [de

  15. A Linguistic Research Programme for Reading in African ...

    African Journals Online (AJOL)

    Although ANAs show language conditioned problems in reading comprehension and decoding ability, most South African research focuses disproportionately on ... Obviously African languages are structurally and typologically different to English and Afrikaans; reading strategies required for the mechanics of reading are ...

  16. 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

  17. 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)

  18. 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.

  19. 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.

  20. The EU research activities on partitioning and transmutation. From the 4. to the 5. framework programme

    International Nuclear Information System (INIS)

    Hugon, M.

    1999-01-01

    The European Commission is partly supporting research work on partitioning and transmutation of radioactive waste under the Fourth Framework Programme (1994-1998). This work includes nine research projects. Five strategy studies are evaluating the capabilities of various burners and fuel cycles to limit the production and even destroy the stock of actinides (plutonium and minor actinides). Two experimental projects are aiming at developing techniques for the chemical separation of actinides and two others are dealing with the investigation of transmutation of americium and long-lived fission products. The objectives of these studies are described together with the main results already obtained. The European Union should adopt the 5. Framework Programme (1998-2002) at the end of 1998. The broad lines of the research activities foreseen in partitioning and transmutation and future system under the 5. Framework Programme are briefly presented. (author)

  1. 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.)

  2. 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

  3. 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

  4. 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)

  5. 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.)

  6. RATU - Nuclear power plant structural safety research programme

    International Nuclear Information System (INIS)

    Rintamaa, R.

    1992-07-01

    Studies on the structural materials in nuclear power plants create the experimental data and background information necessary for the structural integrity assessments of mechanical components. The research is carried out by developing experimental fracture mechanics methods including statistical analysis methods of materials property data, and by studying material ageing and, in particular, mechanisms of material deterioration due to neutron irradiation, corrosion and water chemistry. Besides material studies, new testing methods and sensors for measurement of loading and water chemistry parameters have been developed. The monitoring data obtained in real power plants has been used to simulate more precisely the real environment during laboratory tests. The research on structural analysis has focused on extending and verifying the analysis capabilities for structural assessments of nuclear power plants. A widely applicable system including various computational fracture assessment methods has been created with which different structural problems can be solved reliably and effectively. Research on reliability assessment of maintenance in nuclear power plants is directed to practical case studies on components and structures of safety importance, and to the development of models for maintenance related decision support. A systematic analysis of motor-operated valve has been performed

  7. 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.)

  8. 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

  9. 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

  10. 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

  11. Development of Surveillance and In-Service Inspection Programme for Indian Research Reactors Cirus and Dhruva

    International Nuclear Information System (INIS)

    Shukla, D.K.

    2006-01-01

    Many safety requirements for research reactors are quite similar to those of power reactors. For research reactors with a higher hazard potential, the use of safety codes and guides for power reactors is more appropriate. However, there are many important differences between power reactors and research reactors that must be taken into account to ensure that adequate safety margins are available in design and operation of the research reactor. Most research reactors may have small potential for hazard to the public compared to power reactors but may pose a greater potential hazard to the plant operators. The need for greater flexibility in use of research reactors for individual experiments requires a different safety approach. Safety rules for power reactors are required to be substantially modified for application to specific research reactor. Following the intent of the available safety guides for surveillance and In-Service Inspection of Nuclear Power Plants, guidelines were formulated to develop surveillance and In-Service Inspection programme for research reactors Cirus and Dhruva. Based on the specific design of these research reactors, regulatory requirements, the degree of sophistication and experience of the technical organization involved in operating the research reactor, guidelines were evolved for developing and implementing the surveillance and In-Service Inspection programme for research reactors Cirus (40 MWt) and Dhruva (100 MWt) located at Bhabha Atomic Research Centre, Trombay, Mumbai, India. Paper describes the approach adopted for formulation of surveillance and In-service Inspection programme for Dhruva reactor in detail. (author)

  12. 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...

  13. Market-based process and product innovation in the food sector: A Danish research programme

    DEFF Research Database (Denmark)

    Grunert, Klaus G.; Baadsgaard, Allan

    1992-01-01

    This note informs about the Danish MAPP research programme, a collection of 15 research projects aimed at making product and process innovation in the food sector more market-based. The programme, which has an interdisciplinary base, but is geared towards marketing applications, is concerned...... with the organization of the innovation process, the interaction of consumer and producer criteria in product development, the assessment of long-term developments in the market environment and the role distribution system in product innovation. Innovation in both primary production and processing are considered....

  14. 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)

  15. Evaluation of the high-temperature materials programme of the Joint Research Centre (1980-85)

    International Nuclear Information System (INIS)

    Glenny, R.J.E.; Boehm, H.; Gellings, P.J.; Gobin, P.; Lanzavecchia, G.; Nicholaides, C.

    1986-01-01

    This report covers the findings of the external panel of experts set up to evaluate the results of the Community's programme in the field of high-temperature materials (1980-85), carried out at the Petten establishment of the Joint Research Centre. The evaluation covers the quality and relevance of the research, the usefulness of the results and the role played by the JRC in this field at the European level. The report describes and gives comments on the content, structure and management of the five projects constituting the current programme, outlines the methods and procedures used during the evaluation and gives a number of recommendations pertinent to future activities

  16. 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

  17. Small ELM regimes with good confinement on JET and comparison to those on ASDEX Upgrade, Alcator C-mod, and JT-60U

    International Nuclear Information System (INIS)

    Stober, J.; Lomas, P.; Saibene, G.

    2005-01-01

    Since it is uncertain if ITER operation is compatible with type-I ELMs, the study of alternative H-mode pedestals is an urgent issue. This paper reports on experiments on JET aiming to find scenarios with small ELMs and good confinement, such as the type-II ELMs in ASDEX Upgrade, the enhanced D-alpha H-mode in Alcator C-mod or the grassy ELMs in JT-60U. The study includes shape variations, especially the closeness to a double-null configuration, variations of q 95 , density and beta poloidal. H-mode pedestals without type-I ELMs have been observed only at the lowest currents (≤ 1.2 MA), showing similarities to the observations in the devices mentioned above. These are discussed in detail on the basis of edge fluctuation analysis. For higher currents, only the mixed type-I/II scenario is observed. Although the increased inter-ELM transport reduces the type-I ELM frequency, a single type-I ELM is not significantly reduced in size. Obviously, these results do question the accessibility of such small ELM scenarios on ITER, except perhaps the high beta-poloidal scenario at higher q 95 , which could not be tested at higher currents at JET due to limitations in heating power. (author)

  18. Three-dimensional simulation of H-mode plasmas with localized divertor impurity injection on Alcator C-Mod using the edge transport code EMC3-EIRENE

    International Nuclear Information System (INIS)

    Lore, J. D.; Reinke, M. L.; Lipschultz, B.; Brunner, D.; LaBombard, B.; Terry, J.; Pitts, R. A.; Feng, Y.

    2015-01-01

    Experiments in Alcator C-Mod to assess the level of toroidal asymmetry in divertor conditions resulting from poloidally and toroidally localized extrinsic impurity gas seeding show a weak toroidal peaking (∼1.1) in divertor electron temperatures for high-power enhanced D-alpha H-mode plasmas. This is in contrast to similar experiments in Ohmically heated L-mode plasmas, which showed a clear toroidal modulation in the divertor electron temperature. Modeling of these experiments using the 3D edge transport code EMC3-EIRENE [Y. Feng et al., J. Nucl. Mater. 241, 930 (1997)] qualitatively reproduces these trends, and indicates that the different response in the simulations is due to the ionization location of the injected nitrogen. Low electron temperatures in the private flux region (PFR) in L-mode result in a PFR plasma that is nearly transparent to neutral nitrogen, while in H-mode the impurities are ionized in close proximity to the injection location, with this latter case yielding a largely axisymmetric radiation pattern in the scrape-off-layer. The consequences for the ITER gas injection system are discussed. Quantitative agreement with the experiment is lacking in some areas, suggesting potential areas for improving the physics model in EMC3-EIRENE

  19. 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).

  20. The Ar{sup 17+} Ly{sub {alpha}2}/Ly{sub {alpha}1} ratio in Alcator C-Mod tokamak plasmas

    Energy Technology Data Exchange (ETDEWEB)

    Rice, J E; Reinke, M L; Ince-Cushman, A C; Podpaly, Y A [Plasma Science and Fusion Center, MIT, Cambridge, MA (United States); Ashbourn, J M A [Mathematical Institute, University of Oxford, Oxford (United Kingdom); Gu, M F [SSL, University of California Berkeley, CA (United States); Bitter, M; Hill, K [Princeton Plasma Physics Laboratory, Princeton, NJ (United States); Rachlew, E, E-mail: rice@psfc.mit.edu [KTH, Stockholm (Sweden)

    2011-08-28

    High-quality spectra of hydrogen-like Ar{sup 17+} have been obtained from Alcator C-Mod tokamak plasmas using a spatially imaging high-resolution x-ray spectrometer system in an extensive study of the underlying high-n satellite lines. The ratio of Ly{sub {alpha}2} (1S{sub 1/2}-2P{sub 1/2}) to Ly{sub {alpha}1} (1S{sub 1/2}-2P{sub 3/2}) was found to be {approx}0.52 regardless of plasma parameters, which is somewhat greater than the ratio of the statistical weights of the upper n = 2 levels, 0.5. This difference is mainly due to the effects of collisional excitation of fine-structure sub-levels. For the observations presented here, electron densities were in an extended range from 3x10{sup 19} to 4x10{sup 20} m{sup -3} with electron and ion temperatures between 1 and 4 keV. Experimental results are compared to calculations from COLRAD, a collisional-radiative modelling code, and good agreement is shown.

  1. The role of nuclear research centers for the introduction of a nuclear power programme

    International Nuclear Information System (INIS)

    Perovic, B.; Frlec, B.; Kundic, V.

    1977-01-01

    Full development of nuclear energy has imposed a new role on nuclear energy centers. Nuclear technology for different reactor concepts is also now in a phase of high development. Several reactor concepts have been developed for industrial use and electric power production. Development of fast reactors is still under way and needs further research efforts. Having in mind these two main guidelines, research programmes in nuclear energy centers should be geared to the development of the activities vital to the implementation of national nuclear energy programmes. In this respect, national nuclear centers should devote their attention to three major tasks. First, to establish a background for the introduction of nuclear energy into the national energy system and to support a national safety system. Second, to support the national programme by skilled manpower, to provide the basic training in nuclear technology for future staff of nuclear power stations and to assist the universities in establishing the necessary educational programme in nuclear energy. Third, to follow the development of nuclear energy technology for the fast breeder reactor concepts. This paper describes some experience in introducing a new programme to the national nuclear energy centers in Yugoslavia. Recently, Yugoslavia has started building its first nuclear power station. Further introduction of nuclear power stations in the national electric energy system is also planned. This implies the need to reconsider the current nuclear energy programme in the nuclear energy centers. It has been decided to evaluate past experience and further needs for research activities regarding the nuclear power programme. Yugoslavia has three main nuclear energy centers whose activities are devoted to the development of national manpower in the field of nuclear sciences. Besides these three organizations, there are several others whose activities are concentrated on specific tasks in nuclear technology. In the

  2. The role of care in nutrition programmes: current research and a research agenda.

    Science.gov (United States)

    Engle, P L; Bentley, M; Pelto, G

    2000-02-01

    The importance of cultural and behavioural factors in children's nutrition, particularly with regard to feeding, has been recognized only recently. The combination of evidence regarding the importance of caregiving behaviour for good nutrition, and improved strategies for measuring behaviour have led to a renewed interest in care. The UNICEF conceptual framework suggests that care, in addition to food security and health care services, are critical for children's survival, growth and development. The present paper focuses on the care practice of complementary feeding, specifically behavioural factors such as parental interaction patterns, feeding style and adaptation of feeding to the child's motor abilities (self-feeding or feeding by others). Three kinds of feeding styles (Birch & Fisher, 1995) are identified: controlling; laissez-faire; responsive. Probable effects of each feeding style on nutrient intake are described. A number of studies of feeding behaviour have suggested that the laissez-faire style is most frequently observed among families and communities with a higher prevalence of malnourished children. Nutrition interventions that have been able to show significant effects on outcomes, such as the Hearth Model in Vietnam (Sternin et al. 1997), have usually incorporated behavioural components in their intervention. At this time, there have been no tests of the efficacy of behavioural interventions to improve feeding practices. Research is needed to understand behavioural factors in complementary feeding, and to identify and test intervention strategies designed to improve nutrient intake of young children. Finally, the paper concludes with a discussion of how nutrition programmes might change if care were incorporated.

