Science.gov

Sample records for reactor demo goals

  1. Beyond ITER: neutral beams for a demonstration fusion reactor (DEMO) (invited).

    PubMed

    McAdams, R

    2014-02-01

    In the development of magnetically confined fusion as an economically sustainable power source, International Tokamak Experimental Reactor (ITER) is currently under construction. Beyond ITER is the demonstration fusion reactor (DEMO) programme in which the physics and engineering aspects of a future fusion power plant will be demonstrated. DEMO will produce net electrical power. The DEMO programme will be outlined and the role of neutral beams for heating and current drive will be described. In particular, the importance of the efficiency of neutral beam systems in terms of injected neutral beam power compared to wallplug power will be discussed. Options for improving this efficiency including advanced neutralisers and energy recovery are discussed. PMID:24593596

  2. Beyond ITER: Neutral beams for a demonstration fusion reactor (DEMO) (invited)

    SciTech Connect

    McAdams, R.

    2014-02-15

    In the development of magnetically confined fusion as an economically sustainable power source, International Tokamak Experimental Reactor (ITER) is currently under construction. Beyond ITER is the demonstration fusion reactor (DEMO) programme in which the physics and engineering aspects of a future fusion power plant will be demonstrated. DEMO will produce net electrical power. The DEMO programme will be outlined and the role of neutral beams for heating and current drive will be described. In particular, the importance of the efficiency of neutral beam systems in terms of injected neutral beam power compared to wallplug power will be discussed. Options for improving this efficiency including advanced neutralisers and energy recovery are discussed.

  3. Design of the DEMO Fusion Reactor Following ITER

    PubMed Central

    Garabedian, Paul R.; McFadden, Geoffrey B.

    2009-01-01

    Runs of the NSTAB nonlinear stability code show there are many three-dimensional (3D) solutions of the advanced tokamak problem subject to axially symmetric boundary conditions. These numerical simulations based on mathematical equations in conservation form predict that the ITER international tokamak project will encounter persistent disruptions and edge localized mode (ELMS) crashes. Test particle runs of the TRAN transport code suggest that for quasineutrality to prevail in tokamaks a certain minimum level of 3D asymmetry of the magnetic spectrum is required which is comparable to that found in quasiaxially symmetric (QAS) stellarators. The computational theory suggests that a QAS stellarator with two field periods and proportions like those of ITER is a good candidate for a fusion reactor. For a demonstration reactor (DEMO) we seek an experiment that combines the best features of ITER, with a system of QAS coils providing external rotational transform, which is a measure of the poloidal field. We have discovered a configuration with unusually good quasisymmetry that is ideal for this task.

  4. Modeling an unmitigated thermal quench event in a large field magnet in a DEMO reactor

    SciTech Connect

    Merrill, Brad J.

    2015-03-25

    The superconducting magnet systems of future fusion reactors, such as a Demonstration Power Plant (DEMO), will produce magnetic field energies in the 10 s of GJ range. The release of this energy during a fault condition could produce arcs that can damage the magnets of these systems. The public safety consequences of such events must be explored for a DEMO reactor because the magnets are located near the DEMO's primary radioactive confinement barrier, the reactor's vacuum vessel (VV). Great care will be taken in the design of DEMO's magnet systems to detect and provide a rapid field energy dump to avoid any accidents conditions. During an event when a fault condition proceeds undetected, the potential of producing melting of the magnet exists. If molten material from the magnet impinges on the walls of the VV, these walls could fail, resulting in a pathway for release of radioactive material from the VV. A model is under development at Idaho National Laboratory (INL) called MAGARC to investigate the consequences of this accident in a large toroidal field (TF) coil. Recent improvements to this model are described in this paper, along with predictions for a DEMO relevant event in a toroidal field magnet.

  5. Modeling an unmitigated thermal quench event in a large field magnet in a DEMO reactor

    DOE PAGESBeta

    Merrill, Brad J.

    2015-03-25

    The superconducting magnet systems of future fusion reactors, such as a Demonstration Power Plant (DEMO), will produce magnetic field energies in the 10 s of GJ range. The release of this energy during a fault condition could produce arcs that can damage the magnets of these systems. The public safety consequences of such events must be explored for a DEMO reactor because the magnets are located near the DEMO's primary radioactive confinement barrier, the reactor's vacuum vessel (VV). Great care will be taken in the design of DEMO's magnet systems to detect and provide a rapid field energy dump tomore » avoid any accidents conditions. During an event when a fault condition proceeds undetected, the potential of producing melting of the magnet exists. If molten material from the magnet impinges on the walls of the VV, these walls could fail, resulting in a pathway for release of radioactive material from the VV. A model is under development at Idaho National Laboratory (INL) called MAGARC to investigate the consequences of this accident in a large toroidal field (TF) coil. Recent improvements to this model are described in this paper, along with predictions for a DEMO relevant event in a toroidal field magnet.« less

  6. Research at ITER towards DEMO: Specific reactor diagnostic studies to be carried out on ITER

    SciTech Connect

    Krasilnikov, A. V.; Kaschuck, Y. A.; Vershkov, V. A.; Petrov, A. A.; Petrov, V. G.; Tugarinov, S. N.