  3. Global ocean monitoring for the World Climate Research Programme.

    Science.gov (United States)

    Revelle, R; Bretherton, F

    1986-07-01

    Oceanic research and modelling for the World Climate Research Program will utilize several recently-developed instruments and measuring techniques as well as well-tested, long-used instruments. Ocean-scanning satellites will map the component of the ocean-surface topography related to ocean currents and mesoscale eddies and to fluctuating water volumes caused by ocean warming and cooling. Other satellite instruments will measure the direction and magnitude of wind stress on the sea surface, surface water temperatures, the distribution of chlorophyll and other photosynthetic pigments, the characteristics of internal waves, and possible precipitation over the ocean. Networks of acoustic transponders will obtain a three-dimensional picture of the distribution of temperature from the surface down to mid-depth and of long-term changes in temperature at depth. Ocean research vessels will determine the distribution and fate of geochemical tracers and will also make high-precision, deep hydrographic casts. Ships of opportunity, using expendable instruments, will measure temperature, salinity and currents in the upper water layers. Drifting and anchored buoys will also measure these properties as well as those of the air above the sea surface. Tide gauges installed on islands and exposed coastal locations will measure variations in monthly and shorter-period mean sea level. These tide gauges will provide 'ground truth' for the satellite maps of sea-surface topography, and will also determine variations in ocean currents and temperature.All these instruments will be used in several major programs, the most ambitious of which is the World Ocean Circulation Experiment (WOCE) designed to obtain global measurements of major currents throughout the world ocean, greater understanding of the transformation of water masses, and the role of advective, convective, and turbulent processes in exchange of properties between surface and deep-ocean layers.A five- to ten-year experiment

  4. 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

  5. Food allergy - science and policy needs - The UK Food Standards Agency Research Programme

    International Nuclear Information System (INIS)

    Buck, Joelle; Hattersley, Sue; Kimber, Ian

    2010-01-01

    Food allergy is a significant health issue in the UK, affecting between 1 and 2% of adults and 5 and 8% of children. The UK Food Standards Agency seeks to ensure the safety of food allergic consumers by providing them with information and guidance on food choices. Since 1995, with the aim of addressing important policy issues and improving the quality of the support and guidance available for food allergic consumers, the Agency (and before that the Ministry of Agriculture, Fisheries and Food), has had a programme of research dedicated to investigating the causes and mechanisms of food allergy and delivering benefits for UK consumers. In this paper, we outline some of the major scientific challenges that the programme has sought to address. We reflect on how the findings have been used as a basis for the development of sound, evidence-based policy and advice for UK consumers, and the current direction of research being supported by the programme.

  6. A Critique for the Methodology of Scientific Research Programmes

    Directory of Open Access Journals (Sweden)

    Saeed Naji

    2009-01-01

    Full Text Available The purpose of the paper is to evaluate of Imre Lakatos' MSRP (Methodology of Scientific Research Programs. Presenting the methodology which is based on Popperian Refutationism, Lakatos intended to overcome Pluralism (, Relativism and Skepticism and distinguishes the best theory (/program in science. The question is that did the lakatos' secondary change in the form and content of MSRP -against some historical facts and criticisms- make some serious deficiencies in his methodology? The answer to this question is positive. One of Lakatos' changes in MSRP is to resort to a new concept of "rationality". Presenting a logical analysis, the paper shows that this change causes MSRP to be unable to distinguish the best program among others. Furthermore he gives a new definition of the term 'methodology'. This definition, in its turn, makes MSRP main task to be inactive.Showing the irreparable harms Lakatos' changes produce in MSRP, the paper shows that these changes not only cannot get rid of the deficiencies therein, but it is also unable to meet lakatos' original purpose for MSRP.

  7. Biomass - Overview of Swiss Research Programme 2003; Biomasse

    Energy Technology Data Exchange (ETDEWEB)

    Binggeli, D.; Guggisberg, B.

    2003-07-01

    This overview for the Swiss Federal Office of Energy (SFOE) discusses the results obtained in 2003 in various research projects worked on in Switzerland on the subject of biomass. In the biomass combustion area, subjects discussed include system optimisation for automatic firing, combustion particles, low-particle pellet furnaces, design and optimisation of wood-fired storage ovens, efficiency of filtering techniques and methane generation from wood. Also, an accredited testing centre for wood furnaces is mentioned and measurements made on an installation are presented. As far as the fermentation of biogenic wastes is concerned, biogas production from dairy-product wastes is described. Other projects discussed include a study on eco-balances of energy products, certification and marketing of biogas, evaluation of membranes, a measurement campaign for solar sludge-drying, the operation of a percolator installation for the treatment of bio-wastes, the effects of compost on the environment and the fermentation of coffee wastes. Also, statistics on biogas production in 2002 is looked at. Finally, a preliminary study on biofuels is presented.

  8. Energy and people: considerations for a research programme

    Energy Technology Data Exchange (ETDEWEB)

    Arnoux, L

    1979-01-01

    Energy consumption is closely related to the whole of the consumption cycle. The consumption cycle is a neverending process of accumulation and elimination which is in turn related to the present sociological systems operating in modern industrial countries. Society has produced a complex set of images, symbols, and artificial needs which are all outward signs of a code of value and power. But what the consumer does not realize is that in fact he is possessed by the very objects or values he thinks he owns. These consumer patterns influence energy consumption and energy futures. This paper proposes to explore possible futures taking into account various societal changes within the existing structure and noting that certain behaviors of present marginal groups may prefigure future patterns. The proposals result from a preliminary review of existing research work on the consumption phenomena in relationship with energy use in modern society as presented in papers delivered at the Energy and People Conference, Canberra, 7-9 September 1978.

  9. The community's research and development programme on decommissioning of nuclear power plants. Third annual progress report (year 1982)

    International Nuclear Information System (INIS)

    1984-01-01

    This is the third progress report of the European Community's programme (1979-83) of research on the decommissioning of nuclear power plants. It covers the year 1982 and follows the 1980 and 1981 reports (EUR 7440, EUR 8343). Since 1982 was a very active year of research under the programme, this report contains a large amount of results. Besides, the work programmes of some additional research contracts, awarded through 1982, are described

  10. 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

  11. 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

  12. 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

  13. 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

  14. Energy research 1998. The programme leaders` status reports; Energie-Forschung 1998. Recherche energetique 1998. Ueberblicksberichte der Programmleiter. Rapport de synthese des chefs de programme

    Energy Technology Data Exchange (ETDEWEB)

    Voirol, C. [ed.; Dubal, L. [ed.

    1999-03-01

    This report is a collection of the annual reports written by the 20 energy research programme leaders of the Swiss Federal Office of Energy about their activities in 1998. There is also a report of the Energy Research Coordinator reviewing the progress achieved in 1998. Finally, the organisation of the Swiss energy research is shortly presented, and useful addresses are given

  15. Radioactive waste management: outline of the research programme of the Commission of the European Communities

    International Nuclear Information System (INIS)

    Bresesti, M.

    1980-01-01

    The lines of activity, the main achievements and the perspectives of the research programme of the Commission of the European Communities on radioactive waste management, are presented. In particular an overall view of the activity on chemical separation and nuclear transmutation of actinides is given, as introduction to the various presentations of the JRC staff on specific aspects of this waste management strategy

  16. An Action-Research Programme with Secondary Education Teachers on Teaching and Learning Photosynthesis

    Science.gov (United States)

    Domingos-Grilo, Paula; Reis-Grilo, Carlos; Ruiz, Constantino; Mellado, Vicente

    2012-01-01

    We describe part of an action-research programme in Spain which was based on metacognitive reflection. The participants were four science teachers in a secondary school during the 2004-05 and 2005-06 academic years. During the study, they each analysed their own pupils' alternative ideas on photosynthesis and their teaching methods as recorded in…

  17. Programme Implementation in Social and Emotional Learning: Basic Issues and Research Findings

    Science.gov (United States)

    Durlak, Joseph A.

    2016-01-01

    This paper discusses the fundamental importance of achieving quality implementation when assessing the impact of social and emotional learning interventions. Recent findings in implementation science are reviewed that include a definition of implementation, its relation to programme outcomes, current research on the factors that affect…

  18. Research Projects at Chulalongkorn University for the Master Degree Programme in Nuclear Security and Safeguard

    International Nuclear Information System (INIS)

    Nilsuwankosit, S.

    2015-01-01

    The Department of Nuclear Engineering, Faculty of Engineering, Chulalongkorn University, Thailand, began its master degree programme in nuclear security and safeguard in November 2013 with the support from the CBRN-Center of Excellence, European Union. This programme was planned as a way to raise the awareness of various local agencies in ASEAN countries regarding the threat of CBRN events. In the long run, the programme will also serve as the platform to develop the human resource and to provide the professional assistance required to counter such threat in the region. The programme closely follows the guideline as given by the IAEA and employs its materials as the main source of references. The first batch of 20 students came from countries in the ASEAN community. Due to the nature of the program, each student is required to conduct the research and a thesis based on such research is to be submitted as part of the requirement for the graduation. Currently, the research subjects that are readily available to the students can be classified into 5 categories: 1. subjects with neutron generator, 2. subjects with nuclear electronics and instruments, 3. subjects with industrial applications, 4. subjects with computer simulations, and 5. subjects with policy research. (author)

  19. 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

  20. Lakatos' Scientific Research Programmes as a Framework for Analysing Informal Argumentation about Socio-Scientific Issues

    Science.gov (United States)

    Chang, Shu-Nu; Chiu, Mei-Hung

    2008-01-01

    The purpose of this study is to explore how Lakatos' scientific research programmes might serve as a theoretical framework for representing and evaluating informal argumentation about socio-scientific issues. Seventy undergraduate science and non-science majors were asked to make written arguments about four socio-scientific issues. Our analysis…

  1. Lessons on transdiciplinary research in a co-innovation programme in the New Zealand agricultural sector

    NARCIS (Netherlands)

    Botha, N.; Klerkx, L.W.A.; Small, B.; Turner, J.A.

    2014-01-01

    A recently implemented research and development (R&D) programme in New Zealand is attempting to implement co-innovation principles throughout the country’s agricultural sector. It is based on an agricultural innovation systems (AIS) approach, using five innovation platforms (IPs) based in the

  2. The National Coordinated Research Programme for Air Quality. Another choice for clean air

    International Nuclear Information System (INIS)

    Van Giezen, M.; Havinga, A.; De Boer, H.

    2009-01-01

    On August 1st 2009 the National Coordinated Research Programme for Air quality (NSL in Dutch) entered into operation. This programme must help improve air quality such that it meets the European standards. At the same time the deadlock between environment and space is also solved. A special approach has been chosen for this purpose, which is based on a common interest of the State, provinces and local authorities. It was an intensive and interesting process. The annual monitoring will have to show whether or not the NSL will meet its objectives. [nl

  3. Ergonomics in a national research and development programme for food technology

    DEFF Research Database (Denmark)

    Broberg, Ole; Hansen, Iben Posniak

    1997-01-01

    The research question for the study presented in this paper was: What are the opportunities and barriers for integrating ergonomics aspects into joint projects sponsored by the FOETEK programme? The objectives were (i) to evaluate the outcome of this clause of accounting for ergonomics impacts......, and (ii) to put forward recommendations for improving the integration of ergonomics into joint projects sponsored by the FOETEK programme. A survey based on a questionnaire was conducted among 57 joint projects. A total of 217 project managers or contact persons received the questionnaire. The response...

  4. Programme of research and development on plutonium recycling in light water reactors

    International Nuclear Information System (INIS)

    1978-01-01

    The state of progress on 31 December 1977 of the work relating to the research and development programme on plutonium recycling in light-water nuclear power stations is presented in this second annual report. Since almost the entire programme is in the process of implementation, the report contains either the technical specifications and the objectives of recently concluded contracts or the initial results obtained. The prime objective of the programme is to facilitate the acceptance of the plutonium industry in the Community. Among the projects necessary to attain this prime objective is a forward analysis of plutonium utilization and of its impact on the environment. Various preliminary projects have been implemented in order to lessen this impact. The second objective is aimed at improving scientific and technical knowledge of the basic neutron physics of the higher isotopes of plutonium and transplutonium elements, of the behavior of the power station (static and dynamic) and of the fuel

  5. 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

  6. 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)

  7. Note On Research Design For The Study Of Community Participation In Health Care Programmes

    Directory of Open Access Journals (Sweden)

    Rifkin Susan B

    1986-01-01

    Full Text Available After describing types of research designs for the study of community participation in health care programmes, this paper examines one methodology, the quantitative methodology, the quantitative methodology, in detail. It presents some of the major attractions and limitations of this approach. The attractions include the need for evaluation of success and failure and of cost effectiveness of programmes. The limitations include the inability of the approach to deal with definitions and interventions that cannot be quantitified and the difficulty of identifying casual relationship between interventions and outcomes. These characteristics are illustrated by a case by a medical school in Asia. Research design, research developments and research outcomes are described and analysed. The paper concludes that an alternative analysis which examines the linkages between participation and health improvements would be more useful as it would allow the political, social and economic dimensions of community participation to be examined.

  8. RATU Nuclear power plant structural safety research programme 1990-1994. Final report

    International Nuclear Information System (INIS)

    Rintamaa, R.; Sarkimo, M.

    1995-12-01

    The major part of nuclear energy research in Finland has been organized as five-year nationally coordinated research programmes. The research programme on the Nuclear Power Plant Structural Safety was carried out during the period from 1990 to 1994. The total volume was about 76 person-years and the expenditure about 49 million FIM. Studies on the structural materials in nuclear power plants created the experimental data and background information necessary for the structural integrity assessments of mechanical components. The research was carried out by developing experimental fracture mechanics methods including statistical analysis methods of material property data, and by studying material ageing and, in particular, mechanisms of material deterioration due to neutron irradiation, corrosion and water chemistry. Besides material studies, new testing methods and sensors for the measurement of loading and water chemistry parameters have been developed

  9. 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

  10. The Community's research and development programme on decommissioning of nuclear installations. Second annual progress report (year 1986)

    International Nuclear Information System (INIS)

    1987-01-01

    This is the second 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 1986. This second progress report describes the objectives, scope and work programme of the 58 research contracts concluded, as well as the progress of work achieved and the results obtained in 1986

  11. Review of national research programmes on the microbiology of radioactive waste disposal

    International Nuclear Information System (INIS)

    Rosevear, A.

    1991-06-01

    Published results on the microbial effects of relevance to radioactive waste disposal are reviewed. The subjects covered by each of the various national programmes are considered in turn and the important themes that emerge from these are summarised. Finally the relevance of this microbiological research to the Nirex Safety case is discussed in brief. All references to research papers that deal with microbial aspects of radioactive waste disposal are listed and the key publications identified. (author)

  12. Protection of human research participants: accreditation of programmes in the Indian context.

    Science.gov (United States)

    Bhosale, Neelambari; Nigar, Shagoofa; Das, Soma; Divate, Uma; Divate, Pathik

    2014-01-01

    The recent negative media reports on the status of participants in clinical trials in India, together with the concerns expressed by the regulatory bodies, have raised questions regarding India's credibility in the conduct of clinical research. Even though the regulations require the registration of trials with the Clinical Trial Registry-India and despite the recently mandated registration of ethics committees (ECs) with the Drugs Controller General of India, the lack of governmental audit and accreditation procedures and bodies has resulted in inadequate protection of human participants in clinical research. Institutions and research sites would benefit by implementing a human research protection programme, which would safeguard the rights, safety and wellbeing of participants in clinical trials, in addition to improving the processes and procedures for the conduct of the trial. The Jehangir Clinical Development Centre, Pune has received accreditation from the Association for the Accreditation of Human Research Protection Programme (AAHRPP). A unique feature of the AAHRPP is the integrative nature of the programme, wherein the sponsors of the trial, investigators, EC members and institution work towards the common goal of protecting research participants. Here, we discuss the improvement needed in the quality standards of institutions for them to be able to meet the requirements of the AAHRPP. We also suggest the need for a governmental accreditation body, which will be required for the future promotion of and improvement in the standards for clinical practice in India.

  13. Content analysis as a means of exploring research opportunities from a conference programme.

    Science.gov (United States)

    Fourie, Ina

    2012-09-01

    Health librarians should keep up-to-date in a dynamic environment and accept the importance of continuing personal development (CPD) and growth in their critical reflection and creative thinking skills. They also need to acknowledge the potential value of research activity and the challenges of ongoing improvement and development. Conference programmes may prove a useful source of stimulation, especially if supplemented by creativity techniques, action research and the ideal of 'finding flow'. The article analyses the themes and papers presented at the 10th International Conference on International Medical Librarianship (ICML) to identify opportunities for further research, literature reviews, assessment of practices and services, etc. Content analysis approach to conference papers and suggestions for further action including supplementing with techniques of creativity and group input. A fairly extensive list of further actions (although not intended to be exhaustive) is suggested for the sixteen conference themes. Although subjective, the list might help to stimulate growth in research on health librarianship and demonstrate how one source of stimulation--conference programmes (regularly presented to medical library communities)--can be used. Content analysis has proven a constructive means of generating research questions from a conference programme. Content analysis and other methods aimed at stimulating creative and progressive thinking, including brainstorming, force field analysis, De Bono's 6 hats, creative swiping and creative visualisation, may prove equally useful and require further investigation. To ensure an ongoing cycle, these can be linked to action research. © 2012 The authors. Health Information and Libraries Journal © 2012 Health Libraries Group.

  14. The role of nuclear research centres in the introduction of a nuclear power programme

    International Nuclear Information System (INIS)

    Afgan, N.; Anastasijevic, P.; Kolar, D.; Strohal, P.

    1977-01-01

    Full development of nuclear energy has imposed a new role on nuclear energy centres. Nuclear technology for different reactor concepts is also now in a phase of high development. Several reactor concepts have been developed for industrial use and electric power production. Development of fast reactors is still under way and needs further research efforts. Having in mind these two main guidelines, research programmes in nuclear energy centres should be geared to the development of the activities vital to the implementation of national nuclear energy programmes. In this respect, national nuclear centres should devote their attention to three major tasks. First, to establish a background for the introduction of nuclear energy into the national energy system and to support a national safety system. Secondly, to support the national programme by skilled manpower, to provide the basic training in nuclear technology for future staff of nuclear power stations and to assist the universities in establishing the necessary educational programme in nuclear energy. Thirdly, to follow the development of nuclear energy technology for fast breeder reactor concepts. (author)

  15. Coordinated research programme on radiation protection in diagnostic radiology in Asia and the Far East

    International Nuclear Information System (INIS)

    Le Heron, J.

    1997-01-01

    Ten Asian countries (China, Vietnam, Thailand, Bangladesh, India, Pakistan, Iran, Philipppines, Malaysia, and Indonesia) are currently participating in a three year programme, as part of a Coordinated Research Programme of the International Atomic Energy Agency, aimed at reducing patient doses in diagnostic radiology through the implementation of optimisation of radiation protection. At the first meeting, held in Manila in September 1995, the project protocol was formulated for the first eighteen months of the programme, where the focus was on plain film radiography. The purpose of the second meeting was to briefly review the first half of the project, and to then come up with protocols for the second phase, where the attention was on dose reduction in fluoroscopic procedures and CT procedures. The second Research Coordination Meeting, held in Manila 3-7 March, was attended by participants from all the countries, with the exception of Iran, plus a consultant from each of Italy and New Zealand, and the scientific secretary from IAEA, Vienna. If the obvious enthusiasm of the participants is able to b maintained on return to their respective countries, then the signs are very healthy for a successful second phase of the programme. (author)

  16. A novel Internet-based blended learning programme providing core competency in clinical research.

    Science.gov (United States)

    Tsugihashi, Yukio; Kakudate, Naoki; Yokoyama, Yoko; Yamamoto, Yosuke; Mishina, Hiroki; Fukumori, Norio; Nakamura, Fumiaki; Takegami, Misa; Ohno, Shinya; Wakita, Takafumi; Watanabe, Kazuhiro; Yamaguchi, Takuhiro; Fukuhara, Shunichi

    2013-04-01

    We developed a novel Internet-based blended learning programme that allows busy health care professionals to attain core competency in clinical research. This study details the educational strategies and learning outcomes of the programme. This study was conducted at Kyoto University and seven satellite campuses from September 2009 to March 2010. A total of 176 health care professionals who had never attempted to attain core competency in clinical research were enrolled. The participants were supplied with a novel programme comprising the following four strategies: online live lectures at seven satellite campuses, short examinations after each lecture, an Internet-based feedback system and an end-of-course examination. We assessed the proportion of attendance at the lectures as the main outcome. In addition, we evaluated interaction via the feedback system and scores for end-of-course examination. Of the 176 participants, 134 (76%) reported working more than 40 hours per week. The mean proportion of attendance over all 23 lectures was 82%. A total of 156 (89%) participants attended more than 60% of all lectures and were eligible for the end-of-course examination. A total of the participants accessed the feedback system 3564 times and asked 284 questions. No statistically significant differences were noted in the end-of-course scores among medical doctors, pharmacists, registered nurses and other occupations. We developed an Internet-based blended learning programme providing core competency in clinical research. Most busy health care professionals completed the programme successfully. In addition, the participants could attain the core competency effectively, regardless of their occupation. © 2011 Blackwell Publishing Ltd.

  17. The CRACK programme: a scientific alliance for bridging healthcare research and public health policies in Italy

    Directory of Open Access Journals (Sweden)

    Giovanni Corrao

    2013-09-01

    Full Text Available Healthcare utilisation databases, and other secondary data sources, have been used with growing frequency to assess health outcomes and healthcare interventions worldwide. Their increased popularity as a research tool is due to their timely availability, the large patient populations covered, low cost, and applicability for studying real-world clinical practice. Despite the need to measure Italian National Health Service performance both at regional and national levels, the wealth of good quality electronic data and the high standards of scientific research in this field, healthcare research and public health policies seem to progress along orthogonal dimensions in Italy. The main barriers to the development of evidence-based public health include the lack of understanding of evidence-based methodologies by policy makers, and of involvement of researchers in the policy process. The CRACK programme was launched by some academics from the Lombardy Region. By extensively using electronically stored data, epidemiologists, biostatisticians, pharmacologists and clinicians applied methods and evidence to several issues of healthcare research. The CRACK programme was based on their intention to remove barriers that thwart the process of bridging methods and findings from scientific journals to public health practice. This paper briefly describes aim, articulation and management of the CRACK programme, and discusses why it might find articulated application in Italy.

  18. Research programme on controlled thermonuclear fusion. Synthesis report 2011; Programme de recherche Fusion thermonucleaire controlee. Rapport de synthese 2011

    Energy Technology Data Exchange (ETDEWEB)

    Vaucher, C. [Secretariat d' Etat a l' education et a la recherche, Berne (Switzerland); Tran, M. Q.; Villard, L. [Swiss Federal Institute of Technology (EPFL), Lausanne (Switzerland); Marot, L. [University of Basel, Basel (Switzerland)

    2012-07-01

    Since 1978, research on thermonuclear fusion in Switzerland is closely related to the research programme of the European Atomic Energy Community (EURATOM). The Swiss projects tackle aspects of plasma physics and fusion technology. Switzerland participates to the construction and operation of the Joint European Torus (JET), which started operation again in 2011. The International Thermonuclear Experimental Reactor (ITER) is the last step before DEMO, a prototype fusion reactor able to deliver electricity and demonstrate the economic viability of fusion energy. The 'Centre de Recherches en Physique des Plasmas' (CRPP) of the EPFL went on with its participation to the scientific and technological programme of EURATOM. Researches are carried out essentially on 2 sites: (i) at EPFL, where topics dealt with include the physics of magnetic confinement studied using the Variable Configuration Tokamak (TCV), the basic experiment TORPEX, theory and numerical modelling, and the technology of plasma heating and current generation by hyper-frequency waves; (ii) at the Paul Scherrer Institute (PSI), where activities are devoted to superconductivity and structure materials. Thanks to the large flexibility of the TCV design and operation modus, plasmas of different shapes can be created and controlled, what is a very useful option to verify numerical simulation results. Besides, the injection of millimetre waves allows directing the injected power according to specific profiles. In the TCV it could be demonstrated for the first time that the injection of Electronic Cyclotronic Heating (ECH) waves is able to double the frequency of so-called 'Edge Localized Modes' (ELM), reducing by a factor of 2 the energy expelled by each ELM. In particular, it was possible to considerably reduce the statistical dispersion of the repetition frequency of ELM, and to avoid the appearance of gigantic ELM that are particularly harmful for reactor operation. The effect of plasma

  19. RATU2 - The Finnish research programme on the structural integrity of nuclear power plants. Synthesis of achievements 1995-1998

    International Nuclear Information System (INIS)

    Solin, J.; Sarkimo, M.; Asikainen, M.; Aavall, Aa.