    2014-08-21

    In ITER diagnostics will operate in the very hard radiation environment of fusion reactor. Extensive technology studies are carried out during development of the ITER diagnostics and procedures of their calibration and remote handling. Results of these studies and practical application of the developed diagnostics on ITER will provide the direct input to DEMO diagnostic development. The list of DEMO measurement requirements and diagnostics will be determined during ITER experiments on the bases of ITER plasma physics results and success of particular diagnostic application in reactor-like ITER plasma. Majority of ITER diagnostic already passed the conceptual design phase and represent the state of the art in fusion plasma diagnostic development. The number of related to DEMO results of ITER diagnostic studies such as design and prototype manufacture of: neutron and γ–ray diagnostics, neutral particle analyzers, optical spectroscopy including first mirror protection and cleaning technics, reflectometry, refractometry, tritium retention measurements etc. are discussed.

  7. Research at ITER towards DEMO: Specific reactor diagnostic studies to be carried out on ITER

    NASA Astrophysics Data System (ADS)

    Krasilnikov, A. V.; Kaschuck, Y. A.; Vershkov, V. A.; Petrov, A. A.; Petrov, V. G.; Tugarinov, S. N.

    2014-08-01

    In ITER diagnostics will operate in the very hard radiation environment of fusion reactor. Extensive technology studies are carried out during development of the ITER diagnostics and procedures of their calibration and remote handling. Results of these studies and practical application of the developed diagnostics on ITER will provide the direct input to DEMO diagnostic development. The list of DEMO measurement requirements and diagnostics will be determined during ITER experiments on the bases of ITER plasma physics results and success of particular diagnostic application in reactor-like ITER plasma. Majority of ITER diagnostic already passed the conceptual design phase and represent the state of the art in fusion plasma diagnostic development. The number of related to DEMO results of ITER diagnostic studies such as design and prototype manufacture of: neutron and γ-ray diagnostics, neutral particle analyzers, optical spectroscopy including first mirror protection and cleaning technics, reflectometry, refractometry, tritium retention measurements etc. are discussed.

  8. Plasma regimes and research goals of JT-60SA towards ITER and DEMO

    NASA Astrophysics Data System (ADS)

    Kamada, Y.; Barabaschi, P.; Ishida, S.; Ide, S.; Lackner, K.; Fujita, T.; Bolzonella, T.; Suzuki, T.; Matsunaga, G.; Yoshida, M.; Shinohara, K.; Urano, H.; Nakano, T.; Sakurai, S.; Kawashima, H.; JT-60SA Team

    2011-07-01

    The JT-60SA device has been designed as a highly shaped large superconducting tokamak with a variety of plasma actuators (heating, current drive, momentum input, stability control coils, resonant magnetic perturbation coils, W-shaped divertor, fuelling, pumping, etc) in order to satisfy the central research needs for ITER and DEMO. In the ITER- and DEMO-relevant plasma parameter regimes and with DEMO-equivalent plasma shapes, JT-60SA quantifies the operation limits, plasma responses and operational margins in terms of MHD stability, plasma transport and confinement, high-energy particle behaviour, pedestal structures, scrape-off layer and divertor characteristics. By integrating advanced studies in these research fields, the project proceeds 'simultaneous and steady-state sustainment of the key performances required for DEMO' with integrated control scenario development applicable to the highly self-regulating burning high-β high bootstrap current fraction plasmas.

  9. Effect on the tritium breeding ratio for a distributed ICRF antenna in a DEMO reactor

    NASA Astrophysics Data System (ADS)

    Garcia, A.; Noterdaeme, J.-M.; Fischer, U.; Dies, J.

    2015-12-01

    The paper reports results of MCNP-5 calculations to assess the effect on the Tritium Breeding Ratio (TBR) when integrating a distributed Ion Cyclotron Range of Frequencies (ICRF) antenna in the blanket of DEMO fusion power reactor. The calculations consider different parameters such as the ICRF covering ratio and the type of breeding blanket including the Helium Cooled Pebble Bed (HCPB) and the Helium Cooled Lithium Lead (HCLL) concepts. For an antenna with a full toroidal circumference of 360°, located poloidally at 40° with a poloidal extension of 1 m, the reduction of the TBR is -0.349% for the HCPB blanket and -0.532% for the HCLL blanket. The distributed ICRF antenna is thus shown to have only a marginal effect on the TBR of the DEMO reactor.

  10. Effect on the tritium breeding ratio for a distributed ICRF antenna in a DEMO reactor

    SciTech Connect

    Garcia, A.; Noterdaeme, J.-M.; Fischer, U.; Dies, J.

    2015-12-10

    The paper reports results of MCNP-5 calculations to assess the effect on the Tritium Breeding Ratio (TBR) when integrating a distributed Ion Cyclotron Range of Frequencies (ICRF) antenna in the blanket of DEMO fusion power reactor. The calculations consider different parameters such as the ICRF covering ratio and the type of breeding blanket including the Helium Cooled Pebble Bed (HCPB) and the Helium Cooled Lithium Lead (HCLL) concepts. For an antenna with a full toroidal circumference of 360°, located poloidally at 40° with a poloidal extension of 1 m, the reduction of the TBR is −0.349% for the HCPB blanket and −0.532% for the HCLL blanket. The distributed ICRF antenna is thus shown to have only a marginal effect on the TBR of the DEMO reactor.