    1998-01-01

    The symposium summarises the scientific and technical achievements within the Finnish Research programme on the structural integrity of nuclear power plants (RATU2). The programme began in 1995 and will be accomplished at the end of 1998. The annual volume of this programme represented approximately 6 % of the total nuclear energy R and D in Finland. The research programme was mainly publicly funded and supplied impartial expertise for the regulation of nuclear energy. It also played an important role in the education of new experts, technology transfer and the international exchange of scientific results. (orig.)

  20. Cleaner heat from wood. TULISIJA research programme for wood firing technology 1997-1999

    International Nuclear Information System (INIS)

    1998-01-01

    There are 1.3 million wood-burning fireplaces in Finnish homes. The interest in using fireplaces for heating of dwellings has recently been growing strongly. Some 5.6 million cubic meters of firewood is burned in domestic stoves and fireplaces annually. This corresponds to a total of 7.5 terawatthours of energy and amounts to 13 % of all energy used for heating in Finland. The aim of the TULISIJA research programme for wood firing technology (1997-1999) is to assist manufacturers in their efforts to develop the most emission-free, yet efficient, wood firing equipment in the world. Detailed objectives of the TULISIJA programme are: (1) To produce modelling capabilities for the evaluation of different fireplace designs. Capabilities are produced for utilising computer simulation for investigation of the emissions of small-size fireplaces. (2) To establish a measuring place for fireplaces, where manufacturers' equipment designs can be reliably tested according to different standards is to be built, through which the Finnish manufacturers may obtain approvals for their products for different market areas. (3) To enhance co-operation between manufacturers and research institutions. Within the programme, the expertise of researchers in universities and other research institutes is made available to manufacturers - and vice versa. Equally important is the utilisation of international co-operation and making new connections

  1. 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

  2. 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

  3. 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

  4. 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

  5. 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

  6. Quality assurance of approved out of programme psychiatry training and research over the past 5 years

    Science.gov (United States)

    Osman-Hicks, Victoria; Graham, Hannah; Leadbetter, Peter; Brittlebank, Andrew

    2015-01-01

    Aims and method This paper intends to analyse the number of applications, trainee demographic and approval rate of those applying for out of programme training (OOPT) or out of programme research (OOPR) between January 2008 and April 2013 using the committee’s anonymised database. We also describe the process of application and approval by the Quality Assurance Committee. Results There were 90 applications, including 10 resubmissions during the 64-month period. Most applicants (77%) were higher trainees; 53% of applicants were from the London deanery; 60% of applications were for research posts and higher degrees (OOPR). Overall, 64% were approved by the committee: 70% for OOPRs and 53% for OOPTs. Clinical implications This paper shows with transparency the breakdown of applications to the Quality Assurance Committee. Around two-thirds of applications to the committee are supported (64%). Relatively few psychiatry trainees (2.5%) have applied for an OOPT or an OOPR over the past 5 years. PMID:26191450

  7. Development of a Customizable Programme for Improving Interprofessional Team Meetings: An Action Research Approach.

    Science.gov (United States)

    van Dongen, Jerôme Jean Jacques; van Bokhoven, Marloes Amantia; Goossens, Wilhelmus Nicolaas Marie; Daniëls, Ramon; van der Weijden, Trudy; Beurskens, Anna

    2018-01-25

    Interprofessional teamwork is increasingly necessary in primary care to meet the needs of people with complex care demands. Needs assessment shows that this requires efficient interprofessional team meetings, focusing on patients' personal goals. The aim of this study was to develop a programme to improve the efficiency and patient-centredness of such meetings. Action research approach: a first draft of the programme was developed, and iteratively used and evaluated by three primary care teams. Data were collected using observations, interviews and a focus group, and analysed using directed content analysis. The final programme comprises a framework to reflect on team functioning, and training activities supplemented by a toolbox. Training is intended for the chairperson and a co-chair, and aims at organizing and structuring meetings, and enhancing patient-centredness. Our findings emphasize the essential role of the team's chairperson, who, in addition to technically structuring meetings, should act as a change agent guiding team development. Findings show that the programme should be customizable to each individual team's context and participants' learning objectives. Becoming acquainted with new structures can be considered a growth process, in which teams have to find their way, with the chairperson as change agent.

  8. Overview of current research and development programmes for fuel in Japan

    International Nuclear Information System (INIS)

    Shiozawa, S.

    1991-01-01

    The Research and Development (R and D) programmes for HTGR fuel have been performed since 1969 by Japan Atomic Energy Research Institute (JAERI) as a leading organization in Japan. The R and D covers all fields necessary for the construction of the High Temperature Engineering Test Reactor (HTTR), which is the first HTGR in Japan. This R and D includes fuel fabrication, fuel property data, irradiation performance under normal operating conditions, safety-related research and fuel inspection technology. The R and D for the HTTR has been completed from a licensing point of view. Some R and D including future advanced fuel development continue. 2 figs, 3 tabs

  9. Overview on recent results of the VTT's research programme on assuring nuclear power plant structural safety

    International Nuclear Information System (INIS)

    Rintamaa, R.; Aaltonen, P.; Kauppinen, P.; Keinaenen, H.; Talja, H.; Valo, M.; Wallin, K.; Toerroenen, K.

    1994-01-01

    An overview of the Finnish national research programme on the Nuclear Power Plant Structural Safety, being carried out from 1990 to 1994, is presented. The focus of this paper is on recent results in the areas of experimental and computational fracture mechanics, material deterioration due to neutron irradiation, corrosion and water chemistry, nondestructive testing methods and procedures, and verification of structural integrity assessment methods by large scale component tests. (author). 21 refs, 21 figs, 2 tabs

  10. The Community's research and development programme on decommissioning of nuclear power plants

    International Nuclear Information System (INIS)

    1982-01-01

    The programme, adopted by the Council of the European Communities, 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; decontaminations for decommissioning purposes; dismantling techniques; treatment of specific waste materials (steel, concrete and graphite); large transport containers for radioactive waste arising from decommissioning of nuclear power plants in the Community; and influence of nuclear power plant design features on decommissioning

  11. Radioecology-related health physics and radiological protection. Departmental research programme of the BMU. Colloquium proceedings

    International Nuclear Information System (INIS)

    Wirth, E.; Pohl, H.

    1999-08-01

    The conference report covers the full texts of the 18 papers presented at the conference, as well as the contributions to the discussions. Except for two of the 18 papers, which set out the objectives and subjects of the departmental research programmes of the BMU, subject analysis and indexing has been done for individual retrieval of the papers from the database. (orig./CB) [de

  12. 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

  13. Status of the French research programme for actinides and fission products partitioning and transmutation

    International Nuclear Information System (INIS)

    Warin, D.

    2003-01-01

    The paper focus on separation and transmutation research and development programme and main results over these ten last years. The massive research programme on enhanced separation, conducted by CEA and supported by broad international cooperation, has recently achieved some vital progress. Based on real solutions derived from the La Hague process, the CEA demonstrated the lab-scale feasibility of extracting minor actinides and some fission products (I, Cs and Tc) using an hydrometallurgical process that can be extrapolated on the industrial scale. The CEA also conducted programmes proving the technical feasibility of the elimination of minor actinides and fission products by transmutation: fabrication of specific targets and fuels for transmutation tests in the HFR and Phenix reactors, neutronics and technology studies for ADS developments in order to support the MEGAPIE, TRADE and MYRRHA experiments and the future 100 MW international ADS demonstrator. Scenarios studies aimed at stabilizing the inventory with long-lived radionuclides, plutonium, minor actinides and certain long-lived fission products in different nuclear power plant parks and to verify the feasibility at the level of the cycle facilities and fuels involved in those scenarios. Three French Research Groups CEA-CNRS carry out partitioning (PRACTIS) and transmutation (NOMADE and GEDEON) more basic studies. (author)

  14. RETU. The Finnish research programme on reactor safety. Interim report 1995 - May 1997

    International Nuclear Information System (INIS)

    Vanttola, T.; Puska, E.K.

    1997-08-01

    The Finnish national research programme on Reactor Safety (RETU, 1995-1998) concentrates on the search of safe limits of nuclear fuel and the reactor core, accident management methods and risk management of the operation of nuclear power plants. The annual volume of the programme has been about 26 person years and the annual funding FIM 15 million. This report summarises the structure and objectives of the programme, research fields included and the main results obtained during the period 1995 - May 1997. In the field of operational margins of a nuclear reactor, the behaviour of high burnup nuclear fuel is studied both in normal operation and during power transients. The static and dynamic reactor analysis codes are developed and validated to cope with new fuel designs and complicated three-dimensional reactivity transients and accidents. Research on accident management aims at development and validation of calculation methods needed to plan preventive measures and to train the personnel to severe accident mitigation. Other goals are to reduce uncertainties in phenomena important in severe accidents and to study actions planned for accident management. In the field of risk management probabilistic methods are developed for safety related decision making and for complex phenomena and event sequences. Effects of maintenance on nuclear power plant safety are studied and more effective methods for the assessment of human reliability and safety critical organisations are searched

  15. Experiments and Research Programmes. Revisiting Vitalism/Non-Vitalism Debate in Early Twentieth Century

    Directory of Open Access Journals (Sweden)

    Bijoy MUKHERJEE

    2012-06-01

    Full Text Available Debates in the philosophy of science typically take place around issues such as realism and theory change. Recently, the debate has been reformulated to bring in the role of experiments in the context of theory change. As regards realism, Ian Hacking’s contribution has been to introduce ‘intervention’ as the basis of realism. He also proposed, following Imre Lakatos, to replace the issue of truth with progress and rationality. In this context we examine the case of the vitalism — reductionism debate in biology inspired by the works of Indian physicist-turned-biologist Jagadish Chandra Bose (1858–1937, in the early twentieth century. Both camps had their characteristic hardcores. Vitalists led by John S. Burdon-Sanderson and Augustus D. Waller accepted religious metaphysics to support their research programme, which ultimately degenerated. Bose worked more with the ideals of science such as Occam’s razor, large-scale systematization of phenomena and novel prediction. I argue that his religious metaphysics, instead of acting as a protective shield, helped him to consolidate his position and allowed further problem shift resulting in a research programme that involved consciousness too. His research programme remains relevant even today.

  16. RETU. The Finnish research programme on reactor safety. Interim report 1995 - May 1997

    Energy Technology Data Exchange (ETDEWEB)

    Vanttola, T; Puska, E K [VTT Energy, Espoo (Finland). Nuclear Energy; eds.

    1997-08-01

    The Finnish national research programme on Reactor Safety (RETU, 1995-1998) concentrates on the search of safe limits of nuclear fuel and the reactor core, accident management methods and risk management of the operation of nuclear power plants. The annual volume of the programme has been about 26 person years and the annual funding FIM 15 million. This report summarises the structure and objectives of the programme, research fields included and the main results obtained during the period 1995 - May 1997. In the field of operational margins of a nuclear reactor, the behaviour of high burnup nuclear fuel is studied both in normal operation and during power transients. The static and dynamic reactor analysis codes are developed and validated to cope with new fuel designs and complicated three-dimensional reactivity transients and accidents. Research on accident management aims at development and validation of calculation methods needed to plan preventive measures and to train the personnel to severe accident mitigation. Other goals are to reduce uncertainties in phenomena important in severe accidents and to study actions planned for accident management. In the field of risk management probabilistic methods are developed for safety related decision making and for complex phenomena and event sequences. Effects of maintenance on nuclear power plant safety are studied and more effective methods for the assessment of human reliability and safety critical organisations are searched. 135 refs.

  17. Research programme on controlled thermonuclear fusion - Synthesis report 2010; Programme de recherche Fusion thermonucleaire controlee. Rapport de synthese 2010

    Energy Technology Data Exchange (ETDEWEB)

    Vaucher, C. [Secretariat d' Etat a l' education et a la recherche, Berne (Switzerland); Tran, M. Q.; Villard, L. [Swiss Federal Institute of Technology (EPFL), Lausanne (Switzerland); Marot, L. [University of Basel, Basel (Switzerland)

    2011-07-01

    Since 1978, research on thermonuclear fusion in Switzerland is closely related to the research programme of the European Atomic Energy Community (EURATOM). The Swiss projects tackle aspects of plasma physics and fusion technology. Switzerland participates to the construction and operation of the Joint European Torus (JET). The International Thermonuclear Experimental Reactor (ITER) is being built; the first plasma is expected in 2019. The 'Centre de Recherches en Physique des Plasmas' (CRPP) of the EPFL participates to EURATOM scientific and technological projects in magnetic confinement physics, through an experimental contribution (the Variable Configuration Tokamak, TCV) and theoretical studies. Thanks to the large flexibility of the TCV design and operation modus, plasmas of different shapes can be created and controlled, what is a very useful option to verify numerical simulation results. Besides, the injection of millimetre waves allows directing the injected power according to specific profiles. A configuration of type 'snowflakes' could be created, reducing the power deposition at the edge of the plasma. Theoretical studies on turbulence have improved the plasma stability in the TCV. For the first time in the world, TCV could reach a stable plasma, the plasma current being generated using the so-called 'bootstrap' phenomenon. Besides turbulence, studies were focused on heat and particle transport in tokamaks, on an analysis of the equilibrium and magneto-hydrodynamic stability of tokamaks and stellarators, on the application of radiofrequency waves and on the optimization of new confinement configurations. Experiments in the JET facility confirmed the numerical results of theoretical simulations. The TORPEX facility, which is simpler than TCV, allows high space-temporal resolution measurements for the study of turbulences and plasma threads ('blobs'). At the Paul Scherrer Institute (PSI), research topics include

  18. TELEMAN - an European community research and development programme on robotics in the nuclear industry

    International Nuclear Information System (INIS)

    Tolley, B.; Robertson, B.

    1991-01-01

    The TELEMAN Programme is a five year cost-shared research programme covering remote handling in hazardous and disordered nuclear environments. It is supported within the current research and development of the European Communities. TELEMAN's strategic objective is to develop advanced teleoperators that respond to the needs of the nuclear industry. Its technical objective is to strengthen the scientific and engineering bases upon which the design of teleoperators for use throughout the nuclear industry rests. This will be done by providing new solutions to problems of manipulation, material transport and mobile surveillance in nuclear environments and by demonstrating their feasibility. Motivation for such a programme lies in the potential teleoperators have to improve the separation of workers from radioactive equipment. This technology will also enable plant operators and public authorities to deal more effectively with nuclear abnormal incidents and increase gains in productivity, mainly in the repair and maintenance area. Community support is justified by the cost of the reliability and autonomy required for the nuclear teleoperator, the need to rationalise R and D investment in an area of increasing industrial potential and a common interest in coherent responses to emergencies. (author)

  19. The Nordic Nuclear Safety Research (NKS) programme. Nordic cooperation on nuclear safety

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, Kasper G. [Technical Univ. of Denmark, Roskilde (Denmark). National Lab. for Sustainable Energy; Ekstroem, Karoliina [Fortum Power and Heat, Fortum (Finland); Gwynn, Justin P. [Norwegian Radiation Protection Authority, Tromsoe (Norway). Fram Centre; Magnusson, Sigurdur M. [Icelandic Radiation Safety Authority, Reykjavik (Iceland); Physant, Finn C. [NKS-Sekretariatet, Roskilde (Denmark)

    2012-07-01

    The roots of the current Nordic Nuclear Safety Research (NKS) programme can be traced back to the recommendation by the Nordic Council in the late 1950s for the establishment of joint Nordic committees on the issues of nuclear research and radiation protection. One of these joint Nordic committees, the 'Kontaktorgan', paved the way over its 33 years of existence for the future of Nordic cooperation in the field of nuclear safety, through the formation of Nordic groups on reactor safety, nuclear waste and environmental effects of nuclear power in the late 1960s and early 1970s. With an increased focus on developing nuclear power in the wake of the energy crisis on the 1970s, the NKS was established by the Nordic Council to further develop the previous strands of Nordic cooperation in nuclear safety. NKS started its first programme in 1977, funding a series of four year programmes over the next 24 years covering the areas of reactor safety, waste management, emergency preparedness and radioecology. Initially funded directly from the Nordic Council, ownership of NKS was transferred from the political level to the national competent authorities at the beginning of the 1990s. This organizational and funding model has continued to the present day with additional financial support from a number of co-sponsors in Finland, Norway and Sweden. (orig.)

  20. The programme 'fission product deposition' at the IRB of Juelich nuclear research centre

    International Nuclear Information System (INIS)

    Gottaut, H.; Iniotakis, N.; Malinowski, J.; Muenchow, K.H.; Sackmann, B.

    1976-01-01

    The transport and deposition behaviour of the non-gaseous fission and activation products in the primary circuit of HTR-type reactors determines the possibility of inspection and maintenance of single components of the primary circuit as well as the safety of the reactor in normal operation and during accidents. For the investigation of these problems, the programme 'fission product deposition' was started at Juelich nuclear research centre in 1969 in cooperation with a number of industrial firms. The programme covers in-pile and out-of-pile experiments, in which the HTR conditions are simulated as realistically as possible, as well as various laboratory experiments and extensive theoretical studies. It is the objective of this work to establish a realistic physical model and computer programme with which the transport and deposition of nuclides in the primary circuit of HTR reactors can be calculated in advance. A report is given on the experimental and theoretical studies carried out at the IRB of Juelich nuclear research centre. (orig./AK) [de

  1. A review of DOE chemical and geochemical research programmes (for disposal of low and intermediate level waste)

    International Nuclear Information System (INIS)

    May, R.

    1987-01-01

    A study of 26 DOE sponsored research programmes has been carried out with respect to their coverage of various chemical and geochemical issues posed by the proposed disposal of low and intermediate level wastes in a land repository. The study also took into account various experimental programmes sponsored by NIREX and abroad. The findings of the study are reported here. (author)

  2. A Research-Informed, School-Based Professional Development Workshop Programme to Promote Dialogic Teaching with Interactive Technologies

    Science.gov (United States)

    Hennessy, Sara; Dragovic, Tatjana; Warwick, Paul

    2018-01-01

    The study reported in this article investigated the influence of a research-informed, school-based, professional development workshop programme on the quality of classroom dialogue using the interactive whiteboard (IWB). The programme aimed to develop a dialogic approach to teaching and learning mediated through more interactive uses of the IWB,…

  3. Environmental research programme. Ecological research. Annual report 1994. Urban-industrial landscapes, forests, agricultural landscapes, river and lake landscapes, terrestrial ecosystem research, environmental pollution and health

    International Nuclear Information System (INIS)

    1995-01-01

    In the annual report 1994 of the Federal Ministry of Research and Technology, the points of emphasis of the ecological research programme and their financing are discussed. The individual projects in the following subject areas are described in detail: urban-industrial landscapes, forests, agricultural landscapes, river and lake landscapes, other ecosystems and landscapes, terrestrial ecosystem research, environmental pollution and human health and cross-sectional activities in ecological research. (vhe) [de

  4. Recent results from CEC cost sharing research programme on LWR fuel behaviour under accident conditions

    International Nuclear Information System (INIS)

    Fairbairn, S.A.

    1983-01-01

    The present structure and intentions of the CEC sponsored cost sharing programme for LWR safety research are outlined. Detailed results are reported for two projects from this programme. The first project concerns experimental data on the thermohydraulic effects of flow diversion around ballooned fuel rods. Data are presented on single and two phase heat transfer in an electrically heated rod bundle. Detailed photographic data on droplet behaviour are also given. The second project is an investigation of the effects of zircaloy oxidation on rewetting during reflood. It is shown that as oxide thickness increases from 1μm to 76μm that rewet rates can increase by up to 40%. A systematic effect of oxidation on rewet temperatures is also noted. (author)

  5. Description of a research reactor control system using a programmable controller

    International Nuclear Information System (INIS)

    Battle, R.E.

    1986-01-01

    This paper describes the design features, testing methods, and operational experience of a programmable controller (PC) installed as a neutron flux controller in the Oak Ridge Research Reactor (ORR) at Oak Ridge National Laboratory (ORNL). The PC was designed to control neutron flux from 1 to 105% for three selectable ranges. The PC generates a flux setpoint under operator control, calculates the reactor heat power from flow and temperature signals, calculates a neutron flux calibration factor based on the heat power, and positions a control rod based on the flux-setpoint difference. The programmable controller was tested by controlling an analog computer model of the ORR. The equipment was installed in August 1985, and except for some startup problems, the system has performed well

  6. RD and D Programme 98. Treatment and final disposal of nuclear waste. Programme for research, development and demonstration of encapsulation and geological disposal

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-09-01

    RD and D-Programme 98 is intended to provide an overview of SKBs activities and plans. The detailed research programme is presented in a separate background report. In parallel with RDD-Programme 98, SKB is publishing a number of reports that provide a more thorough background and a more detailed account, particularly on those issues that the Government mentioned in its decision regarding RD and D-Programme 95. The programme is divided into two parts: Background and Execution. The background part begins with a chapter on the basic premises. It deals with general principles, laws and the properties of the waste. The facilities that exist today for dealing with the nuclear waste are also described in the introductory chapter. The two following chapters have to do with the choice between different methods for disposing of nuclear waste and with the KBS-3 method, which SKB has chosen as its main alternative. These two chapters provide a broader account of both the KBS-3 method and different alternative methods than previous RD and D-programmes. The background part concludes with a chapter about the long-term safety of the deep repository. The second part, Execution, begins with an overview of SKBs strategy and the main features of the programme, both for the next few years and further in the future. The plans for siting, technology and safety assessment are then presented in greater detail. This is followed by an overview of our plans for supportive research and development, including continued R and D on other methods than the KBS-3 method. The programme concludes with a chapter on decommissioning of nuclear facilities. An important part of the ongoing and planned work is consultation on environmental impact assessments. A first draft of the contents of future environmental impact statements is therefore provided. By attaching it to RD and D-Programme 98, SKB wishes to give all reviewing bodies an opportunity to offer their viewpoints at an early stage on what future

  7. RD and D Programme 98. Treatment and final disposal of nuclear waste. Programme for research, development and demonstration of encapsulation and geological disposal

    International Nuclear Information System (INIS)

    1998-09-01

    RD and D-Programme 98 is intended to provide an overview of SKBs activities and plans. The detailed research programme is presented in a separate background report. In parallel with RDD-Programme 98, SKB is publishing a number of reports that provide a more thorough background and a more detailed account, particularly on those issues that the Government mentioned in its decision regarding RD and D-Programme 95. The programme is divided into two parts: Background and Execution. The background part begins with a chapter on the basic premises. It deals with general principles, laws and the properties of the waste. The facilities that exist today for dealing with the nuclear waste are also described in the introductory chapter. The two following chapters have to do with the choice between different methods for disposing of nuclear waste and with the KBS-3 method, which SKB has chosen as its main alternative. These two chapters provide a broader account of both the KBS-3 method and different alternative methods than previous RD and D-programmes. The background part concludes with a chapter about the long-term safety of the deep repository. The second part, Execution, begins with an overview of SKBs strategy and the main features of the programme, both for the next few years and further in the future. The plans for siting, technology and safety assessment are then presented in greater detail. This is followed by an overview of our plans for supportive research and development, including continued R and D on other methods than the KBS-3 method. The programme concludes with a chapter on decommissioning of nuclear facilities. An important part of the ongoing and planned work is consultation on environmental impact assessments. A first draft of the contents of future environmental impact statements is therefore provided. By attaching it to RD and D-Programme 98, SKB wishes to give all reviewing bodies an opportunity to offer their viewpoints at an early stage on what future

  8. The European Communities' research programme on management of low and intermediate level wastes

    International Nuclear Information System (INIS)

    Simon, R.; Cecille, L.