  11. Development of fusion blanket technology for the DEMO reactor.

    PubMed

    Colling, B R; Monk, S D

    2012-07-01

    The viability of various materials and blanket designs for use in nuclear fusion reactors can be tested using computer simulations and as parts of the test blanket modules within the International Thermonuclear Experimental Reactor (ITER) facility. The work presented here focuses on blanket model simulations using the Monte Carlo simulation package MCNPX (Computational Physics Division Los Alamos National Laboratory, 2010) and FISPACT (Forrest, 2007) to evaluate the tritium breeding capability of a number of solid and liquid breeding materials. The liquid/molten salt breeders are found to have the higher tritium breeding ratio (TBR) and are to be considered for further analysis of the self sufficiency timing. PMID:22112596

  12. Materials for DEMO and reactor applications—boundary conditions and new concepts

    NASA Astrophysics Data System (ADS)

    Coenen, J. W.; Antusch, S.; Aumann, M.; Biel, W.; Du, J.; Engels, J.; Heuer, S.; Houben, A.; Hoeschen, T.; Jasper, B.; Koch, F.; Linke, J.; Litnovsky, A.; Mao, Y.; Neu, R.; Pintsuk, G.; Riesch, J.; Rasinski, M.; Reiser, J.; Rieth, M.; Terra, A.; Unterberg, B.; Weber, Th; Wegener, T.; You, J.-H.; Linsmeier, Ch

    2016-02-01

    DEMO is the name for the first stage prototype fusion reactor considered to be the next step after ITER towards realizing fusion. For the realization of fusion energy especially, materials questions pose a significant challenge already today. Heat, particle and neutron loads are a significant problem to material lifetime when extrapolating to DEMO. For many of the issues faced, advanced materials solutions are under discussion or already under development. In particular, components such as the first wall and the divertor of the reactor can benefit from introducing new approaches such as composites or new alloys into the discussion. Cracking, oxidation as well as fuel management are driving issues when deciding for new materials. Here {{{W}}}{{f}}/{{W}} composites as well as strengthened CuCrZr components together with oxidation resilient tungsten alloys allow the step towards a fusion reactor. In addition, neutron induced effects such as transmutation, embrittlement and after-heat and activation are essential. Therefore, when designing a component an approach taking into account all aspects is required.

  13. Fabrication of a He-cooled divertor module for DEMO reactor

    NASA Astrophysics Data System (ADS)

    Gervash, A.; Giniyatulin, R.; Ihli, T.; Krauss, W.; Makhankov, A.; Mazul, I.; Norajitra, P.; Yablokov, N.

    2007-08-01

    One current design of the divertor for a fusion reactor like DEMO uses He-cooled thimble-like tungsten, which is covered by sacrificial tungsten tile. Each thimble has to be connected with a supporting unit made from ferritic steel. This paper describes the development of joining techniques between tungsten thimbles and steel supporting units. Paper also provides an evaluation of simple geometries up to more complex conical interlocks filled with cast copper. Four candidates tungsten alloys (WL10, W-single crystal, W-Cu composite and chemical vapour deposited (CVD) tungsten) were experimentally checked by 'non-isothermal' heating to characterize the thermal gradient in the range 600 °C (for joint) and more than 1000 °C (for thimble top) using a special testing procedure. Basing on the test results, several mock-ups were manufactured for future high heat flux testing in a helium loop.

  14. Radioactive waste produced by DEMO and commerical fusion reactors extrapolated from ITER and advanced data bases

    SciTech Connect

    Stacey, W.M.; Hertel, N.E.; Hoffman, E.A.

    1994-12-31

    The potential for providing energy with minimal environmental impact is a powerful motivation for the development of fusion and is the long-term objective of most fusion programs. However, the societal acceptability of magnetic fusion may well be decided in the near-term when decisions are taken on the construction of DEMO to follow ITER (if not when the construction decision is taken on ITER). Component wastes were calculated for DEMOs based on each data base by first calculating reactor sizes needed to satisfy the physics, stress and radiation attenuation requirements, and then calculating component replacement rates based on radiation damage and erosion limits. Then, radioactive inventories were calculated and compared to a number of international criteria for {open_quote}near-surface{close_quote} burial. None of the components in either type of design would meet the Japanese LLW criterion (<1 Ci/m{sup 3}) within 10 years of shutdown, although the advanced (V/Li) blanket would do so soon afterwards. The vanadium first wall, divertor and blanket would satisfy the IAEA LLW criterion (<2 mSv/h contact dose) within about 10 years after shutdown, but none of the stainless steel or copper components would. All the components in the advanced data base designs except the stainless steel vacuum vessel and shield readily satisfy the US extended 10CFR61 intruder dose criterion, but none of the components in the {open_quotes}ITER data base{close_quotes} designs do so. It seems unlikely that a stainless steel first wall or a copper divertor plate could satisfy the US (class C) criterion for near surface burial, much less the more stringent international, criteria. On the other hand, the first wall, divertor and blanket of the V/Li system would still satisfy the intruder dose concentration limits even if the dose criterion was reduced by two orders of magnitude.