    1989-01-01

    In the European Communities' third R and D programme on Management and Disposal of Radioactive Wastes a large number of projects have been commissioned to develop treatment and conditioning processes for low and intermediate level wastes and to qualify the conditioned waste forms. The paper presents the main objectives of this research and summarizes some of the more important studies. In liquid waste treatment, the research includes processes to separate actinides by new extractive methods and application of selective inorganic ion exchangers as well as electrochemically controlled ion exchange processes and a series of purification methods involving membrane techniques. The most important issue of solid waste management in the programme is the treatment and conditioning of plutonium containing wastes, for which a strategic study had been commissioned to optimize the choice between different treatment and conditioning options. Processes being studied include two advanced decontamination techniques and a variety of conditioning methods for incinerator ash and fuel element hulls. Another task of the programme is devoted to the qualification of waste forms. This comprises the characterization of the most common low and intermediate level waste products with respect to leaching, waste form stability, radiation resistance and compatibility with the respective disposal environments. In the course of the programme, the development of methods for quality assurance and in particular quality control has become an important issue: the control of the nuclide inventory, of the chemical composition of the wastes and of the correct operation of treatment and conditioning processes is being investigated in special laboratories. (author). 21 refs, 4 tabs

  9. Eu-funded nuclear research on plant life management in the 4. and 5. framework programme

    International Nuclear Information System (INIS)

    Lemaitre, P.; Van Goethem, G.

    2001-01-01

    In this paper an overview will be given of the European Union EURATOM research in the field of plant life management and ageing of structural components. The results obtained so far in the projects executed under the 5. framework programme (FP-5/1999-2002) will be presented and discussed in detail. The objectives of the 5. framework programme, which is end-user driven, are: 1) to develop a common basis for the continued safe operation and prolonging the safe operational life-spans of existing nuclear installations; 2) to develop better methods for their inspection, maintenance and management (both in terms of performance and occupational exposure). The following three sections were proposed under this heading of the work programme: Integrity of equipment and structures, on-line monitoring, inspection and maintenance, and organisation and management of safety. Besides the traditional technological challenges, socio-economic concerns are also taken on board, such as public acceptance and cost of the nuclear option as well as plant simplification and man-technology-organisation interaction. An additional challenge for the EU consists of the enlargements process towards Central and Eastern European Countries in the coming years. Therefore FP5 pays attention also to plant safety assessments of VVER reactors and to the spreading of the new safety culture in these candidate countries in co-operation with similar activities run at the Commission especially under the programmes of Tacis/Phare and of the Joint Research Centre (JRC). In the area of plant life management so far 18 projects have been selected for funding by the European Commission. Most of them are costs shared actions, which means that the European Commission on the one hand and the project partners on the other hand provide each 50 % of the necessary funding. The total contract value of the selected projects is about 18 million euros. (authors)

  10. Eu-funded nuclear research on plant life management in the 4. and 5. framework programme

    Energy Technology Data Exchange (ETDEWEB)

    Lemaitre, P.; Van Goethem, G. [European Commission, Dir. General Research, Bruxelles (Belgium)

    2001-07-01

    In this paper an overview will be given of the European Union EURATOM research in the field of plant life management and ageing of structural components. The results obtained so far in the projects executed under the 5. framework programme (FP-5/1999-2002) will be presented and discussed in detail. The objectives of the 5. framework programme, which is end-user driven, are: 1) to develop a common basis for the continued safe operation and prolonging the safe operational life-spans of existing nuclear installations; 2) to develop better methods for their inspection, maintenance and management (both in terms of performance and occupational exposure). The following three sections were proposed under this heading of the work programme: Integrity of equipment and structures, on-line monitoring, inspection and maintenance, and organisation and management of safety. Besides the traditional technological challenges, socio-economic concerns are also taken on board, such as public acceptance and cost of the nuclear option as well as plant simplification and man-technology-organisation interaction. An additional challenge for the EU consists of the enlargements process towards Central and Eastern European Countries in the coming years. Therefore FP5 pays attention also to plant safety assessments of VVER reactors and to the spreading of the new safety culture in these candidate countries in co-operation with similar activities run at the Commission especially under the programmes of Tacis/Phare and of the Joint Research Centre (JRC). In the area of plant life management so far 18 projects have been selected for funding by the European Commission. Most of them are costs shared actions, which means that the European Commission on the one hand and the project partners on the other hand provide each 50 % of the necessary funding. The total contract value of the selected projects is about 18 million euros. (authors)

  11. Bioenergy Research Programme, Yearbook 1995. Production of wood fuels; Bioenergian tutkimusohjelma, vuosikirja 1995. Puupolttoaineen tuotantotekniikka

    Energy Technology Data Exchange (ETDEWEB)

    Alakangas, E. [ed.

    1996-12-31

    Bioenergy Research Programme is one of the energy technology research programmes of the Technology Development Center TEKES. The aim of the Bioenergy Research Programme is to increase, by using technical research and development, the economically profitable and environmentally sound utilisation of bioenergy, to improve the competitiveness of present peat and wood fuels, and to develop new competitive fuels and equipment related to bioenergy. The funding for 1995 was nearly 52 million FIM and the number of projects 66. The main goal of the 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{sup 3}). During the year 1995 There were over 30 projects concerning the production of wood derived fuels going on. Nearly half of them focused on integrated production of pulp wood and wood fuel. About ten projects was carried out to promote the wood fuel production from logging residues. Other topics were firewood production, production logistics and wood fuel resources. For production of fuel chips from logging residues, a new chipper truck, MOHA-SISU, was introduced. The new machine gives a new logistic solution resulting in high productivity and reasonable operating costs. In Mikkeli region three years of active work promoted the usage of wood fuel in a district power plant to the level of over 110 000 m{sup 3} of fuel chips. The production costs tend to be a little high in average, and the production chain still needs to be improved

  12. Bioenergy Research Programme, Yearbook 1995. Production of wood fuels; Bioenergian tutkimusohjelma, vuosikirja 1995. Puupolttoaineen tuotantotekniikka

    Energy Technology Data Exchange (ETDEWEB)

    Alakangas, E [ed.

    1997-12-31

    Bioenergy Research Programme is one of the energy technology research programmes of the Technology Development Center TEKES. The aim of the Bioenergy Research Programme is to increase, by using technical research and development, the economically profitable and environmentally sound utilisation of bioenergy, to improve the competitiveness of present peat and wood fuels, and to develop new competitive fuels and equipment related to bioenergy. The funding for 1995 was nearly 52 million FIM and the number of projects 66. The main goal of the 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{sup 3}). During the year 1995 There were over 30 projects concerning the production of wood derived fuels going on. Nearly half of them focused on integrated production of pulp wood and wood fuel. About ten projects was carried out to promote the wood fuel production from logging residues. Other topics were firewood production, production logistics and wood fuel resources. For production of fuel chips from logging residues, a new chipper truck, MOHA-SISU, was introduced. The new machine gives a new logistic solution resulting in high productivity and reasonable operating costs. In Mikkeli region three years of active work promoted the usage of wood fuel in a district power plant to the level of over 110 000 m{sup 3} of fuel chips. The production costs tend to be a little high in average, and the production chain still needs to be improved

  13. Collective statement on major nuclear safety research facilities and programmes at risk

    International Nuclear Information System (INIS)

    2001-01-01

    Nuclear safety research remains necessary, since nuclear power programmes are dynamic. In addition to maintaining in-depth competencies, its aim is to provide information to plant designers, operators and regulators in support of the resolution of safety issues, to strengthen confidence in their solution and their implementation, and also to anticipate problems of potential significance. New fields of research open up as a result of plant ageing, plant life extension, plant up-rating, optimisation of plant economics and the associated need to further reduce uncertainties in safety margins quantification. The safety evaluation of future reactor systems being developed or considered in several Member countries also requires new research efforts. Accordingly, Member countries are encouraged to support efforts to maintain key research data, facilities and programmes through national support of international co-operation and funding. This should be under-pinned by development of short-, medium- and long-term strategic visions of the needs of the nuclear safety research community, including a strong component of international collaboration given the international nature of nuclear safety issues. (author)

  14. Non-animal approaches for consumer safety risk assessments: Unilever's scientific research programme.

    Science.gov (United States)

    Carmichael, Paul; Davies, Michael; Dent, Matt; Fentem, Julia; Fletcher, Samantha; Gilmour, Nicola; MacKay, Cameron; Maxwell, Gavin; Merolla, Leona; Pease, Camilla; Reynolds, Fiona; Westmoreland, Carl

    2009-12-01

    Non-animal based approaches to risk assessment are now routinely used for assuring consumer safety for some endpoints (such as skin irritation) following considerable investment in developing and applying new methods over the past 20 years. Unilever's research programme into non-animal approaches for safety assessment is currently focused on the application of new technologies to risk assessments in the areas of skin allergy, cancer and general toxicity (including inhalation toxicity). In all of these areas, a long-term investment is essential to increase the scientific understanding of the underlying biological and chemical processes that we believe will ultimately form a sound basis for novel risk assessment approaches. Our research programme in these priority areas consists of in-house research as well as Unilever-sponsored academic research, involvement with EU-funded projects (e.g. Sens-it-iv, carcinoGENOMICS), participation in cross-industry collaborative research (e.g. COLIPA, EPAA) and ongoing involvement with other scientific initiatives on non-animal approaches to risk assessment (e.g. UK NC3Rs, US 'Human Toxicology Project' consortium). 2009 FRAME.

  15. Research in the field of energy: the priorities of framework programme V and the main trends of the new framework programme

    International Nuclear Information System (INIS)

    Pilavachi, P.

    2001-01-01

    The features and priorities of the 5th European Framework Programme are discussed. The first action include quality of life and management of living resources; user friendly information society; competitive and sustainable growth and energy, environment and sustainable development (environment, energy and nuclear energy). The key actions are as follows: for environment - sustainable management and quality of water, global change, climate and biodiversity, sustainable marine ecosystems; for energy - cleaner energy systems, including renewable, economic efficient energy; for nuclear energy - controlled thermonuclear fusion, nuclear fission. The priorities of strategic importance to the EU are management of greenhouse gases emissions and climate change; exploiting of the potential of new ICTs in energy RTD including e-science issues; socio-economic research related to energy technologies and their impact; international co-operation, co-ordination with MS research programmes and EU wide research networks; pre-normative research of interest at EU level

  16. A scientometric evaluation of the Chagas disease implementation research programme of the PAHO and TDR.

    Directory of Open Access Journals (Sweden)

    Ana Laura Carbajal-de-la-Fuente

    2013-11-01

    Full Text Available The Special Programme for Research and Training in Tropical Diseases (TDR is an independent global programme of scientific collaboration cosponsored by the United Nations Children's Fund, the United Nations Development Program, the World Bank, and the World Health Organization. TDR's strategy is based on stewardship for research on infectious diseases of poverty, empowerment of endemic countries, research on neglected priority needs, and the promotion of scientific collaboration influencing global efforts to combat major tropical diseases. In 2001, in view of the achievements obtained in the reduction of transmission of Chagas disease through the Southern Cone Initiative and the improvement in Chagas disease control activities in some countries of the Andean and the Central American Initiatives, TDR transferred the Chagas Disease Implementation Research Programme (CIRP to the Communicable Diseases Unit of the Pan American Health Organization (CD/PAHO. This paper presents a scientometric evaluation of the 73 projects from 18 Latin American and European countries that were granted by CIRP/PAHO/TDR between 1997 and 2007. We analyzed all final reports of the funded projects and scientific publications, technical reports, and human resource training activities derived from them. Results about the number of projects funded, countries and institutions involved, gender analysis, number of published papers in indexed scientific journals, main topics funded, patents inscribed, and triatomine species studied are presented and discussed. The results indicate that CIRP/PAHO/TDR initiative has contributed significantly, over the 1997-2007 period, to Chagas disease knowledge as well as to the individual and institutional-building capacity.

  17. Bioenergy research programme. Yearbook 1996. Production of wood fuels; Bioenergian tutkimusohjelma. Vuosikirja 1996. Puupolttoaineiden tuotantotekniikka

    Energy Technology Data Exchange (ETDEWEB)

    Nikku, P [ed.

    1997-12-01

    The aim of the 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, new equipment and methods for production, handling and utilisation of biofuels. The total funding for 1996 was 27.3 million FIM and the number of projects 63. The number of projects concerning wood fuels production was 36. The main goals of the research are to develop new production methods for wood fuels in order to decrease the production costs to the level of imported fuels (100 km distance). The second goal is to decrease the small scale production costs by 20 % as compared with the 1992 technology level. Also, new harvesting technology and new work methods will be developed for forest owners and small-entrepreneurs in the course of the programme. Results of the projects carried out in 1996 in this programme are presented in this publication. The integrated harvesting methods, which supply both raw material to wood products industry and wood fuel for energy production, have been chosen the main research areas because they seem to be most promising. Most of the projects are focused in the wood fuel production from first thinnings and from final fellings. The projects broadly covered the research area focusing from material flows, productivity studies, basic wood properties to several case studies. The follow up project of Evaluation-drum chipper was completed with good fuel quality and productivity results. Also the large Forest Energy Project of Central Finland was completed. The project was a significant technology transfer and information dissemination project. (orig.)

  18. Dismantling and rehabilitation programme of nuclear and radioactive facilities at the Spanish Research Centre (CIEMAT)

    International Nuclear Information System (INIS)

    Diaz Diaz, J.L.; Lopez Jimenez, J.

    2002-01-01

    Ciemat was gradually proceeding to the decommissioning of its more than 60 historical facilities. At present, a general decommissioning programme has been established that includes, to a different extent, all radioactive and nuclear facilities and their areas of influence, particularly those related to the front-end and back-end of the nuclear fuel cycle, hot cells and three experimental reactors. The purpose of the programme is to manage a model of a research centre integrating, on one side, a set of radioactive and conventional facilities and laboratories, and, on the other, a small area temporarily classified as a nuclear facility dedicated to the radioactive wastes management and providing an interim storage for materials under safeguards. The largest part of the radioactive wastes produced will be sent to El Cabril, a near surface disposal facility for low and intermediate level wastes, and the rest will be temporarily stored at Ciemat. This paper presents the main features of the programme and the lessons learned in its execution so far. (author)

  19. Programme of research and development on plutonium recycling in light-water reactors; indirect nuclear action

    International Nuclear Information System (INIS)

    1982-01-01

    This report is a summary of the results obtained during the five-year programme 'Plutonium recycle in LWRs' (1975-79) which has been made possible after the completion of the synthesis studies on 'Control and Safety' and on the 'Environmental impact'. The work performed during the programme is reported; the contracts concluded and their main results and conclusions are summarized. The activity was devoted to studies of general interest and to R and D in order to improve the scientific and technical knowledge of plutonium recycling. General studies included an assessment of the environmental impact of plutonium recycling in the EC as well as research aimed at reducing this impact. Improvements were achieved on neutron-physics parameters of the actinides, on neutron computer codes for plutonium-fuelled LWRs, on control and safety and on the in-pile behaviour of mixed-oxide fuels. The conclusions state that, while fostering a fruitful exchange of information in the Community, the programme has contributed to demonstrating the feasibility of plutonium recycling in LWRs

  20. Co-ordinated research programme on nuclear techniques for toxic elements in foodstuffs

    International Nuclear Information System (INIS)

    1988-01-01

    The purpose of this Co-ordinated Research Programme (CRP) is to obtain comparative data on the existing elemental concentrations of potentially toxic elements in foodstuffs in various countries. This study is also intended to provide information on the dietary intakes of toxic elements as a means to detect potential health hazards to the population groups concerned. This study has important economic implications since trade in foodstuffs is dependent on compliance with regulations pertaining to maximum permissible concentrations. An important supplementary purpose of the programme is to help establish analytical expertise for work of this kind in individual countries, allowing such laboratories to offer analytical quality control services. The programme has centred its objective on the determination of important toxic elements such as As, Cd, Cr, Hg, Pb and Se, in addition to Cu, Sb and Zn, which are also potentially toxic but are generally of minor importance from the point of view of public health. The matrices of interest are foodstuffs which comprise together more than 50% of the average daily intake. Drinking water is also of high importance and should be analysed as well. Refs, figs and tabs

  1. A Research Agenda for Helminth Diseases of Humans: Diagnostics for Control and Elimination Programmes

    Science.gov (United States)

    McCarthy, James S.; Lustigman, Sara; Yang, Guo-Jing; Barakat, Rashida M.; García, Héctor H.; Sripa, Banchob; Willingham, Arve Lee; Prichard, Roger K.; Basáñez, María-Gloria

    2012-01-01

    Diagnostic tools appropriate for undertaking interventions to control helminth infections are key to their success. Many diagnostic tests for helminth infection have unsatisfactory performance characteristics and are not well suited for use in the parasite control programmes that are being increasingly implemented. Although the application of modern laboratory research techniques to improve diagnostics for helminth infection has resulted in some technical advances, uptake has not been uniform. Frequently, pilot or proof of concept studies of promising diagnostic technologies have not been followed by much needed product development, and in many settings diagnosis continues to rely on insensitive and unsatisfactory parasitological or serodiagnostic techniques. In contrast, PCR-based xenomonitoring of arthropod vectors, and use of parasite recombinant proteins as reagents for serodiagnostic tests, have resulted in critical advances in the control of specific helminth parasites. The Disease Reference Group on Helminths Infections (DRG4), established in 2009 by the Special Programme for Research and Training in Tropical Diseases (TDR) was given the mandate to review helminthiases research and identify research priorities and gaps. In this review, the diagnostic technologies relevant to control of helminth infections, either available or in development, are reviewed. Critical gaps are identified and opportunities to improve needed technologies are discussed. PMID:22545166

  2. National Plan for Research - Development and Innovation, CERES Programme. Annual Scientific Session

    International Nuclear Information System (INIS)

    Ionescu-Bujor, Theodor; Dobrescu, Serban

    2002-01-01

    The CERES Programme is a research program organized in the frame of Institut of Atomic Physics, Bucharest, Romania. The annual scientific session held in Bucharest on December 2-3, 2002 covered the following 9 sections (projects): Mathematics (2); Physics (85); Chemistry (14); Engineering (2); Earth Sciences (13); Life Sciences (8); Economics and Social Studies (4); Culture (4); Works received after the deadline. The most numerous contributions within the INIS scope addressed subjects from the fields: theoretical and experimental nuclear physics, seismic survey and prognoses, high energy physics and quantum field theory, physical properties of materials, nuclear spectroscopic instrumentation, nuclear methods in isotopic analysis. The contributors presented their results obtained under research contracts supported by the Romanian Ministry of Education and Research in the period October 15, 2001 - October 15, 2002. Many of the reported research works were done in collaborations with international organizations or institutes from abroad

  3. A European collaboration research programme to study and test large scale base isolated structures

    International Nuclear Information System (INIS)

    Renda, V.; Verzeletti, G.; Papa, L.

    1995-01-01

    The improvement of the technology of innovative anti-seismic mechanisms, as those for base isolation and energy dissipation, needs of testing capability for large scale models of structures integrated with these mechanisms. These kind experimental tests are of primary importance for the validation of design rules and the setting up of an advanced earthquake engineering for civil constructions of relevant interest. The Joint Research Centre of the European Commission offers the European Laboratory for Structural Assessment located at Ispra - Italy, as a focal point for an international european collaboration research programme to test large scale models of structure making use of innovative anti-seismic mechanisms. A collaboration contract, opened to other future contributions, has been signed with the national italian working group on seismic isolation (Gruppo di Lavoro sull's Isolamento Sismico GLIS) which includes the national research centre ENEA, the national electricity board ENEL, the industrial research centre ISMES and producer of isolators ALGA. (author). 3 figs

  4. Research support for effective state and community tobacco control programme response to electronic nicotine delivery systems.

    Science.gov (United States)

    Schmitt, Carol L; Lee, Youn Ok; Curry, Laurel E; Farrelly, Matthew C; Rogers, Todd

    2014-07-01

    To identify unmet research needs of state and community tobacco control practitioners pertaining to electronic nicotine delivery systems (ENDS or e-cigarettes) that would inform policy and practice efforts at the state and community levels, and to describe ENDS-related research and dissemination activities of the National Cancer Institute-funded State and Community Tobacco Control Research Initiative. To determine specific research gaps relevant to state and community tobacco control practice, we analysed survey data collected from tobacco control programmes (TCPs) in all 50 U.S. states and the District of Columbia (N=51). Survey items covered a range of ENDS issues: direct harm to users, harm of secondhand vapour, cessation, flavours, constituents and youth access. There is no ENDS topic on which a majority of state TCP managers feel very informed. They feel least informed about harms of secondhand vapour while also reporting that this information is among the most important for their programme. A majority (N=31) of respondents indicated needs for research on the implications of ENDS products for existing policies. TCP managers report that ENDS research is highly important for practice and need research-based information to inform decision making around the inclusion of ENDS in existing tobacco control policies. For optimal relevance to state and community TCPs, research on ENDS should prioritise study of the health effects of ENDS use and secondhand exposure to ENDS vapour in the context of existing tobacco control policies. Published by the BMJ Publishing Group Limited. For permission to use (where not already granted under a licence) please go to http://group.bmj.com/group/rights-licensing/permissions.

  5. RETU The Finnish research programme on reactor safety 1995-1998. Final Symposium

    International Nuclear Information System (INIS)

    Vanttola, T.

    1998-01-01

    The Reactor Safety (RETU, 1995-1998) research programme concentrated on search of safe limits for nuclear fuel and the reactor core, accident management methods and risk management of nuclear power plants. The total volume of the programme was 100 person years and funding FIM 58 million. This symposium report summarises the research fields, the objectives and the main results obtained. In the field of operational margins of a nuclear reactor, the behaviour of high burnup nuclear fuel was studied both in normal operation and during power transients. The static and dynamic reactor analysis codes were developed and validated to cope with new fuel designs and complicated three-dimensional reactivity transients. Advanced flow models and numerical solution methods for the dynamics codes were developed and tested. Research on accident management developed and validated calculation methods needed to plan preventive measures and to train the personnel to severe accident mitigation. Efforts were made to reduce uncertainties in phenomena important in severe accidents and to study actions planned for accident management. The programme included experimental work, but also participation in large international tests. The Finnish thermal-hydraulic test facility PACTEL was used extensively for the evaluation of the VVER-440 plant accident behaviour, for the validation of the accident analysis computer codes and for the testing of passive safety system concepts for future plant designs. In risk management probabilistic methods were developed for safety related decision making and for complex event sequences. Effects of maintenance on safety were studied and effective methods for assessment of human reliability and safety critical organisations were searched. To enhance human competencies in control of complex environments, practical tools for training and continuous learning were worked out, and methods to evaluate appropriateness of control room design were developed. (orig)

  6. Co-ordinated research and environmental surveillance programme related to sea disposal of radioactive waste

    International Nuclear Information System (INIS)

    1996-01-01

    The co-ordinated Research and Environmental Surveillance Programme relevant to sea disposal of radioactive waste (CRESP) was created in 1981 in the framework of the 1977 Decision of the OECD Council establishing a Multilateral Consultation and Surveillance Mechanism for Sea Dumping of Radioactive Waste. CRESP was essentially a scientific research programme. Its main objective was to increase the knowledge of processes controlling the transfer of radionuclides in the marine environment, so that safety assessments could be based on more accurate and comprehensive scientific data. From 1986, in response to a request from the Paris Commission, CRESP also considered the scientific aspects of coastal releases. CRESP made it possible to co-ordinate national research activities and generated an important international co-operation in its areas of work. The vast amount of scientific information gathered in this framework increased strongly our knowledge of the impact of radionuclides introduced to the deep sea environment. In particular, CRESP provided the basis for a comprehensive safety analysis of sea dumping operations. This study, published by the NEA in 1985, is still e reference on the subject. In November 1993, the Sixteenth Consultative Meeting of Contracting Parties to the London Convention 1972 voted a total ban on the disposal at sea of radioactive wastes and other radioactive matter. Considering this decision, the conclusions of the 1985 safety analysis, and CRESP's view that new scientific findings are unlikely to alter these conclusions, the NEA Steering Committee for nuclear Energy decided in October 1995 to terminate the programme. The present report summarises the knowledge accumulated within CRESP over its fifteen years of existence. (author)

  7. A study of the National Physical Laboratory microdosimetry research programme in collaboration with the University of Leeds

    International Nuclear Information System (INIS)

    Menzel, H.G.