  15. Current generation by helicons and lower hybrid waves in modern tokamaks and reactors ITER and DEMO. Scenarios, modeling and antennae

    SciTech Connect

    Vdovin, V. L.

    2013-02-15

    The innovative concept and 3D full-wave code modeling the off-axis current drive by radio-frequency (RF) waves in large-scale tokamaks, ITER and DEMO, for steady-state operation with high efficiency is proposed. The scheme uses the helicon radiation (fast magnetosonic waves at high (20-40) ion cyclotron frequency harmonics) at frequencies of 500-700 MHz propagating in the outer regions of the plasmas with a rotational transform. It is expected that the current generated by helicons, in conjunction with the bootstrap current, ensure the maintenance of a given value of the total current in the stability margin q(0) {>=} 2 and q(a) {>=} 4, and will help to have regimes with a negative magnetic shear and internal transport barrier to ensure stability at high normalized plasma pressure {beta}{sub N} > 3 (the so-called advanced scenarios) of interest for the commercial reactor. Modeling with full-wave three-dimensional codes PSTELION and STELEC showed flexible control of the current profile in the reactor plasmas of ITER and DEMO, using multiple frequencies, the positions of the antennae and toroidal wave slow down. Also presented are the results of simulations of current generation by helicons in the DIII-D, T-15MD, and JT-60AS tokamaks. Commercially available continuous-wave klystrons of the MW/tube range are promising for commercial stationary fusion reactors. The compact antennae of the waveguide type are proposed, and an example of a possible RF system for today's tokamaks is given. The advantages of the scheme (partially tested at lower frequencies in tokamaks) are a significant decline in the role of parametric instabilities in the plasma periphery, the use of electrically strong resonator-waveguide type antennae, and substantially greater antenna-plasma coupling.

  16. Neutronic design studies of a conceptual DCLL fusion reactor for a DEMO and a commercial power plant

    NASA Astrophysics Data System (ADS)

    Palermo, I.; Veredas, G.; Gómez-Ros, J. M.; Sanz, J.; Ibarra, A.

    2016-01-01

    Neutronic analyses or, more widely, nuclear analyses have been performed for the development of a dual-coolant He/LiPb (DCLL) conceptual design reactor. A detailed three-dimensional (3D) model has been examined and optimized. The design is based on the plasma parameters and functional materials of the power plant conceptual studies (PPCS) model C. The initial radial-build for the detailed model has been determined according to the dimensions established in a previous work on an equivalent simplified homogenized reactor model. For optimization purposes, the initial specifications established over the simplified model have been refined on the detailed 3D design, modifying material and dimension of breeding blanket, shield and vacuum vessel in order to fulfil the priority requirements of a fusion reactor in terms of the fundamental neutronic responses. Tritium breeding ratio, energy multiplication factor, radiation limits in the TF coils, helium production and displacements per atom (dpa) have been calculated in order to demonstrate the functionality and viability of the reactor design in guaranteeing tritium self-sufficiency, power efficiency, plasma confinement, and re-weldability and structural integrity of the components. The paper describes the neutronic design improvements of the DCLL reactor, obtaining results for both DEMO and power plant operational scenarios.

  17. Combination of helical ferritic-steel inserts and flux-tube-expansion divertor for the heat control in tokamak DEMO reactor

    NASA Astrophysics Data System (ADS)

    Takizuka, T.; Tokunaga, S.; Hoshino, K.; Shimizu, K.; Asakura, N.

    2015-08-01

    Edge localized modes (ELMs) in the H-mode operation of tokamak reactors may be suppressed/mitigated by the resonant magnetic perturbation (RMP), but RMP coils are considered incompatible with DEMO reactors under the strong neutron flux. We propose an innovative concept of the RMP without installing coils but inserting ferritic steels of the helical configuration. Helically perturbed field is naturally formed in the axisymmetric toroidal field through the helical ferritic steel inserts (FSIs). When ELMs are avoided, large stationary heat load on divertor plates can be reduced by adopting a flux-tube-expansion (FTE) divertor like an X divertor. Separatrix shape and divertor-plate inclination are similar to those of a simple long-leg divertor configuration. Combination of the helical FSIs and the FTE divertor is a suitable method for the heat control to avoid transient ELM heat pulse and to reduce stationary divertor heat load in a tokamak DEMO reactor.

  18. Model and Mockup of DEMO Ceramic Breeding Zone for Testing in the IVV-2M Reactor

    SciTech Connect

    Kapychev, V.; Gorokhov, V.; Davydov, D.

    2001-01-15

    A model of a ceramic breeding zone has been designed and manufactured for testing in the IVV-2M fission reactor. The model contains both lithium orthosilicate and beryllium spheroid particles 1 to 2 mm in diameter. The structural material is ferritic-martensitic stainless steel. In addition, a mockup of the model for verification of neutronics calculation methods has been designed and manufactured. A special facility (Functional In-Reactor Investigations of Tritium-Breeding Models) has been designed, fabricated, and assembled at the reactor for studying the kinetics of tritium extraction from the ceramic material under irradiation. Neutronic and thermo-hydraulic calculations and an initial measurement of tritium release from the model under reactor irradiation have been performed.

  19. Methods and strategies for future reactor safety goals

    NASA Astrophysics Data System (ADS)

    Arndt, Steven Andrew

    There have been significant discussions over the past few years by the United States Nuclear Regulatory Commission (NRC), the Advisory Committee on Reactor Safeguards (ACRS), and others as to the adequacy of the NRC safety goals for use with the next generation of nuclear power reactors to be built in the United States. The NRC, in its safety goals policy statement, has provided general qualitative safety goals and basic quantitative health objectives (QHOs) for nuclear reactors in the United States. Risk metrics such as core damage frequency (CDF) and large early release frequency (LERF) have been used as surrogates for the QHOs. In its review of the new plant licensing policy the ACRS has looked at the safety goals, as has the NRC. A number of issues have been raised including what the Commission had in mind when it drafted the safety goals and QHOs, how risk from multiple reactors at a site should be combined for evaluation, how the combination of a new and old reactor at the same site should be evaluated, what the criteria for evaluating new reactors should be, and whether new reactors should be required to be safer than current generation reactors. As part of the development and application of the NRC safety goal policy statement the Commissioners laid out the expectations for the safety of a nuclear power plant but did not address the risk associated with current multi-unit sites, potential modular reactor sites, and hybrid sites that could contain current generation reactors, new passive reactors, and/or modular reactors. The NRC safety goals and the QHOs refer to a "nuclear power plant," but do not discuss whether a "plant" refers to only a single unit or all of the units on a site. There has been much discussion on this issue recently due to the development of modular reactors. Additionally, the risk of multiple reactor accidents on the same site has been largely ignored in the probabilistic risk assessments (PRAs) done to date, and in most risk

  20. Current generation by helicons and LH waves in modern tokamaks and reactors FNSF-AT, ITER and DEMO. Scenarios, modeling and antennae

    SciTech Connect

    Vdovin, V.

    2014-02-12

    The Innovative concept and 3D full wave code modeling Off-axis current drive by RF waves in large scale tokamaks, reactors FNSF-AT, ITER and DEMO for steady state operation with high efficiency was proposed [1] to overcome problems well known for LH method [2]. The scheme uses the helicons radiation (fast magnetosonic waves at high (20–40) IC frequency harmonics) at frequencies of 500–1000 MHz, propagating in the outer regions of the plasmas with a rotational transform. It is expected that the current generated by Helicons will help to have regimes with negative magnetic shear and internal transport barrier to ensure stability at high normalized plasma pressure β{sub N} > 3 (the so-called Advanced scenarios) of interest for FNSF and the commercial reactor. Modeling with full wave three-dimensional codes PSTELION and STELEC2 showed flexible control of the current profile in the reactor plasmas of ITER, FNSF-AT and DEMO [2,3], using multiple frequencies, the positions of the antennae and toroidal waves slow down. Also presented are the results of simulations of current generation by helicons in tokamaks DIII-D, T-15MD and JT-60SA [3]. In DEMO and Power Plant antenna is strongly simplified, being some analoge of mirrors based ECRF launcher, as will be shown. For spherical tokamaks the Helicons excitation scheme does not provide efficient Off-axis CD profile flexibility due to strong coupling of helicons with O-mode, also through the boundary conditions in low aspect machines, and intrinsic large amount of trapped electrons, as is shown by STELION modeling for the NSTX tokamak. Brief history of Helicons experimental and modeling exploration in straight plasmas, tokamaks and tokamak based fusion Reactors projects is given, including planned joint DIII-D – Kurchatov Institute experiment on helicons CD [1].

  1. Current generation by helicons and LH waves in modern tokamaks and reactors FNSF-AT, ITER and DEMO. Scenarios, modeling and antennae

    NASA Astrophysics Data System (ADS)

    Vdovin, V.

    2014-02-01

    The Innovative concept and 3D full wave code modeling Off-axis current drive by RF waves in large scale tokamaks, reactors FNSF-AT, ITER and DEMO for steady state operation with high efficiency was proposed [1] to overcome problems well known for LH method [2]. The scheme uses the helicons radiation (fast magnetosonic waves at high (20-40) IC frequency harmonics) at frequencies of 500-1000 MHz, propagating in the outer regions of the plasmas with a rotational transform. It is expected that the current generated by Helicons will help to have regimes with negative magnetic shear and internal transport barrier to ensure stability at high normalized plasma pressure βN > 3 (the so-called Advanced scenarios) of interest for FNSF and the commercial reactor. Modeling with full wave three-dimensional codes PSTELION and STELEC2 showed flexible control of the current profile in the reactor plasmas of ITER, FNSF-AT and DEMO [2,3], using multiple frequencies, the positions of the antennae and toroidal waves slow down. Also presented are the results of simulations of current generation by helicons in tokamaks DIII-D, T-15MD and JT-60SA [3]. In DEMO and Power Plant antenna is strongly simplified, being some analoge of mirrors based ECRF launcher, as will be shown. For spherical tokamaks the Helicons excitation scheme does not provide efficient Off-axis CD profile flexibility due to strong coupling of helicons with O-mode, also through the boundary conditions in low aspect machines, and intrinsic large amount of trapped electrons, as is shown by STELION modeling for the NSTX tokamak. Brief history of Helicons experimental and modeling exploration in straight plasmas, tokamaks and tokamak based fusion Reactors projects is given, including planned joint DIII-D - Kurchatov Institute experiment on helicons CD [1].