    1987-11-01

    A study of the present programme of work carried out by the National Physical Laboratory and the University of Leeds, has been carried out. The study is based on the use of the tissue-equivalent proportional counter in microdosimetic techniques in radiation protection for monoenergetic neutrons or reference radionuclide neutron sources. This report comments on the programme as a whole and provides recommendations for future research work, taking into account the research programmes carried out at other institutions. It also attempts to summarise the present state of knowledge and experience associated with the application of this technique to radiation fields met in routine radiation protection. (author)

  8. 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

  9. EU-funded malaria research under the 6th and 7th Framework Programmes for research and technological development.

    Science.gov (United States)

    Holtel, Andreas; Troye-Blomberg, Marita; Penas-Jimenez, Inmaculada

    2011-01-14

    While malaria research has traditionally been strong in Europe, targeted and sustained support for cooperative malaria research at EU level, namely through the EU's 6th and 7th Framework Programmes for research and technological development, FP6 (2002-2006) and FP7 (2007-2013), has boosted both impact and visibility of European malaria research. Most of the European malaria research community is now organized under a number of comprehensive and complementary research networks and projects, assembled around four key areas: (1) fundamental research on the malaria parasite and the disease, (2) development of new malaria drugs, (3) research and development of a malaria vaccine, and (4) research to control the malaria-transmitting mosquito vector. Considerable efforts were undertaken to ensure adequate participation of research groups from disease-endemic countries, in particular from Africa, with the long-term aim to strengthen cooperative links and research capacities in these countries. The concept of organizing European research through major strategic projects to form a "European Research Area" (ERA) was originally developed in the preparation of FP6, and ERA formation has now turned into a major EU policy objective explicitly inscribed into the Lisbon Treaty. EU-funded malaria research may serve as a showcase to demonstrate how ERA formation can successfully be implemented in a given area of science when several surrounding parameters converge to support implementation of this strategic concept: timely coincidence of political stimuli, responsive programming, a clearly defined--and well confined--area of research, and the readiness of the targeted research community who is well familiar with transnational cooperation at EU level. Major EU-funded malaria projects have evolved into thematic and organizational platforms that can collaborate with other global players. Europe may thus contribute more, and better, to addressing the global research agenda for malaria.

  10. Co-ordinated research programme on operator support systems in nuclear power plants. Working material

    International Nuclear Information System (INIS)

    1993-01-01

    In September 1991 the Co-ordinated Research Programme (CRP) on ''Operator Support Systems (OSSs) in Nuclear Power Plants'' was approved in the framework of the Project ''Man-Machine Interface Studies''. The main objective of the programme is to provide guidance and technology transfer in the development and implementation of OSSs. This includes the experience with man-machine interfaces and closely related issues such as control and instrumentation, the use of computers, and operator qualification. The first Co-ordinated Research Meeting held in Vienna, 13-16 October 1992, prepared a summary report which defined the tasks and the responsibilities of the CRP participants. A time schedule and future actions were also agreed upon at this meeting. The second meeting was held in Budapest, Hungary, from 5 to 8 October 1993 and was sponsored by the KFKI Atomic Energy Research Institute. The meeting reviewed the progress of the tasks defined by the first meeting, considered reports on national activities in the subject area, and agreed on time schedule and future actions. The present volume contains: (1) report prepared by the CRP meeting, (2) reports presented by the national delegates, and (3) CRP background and working plan. Refs, figs and tabs

  11. Research plan on programmable automation systems in nuclear power plants (OHA) in 1995-1998

    International Nuclear Information System (INIS)

    Haapanen, P.; Pulkkinen, U.; Korhonen, J.

    1995-05-01

    The main purpose of nuclear energy research is to ensure the safety and continued development of Finnish nuclear power plants - a task which places high demands on expertise needed to support the work of public authorities and power companies. A factor necessarily influencing the orientation of the research is the Parliament's decision of late 1993 against further nuclear capacity in the country. Therefore the main emphasis of research shall be directed towards the ensuring the safety of existing plants and the continuous development of their safety along the progress of the science and technology. Anyhow, the preparedness for constructing new plants shall also be preserved. The utilization of programmable digital automation technology for the safety critical functions is the most significant change in the new plants, but also in existing plants this technology will be used for replacing and complementing the ageing automation systems. The safety evaluation of programmable digital systems can not be based on methods applied to conventional analog systems but new evaluation methods and tools must be developed for the assessing of their acceptability. (5 refs., 1 fig., 2 tabs.)

  12. Research reactor core conversion programmes, Department of Research and Isotopes, International Atomic Energy Agency

    International Nuclear Information System (INIS)

    Muranaka, R.G.

    1985-01-01

    In order to put the problem of core conversion into perspective, statistical information on research reactors on a global scale is presented (from IAEA Research reactor Data Base). This paper describes the research reactor core conversion program of the Department of Research and Isotopes. Technical committee Meetings were held on the subject of research reactor core conversion since 1978, and results of these meetings are published in TECDOC-233, TECDOC-324, TECDOC-304. Additional publications are being prepared, several missions of experts have visited countries to discuss and help to plan core conversion programs; training courses and seminars were organised; IAEA has supported attendance of participants from developing countries to RERTR Meetings

  13. 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

  14. 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

  15. Management strategies to utilize salt affected soils. Isotopic and conventional research methods. Results of a co-ordinated research programme

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-01

    This document summarizes the results of a co-ordinated research programme on ``The Use of Nuclear Techniques for Improvement of Crop Production in Salt-affected Soils``. It aims at providing scientists experimental evidence of demonstrating technical feasibility of biological amelioration of salt affected soils as an alternative option of using expensive chemical amendments in soil reclamation complementing engineering structures of farm drainage systems or option of leaving the saline areas as barren lands in spite of the fact that arable agricultural lands have exhausted. 68 refs, 26 figs, 32 tabs.

  16. Management strategies to utilize salt affected soils. Isotopic and conventional research methods. Results of a co-ordinated research programme

    International Nuclear Information System (INIS)

    1995-07-01

    This document summarizes the results of a co-ordinated research programme on ''The Use of Nuclear Techniques for Improvement of Crop Production in Salt-affected Soils''. It aims at providing scientists experimental evidence of demonstrating technical feasibility of biological amelioration of salt affected soils as an alternative option of using expensive chemical amendments in soil reclamation complementing engineering structures of farm drainage systems or option of leaving the saline areas as barren lands in spite of the fact that arable agricultural lands have exhausted. 68 refs, 26 figs, 32 tabs

  17. Applications of nuclear analytical techniques in human nutrition research as exemplified by research programmes of the International Atomic Energy Agency

    International Nuclear Information System (INIS)

    Parr, R.M.

    1987-01-01

    In human nutrition research, nuclear analytical techniques, particularly neutron activation analysis (NAA), are used mainly for the in vitro study of trace elements. According to work sponsored by the IAEA, up to 15 trace elements and 5 minor elements of nutritional interest may be determined in biological materials by NAA with good accuracy and precision. A programme is described in which NAA was used for the determination of 14 trace elements and one minor element in human milk. NAA also plays an important role in the certification of reference materials for nutritional studies. (author) 17 refs.; 6 tables

  18. Waste management research abstracts no. 22. Information on radioactive waste programmes in progress

    International Nuclear Information System (INIS)

    1995-07-01

    The research abstracts contained in this issue have been collected during recent months and cover the period between January 1992 - February 1994 (through July 1994 for abstracts from the United States). The abstracts reflect research currently in progress in the field of radioactive waste management: environmental impacts, site selection, decontamination and decommissioning, environmental restoration and legal aspects of radioactive waste management. Though the information contained in this publication covers a wide range of programmes in many countries, the WMRA should not be interpreted as providing a complete survey of on-going research and IAEA Member States. For the first time, the abstracts published in document are only in English language. In addition, the abstracts received for this issue have been assigned INIS subject category codes and thesaurus terms to facilitate searches and also to fully utilize established sets of technical categories and terms

  19. Overview of EU research activities in transmutation and innovative reactor systems within the Euratom framework programmes

    International Nuclear Information System (INIS)

    Bhatnagar, V.

    2009-01-01

    European Community (EC) (currently 27 Member States) shared-cost research has been organised in Framework Programmes (FP) of durations of 4 - 5 years since 1984. The 6th European Atomic Energy Community (EURATOM) Framework Programme (2002 - 06) and the current 7th FP (2007 - 11) have been allocated a fission research budget respectively of 209 and 287 Million Euro from the EC. There are 10 projects (total budget 70 M Euro, EC contribution 38 M Euro) in all aspects of transmutation ranging from road-mapping exercise to large integrated projects on accelerator driven systems, lead-cooled fast critical systems for waste transmutation, technology, fuel, accelerator facilities for nuclear data etc. In Innovative Reactor concepts, there are about half-a-dozen projects (total budget 30 M Euro, EC contribution 16 M Euro) including High Temperature Reactors, Gas-cooled Fast reactors, road-mapping exercise on sodium fast reactors etc. The main research and training activities in FP7 are: management of radioactive waste, reactor systems, radiation protection, infrastructures, human resources and mobility and training. In the two call for proposals (2007 and 2008) in FP7, 8 projects have been accepted in transmutation and innovative reactor concepts (total budget 53 M Euro, EC contribution 32 M Euro). These research projects cover activities ranging from materials, fuels, treatment of irradiated graphite waste, European sodium fast reactor to the establishment of a Central Design Team of a fast-spectrum transmutation device in Europe. The third call for proposals is underway requesting proposals on nuclear data, thermal hydraulics, gas and lead-cooled fast reactor systems with a total EC budget of 20 M Euro. International collaboration is an important element of the EU research policy. This overview paper will present elements of the strategy of EURATOM research and training in waste management including accelerator driven transmutation systems and Innovative reactor concepts

  20. Setting research priorities to reduce malaria burden in a post graduate training programme: lessons learnt from the Nigeria field epidemiology and laboratory training programme scientific workshop.

    Science.gov (United States)

    Fawole, Olufunmilayo I; Ajumobi, Olufemi; Poggensee, Gabriele; Nguku, Patrick

    2014-01-01

    Although several research groups within institutions in Nigeria have been involved in extensive malaria research, the link between the research community and policy formulation has not been optimal. The workshop aimed to assist post graduate students to identify knowledge gaps and to develop relevant Malaria-related research proposals in line with identified research priorities. A training needs assessment questionnaire was completed by 22 students two week prior to the workshop. Also, a one page concept letter was received from 40 residents. Thirty students were selected based the following six criteria: - answerability and ethics; efficacy and impact; deliverability, affordability; scalability, sustainability; health systems, partnership and community involvement; and equity in achieved disease burden reduction. The workshop was over a three day period. The participants at the workshop were 30 Nigeria Field Epidemiology and Laboratory Training Programme (NFELTP) residents from cohorts 4 and 5. Ten technical papers were presented by the experts from the academia, National Malaria Elimination (NMEP) Programme, NFELTP Faculty and Implementing partners including CDC/PMI. Draft proposals were developed and presented by the residents. The "strongest need" for training was on malaria prevention, followed by malaria diagnosis. Forty seven new research questions were generated, while the 19 developed by the NMEP were shared. Evaluation revealed that all (100%) students either "agreed" that the workshop objectives were met. Full proposals were developed by some of the residents. A debriefing meeting was held with the NMEP coordinator to discuss funding of the projects. Future collaborative partnership has developed as the residents have supported NMEP to develop a research protocol for a national evaluation. Research prioritization workshops are required in most training programmes to ensure that students embark on studies that address the research needs of their country