  2. Modelling of pulsed and steady-state DEMO scenarios

    NASA Astrophysics Data System (ADS)

    Giruzzi, G.; Artaud, J. F.; Baruzzo, M.; Bolzonella, T.; Fable, E.; Garzotti, L.; Ivanova-Stanik, I.; Kemp, R.; King, D. B.; Schneider, M.; Stankiewicz, R.; Stępniewski, W.; Vincenzi, P.; Ward, D.; Zagórski, R.

    2015-07-01

    Scenario modelling for the demonstration fusion reactor (DEMO) has been carried out using a variety of simulation codes. Two DEMO concepts have been analysed: a pulsed tokamak, characterized by rather conventional physics and technology assumptions (DEMO1) and a steady-state tokamak, with moderately advanced physics and technology assumptions (DEMO2). Sensitivity to impurity concentrations, radiation, and heat transport models has been investigated. For DEMO2, the impact of current driven non-inductively by neutral beams has been studied by full Monte Carlo simulations of the fast ion distribution. The results obtained are a part of a more extensive research and development (R&D) effort carried out in the EU in order to develop a viable option for a DEMO reactor, to be adopted after ITER for fusion energy research.

  3. R&D around a photoneutralizer-based NBI system (Siphore) in view of a DEMO Tokamak steady state fusion reactor

    NASA Astrophysics Data System (ADS)

    Simonin, A.; Achard, Jocelyn; Achkasov, K.; Bechu, S.; Baudouin, C.; Baulaigue, O.; Blondel, C.; Boeuf, J. P.; Bresteau, D.; Cartry, G.; Chaibi, W.; Drag, C.; de Esch, H. P. L.; Fiorucci, D.; Fubiani, G.; Furno, I.; Futtersack, R.; Garibaldi, P.; Gicquel, A.; Grand, C.; Guittienne, Ph.; Hagelaar, G.; Howling, A.; Jacquier, R.; Kirkpatrick, M. J.; Lemoine, D.; Lepetit, B.; Minea, T.; Odic, E.; Revel, A.; Soliman, B. A.; Teste, P.

    2015-11-01

    Since the signature of the ITER treaty in 2006, a new research programme targeting the emergence of a new generation of neutral beam (NB) system for the future fusion reactor (DEMO Tokamak) has been underway between several laboratories in Europe. The specifications required to operate a NB system on DEMO are very demanding: the system has to provide plasma heating, current drive and plasma control at a very high level of power (up to 150 MW) and energy (1 or 2 MeV), including high performances in term of wall-plug efficiency (η  >  60%), high availability and reliability. To this aim, a novel NB concept based on the photodetachment of the energetic negative ion beam is under study. The keystone of this new concept is the achievement of a photoneutralizer where a high power photon flux (~3 MW) generated within a Fabry-Perot cavity will overlap, cross and partially photodetach the intense negative ion beam accelerated at high energy (1 or 2 MeV). The aspect ratio of the beam-line (source, accelerator, etc) is specifically designed to maximize the overlap of the photon beam with the ion beam. It is shown that such a photoneutralized based NB system would have the capability to provide several tens of MW of D0 per beam line with a wall-plug efficiency higher than 60%. A feasibility study of the concept has been launched between different laboratories to address the different physics aspects, i.e. negative ion source, plasma modelling, ion accelerator simulation, photoneutralization and high voltage holding under vacuum. The paper describes the present status of the project and the main achievements of the developments in laboratories.

  4. Goals.

    ERIC Educational Resources Information Center

    Phillips, David A.; Phillips, Prudence

    1985-01-01

    Presents two discussions which focus on the rationale for and goals of teaching electrochemistry at high school and college levels. The first is "Electrochemistry" by Ronald Perkins and the second is "Goals in Teaching Electrochemistry" by J. T. Maloy. (JN)

  5. Diagnostic systems in DEMO: Engineering design issues

    SciTech Connect

    Todd, T. N.

    2014-08-21

    The diagnostic systems of DEMO that are mounted on or near the torus, whether intended for the monitoring and control functions of the engineering aspects or the physics behaviour of the machine, will have to be designed to suit the hostile nuclear environment. This will be necessary not just for their survival and correct functioning but also to satisfy the pertinent regulatory bodies, especially where any of them relate to machine protection or the prevention or mitigation of accidents foreseen in the safety case. This paper aims to indicate the more important of the reactor design considerations that are likely to apply to diagnostics for DEMO, drawn from experience on JET, the provisions in hand for ITER and modelling results for the wall erosion and neutron damage effects in DEMO.

  6. Diagnostic systems in DEMO: Engineering design issues

    NASA Astrophysics Data System (ADS)

    Todd, T. N.

    2014-08-01

    The diagnostic systems of DEMO that are mounted on or near the torus, whether intended for the monitoring and control functions of the engineering aspects or the physics behaviour of the machine, will have to be designed to suit the hostile nuclear environment. This will be necessary not just for their survival and correct functioning but also to satisfy the pertinent regulatory bodies, especially where any of them relate to machine protection or the prevention or mitigation of accidents foreseen in the safety case. This paper aims to indicate the more important of the reactor design considerations that are likely to apply to diagnostics for DEMO, drawn from experience on JET, the provisions in hand for ITER and modelling results for the wall erosion and neutron damage effects in DEMO.

  7. Compact Stellarator Path to DEMO

    NASA Astrophysics Data System (ADS)

    Lyon, J. F.

    2007-11-01

    Issues for a DEMO reactor are sustaining an ignited/high-Q plasma in steady state, avoiding disruptions and large variations in power flux to the wall, adequate confinement of thermal plasma and alpha-particles, control of a burning plasma, particle and power handling, etc. Compact stellarators have key advantages -- steady-state high-plasma-density operation without external current drive or disruptions, stability without a close conducting wall or active feedback systems, and low recirculating power -- in addition to moderate plasma aspect ratio, good confinement, and high-beta potential. The ARIES-CS study established that compact stellarators can be competitive with tokamaks as reactors. Many of the issues for a compact stellarator DEMO can be answered using results from large tokamaks, ITER D-T experiments and fusion materials, technology and component development programs, in addition to stellarators in operation, under construction or in development. However, a large next-generation stellarator will be needed to address some physics issues: size scaling and confinement at higher parameters, burning plasma issues, and operation with a strongly radiative divertor. Technology issues include simpler coils, structure, and divertor fabrication, and better cost information.

  8. Safety goals and functional performance criteria. [Advanced Reactor Design

    SciTech Connect

    Youngblood, R.W.; Pratt, W.T. ); Hardin, W.B. . Div. of Regulatory Applications)

    1990-01-01

    This report discusses a possible approach to the development of functional performance criteria to be applied to evolutionary LWR designs. Key safety functions are first identified; then, criteria are drawn up for each individual function, based on the premise that no single function's projected unreliability should be allowed to exhaust the safety goal frequencies. In the area of core damage prevention, functional criteria are cast in terms of necessary levels of redundancy and diversity of critical equipment. In the area of core damage mitigation (containment), functional performance criteria are cast with the aim of mitigating post-core-melt phenomena with sufficient assurance to eliminate major uncertainties in containment performance. 9 refs.

  9. Advances in the physics basis for the European DEMO design

    NASA Astrophysics Data System (ADS)

    Wenninger, R.; Arbeiter, F.; Aubert, J.; Aho-Mantila, L.; Albanese, R.; Ambrosino, R.; Angioni, C.; Artaud, J.-F.; Bernert, M.; Fable, E.; Fasoli, A.; Federici, G.; Garcia, J.; Giruzzi, G.; Jenko, F.; Maget, P.; Mattei, M.; Maviglia, F.; Poli, E.; Ramogida, G.; Reux, C.; Schneider, M.; Sieglin, B.; Villone, F.; Wischmeier, M.; Zohm, H.

    2015-06-01

    In the European fusion roadmap, ITER is followed by a demonstration fusion power reactor (DEMO), for which a conceptual design is under development. This paper reports the first results of a coherent effort to develop the relevant physics knowledge for that (DEMO Physics Basis), carried out by European experts. The program currently includes investigations in the areas of scenario modeling, transport, MHD, heating & current drive, fast particles, plasma wall interaction and disruptions.

  10. Identification of Selected Areas to Support Federal Clean Energy Goals Using Small Modular Reactors

    SciTech Connect

    Belles, Randy; Mays, Gary T; Omitaomu, Olufemi A; Poore III, Willis P

    2013-12-01

    This analysis identifies candidate locations, in a broad sense, where there are high concentrations of federal government agency use of electricity, which are also suitable areas for near-term SMRs. Near-term SMRs are based on light-water reactor (LWR) technology with compact design features that are expected to offer a host of safety, siting, construction, and economic benefits. These smaller plants are ideally suited for small electric grids and for locations that cannot support large reactors, thus providing utilities or governement entities with the flexibility to scale power production as demand changes by adding additional power by deploying more modules or reactors in phases. This research project is aimed at providing methodologies, information, and insights to assist the federal government in meeting federal clean energy goals.

  11. Availability Considerations in the Design of K-DEMO

    SciTech Connect

    Brown, Thomas; Im, Kim; Kessel, Charles; Kim, K.; Neilson, George H.; Park, J-S.; Titus, Peter

    2014-09-01

    A DEMO device has been considered the next step following ITER as a near-term prototypical reactor design that is tritium self-sufficient and produces a limited amount of net electricity. The machine maintenance approach and planned configuration concept plays a major role in establishing the design point. DEMO will also need to show that adequate operating availability can be achieved over a reasonable time period, as a last step before full-scale electricity production. The ability to operate with high availability/reliability plays a key ingredient in defining the DEMO configuration, fostering the need for rapid removal/replacement of limited-life in-vessel components. DEMO pre-conceptual studies are being carried out by South Korea (with US participation) and other countries. The device designs span a range of maintenance approaches from full radial extraction of large in-vessel modules through all TF horizontal openings to vertical maintenance of segmented in-vessel components. Progress made on the S. Korea's K-DEMO design will be provided with emphasis on the design choices identified to promote high availability.

  12. Fast wave current drive in DEMO

    SciTech Connect

    Lerche, E.; Van Eestera, D.; Messiaen, A.; Collaboration: EFDA-PPPT Contributors

    2014-02-12

    The ability to non-inductively drive a large fraction of the toroidal plasma current in magnetically confined plasmas is an essential requirement for steady state fusion reactors such as DEMO. Besides neutral beam injection (NBI), electron-cyclotron resonance heating (ECRH) and lower hybrid wave heating (LH), ion-cyclotron resonance heating (ICRH) is a promising candidate to drive current, in particular at the high temperatures expected in fusion plasmas. In this paper, the current drive (CD) efficiencies calculated with coupled ICRF wave / CD numerical codes for the DEMO-1 design case (R{sub 0}=9m, B{sub 0}=6.8T, a{sub p}=2.25m) [1] are presented. It will be shown that although promising CD efficiencies can be obtained in the usual ICRF frequency domain (20-100MHz) by shifting the dominant ion-cyclotron absorption layers to the high-field side, operation at higher frequencies (100-300MHz) has a stronger CD potential, provided the parasitic RF power absorption of the alpha particles can be minimized.

  13. A DEMO relevant fast wave current drive high harmonic antenna exploiting the high impedance technique

    NASA Astrophysics Data System (ADS)

    Milanesio, D.; Maggiora, R.

    2015-12-01

    Ion Cyclotron (IC) antennas are routinely adopted in most of the existing nuclear fusion experiments, even though their main goal, i.e. to couple high power to the plasma (MW), is often limited by rather severe drawbacks due to high fields on the antenna itself and on the unmatched part of the feeding lines. In addition to the well exploited auxiliary ion heating during the start-up phase, some non-ohmic current drive (CD) at the IC range of frequencies may be explored in view of the DEMO reactor. In this work, we suggest and describe a compact high frequency DEMO relevant antenna, based on the high impedance surfaces concept. High-impedance surfaces are periodic metallic structures (patches) usually displaced on top of a dielectric substrate and grounded by means of vertical posts embedded inside the dielectric, in a mushroom-like shape. These structures present a high impedance, within a given frequency band, such that the image currents are in-phase with the currents of the antenna itself, thus determining a significant efficiency increase. After a general introduction on the properties of high impedance surfaces, we analyze, by means of numerical codes, a dielectric based and a full metal solution optimized to be tested and benchmarked on the FTU experiment fed with generators at 433MHz.

  14. A DEMO relevant fast wave current drive high harmonic antenna exploiting the high impedance technique

    SciTech Connect

    Milanesio, D. Maggiora, R.

    2015-12-10

    Ion Cyclotron (IC) antennas are routinely adopted in most of the existing nuclear fusion experiments, even though their main goal, i.e. to couple high power to the plasma (MW), is often limited by rather severe drawbacks due to high fields on the antenna itself and on the unmatched part of the feeding lines. In addition to the well exploited auxiliary ion heating during the start-up phase, some non-ohmic current drive (CD) at the IC range of frequencies may be explored in view of the DEMO reactor. In this work, we suggest and describe a compact high frequency DEMO relevant antenna, based on the high impedance surfaces concept. High-impedance surfaces are periodic metallic structures (patches) usually displaced on top of a dielectric substrate and grounded by means of vertical posts embedded inside the dielectric, in a mushroom-like shape. These structures present a high impedance, within a given frequency band, such that the image currents are in-phase with the currents of the antenna itself, thus determining a significant efficiency increase. After a general introduction on the properties of high impedance surfaces, we analyze, by means of numerical codes, a dielectric based and a full metal solution optimized to be tested and benchmarked on the FTU experiment fed with generators at 433MHz.

  15. Terrain Perception for DEMO III

    NASA Technical Reports Server (NTRS)

    Manduchi, R.; Bellutta, P.; Matthies, L.; Owens, K.; Rankin, A.

    2000-01-01

    The Demo III program has as its primary focus the development of autonomous mobility for a small rugged cross country vehicle. In this paper we report recent progress on both stereo-based obstacle detection and terrain cover color-based classification.

  16. Two-minute impromptu demos

    NASA Astrophysics Data System (ADS)

    van den Berg, Ed; van den Berg, Rosea

    1998-09-01

    We present here a collection of small and quick demos that require no equipment beyond what is present in the lecture room (chalk, chairs, students, books, paper, backpacks and their contents). Some are to prove something, but most are to illustrate, visualize, or simulate.

  17. Reliability and availability requirements analysis for DEMO: fuel cycle system

    SciTech Connect

    Pinna, T.; Borgognoni, F.

    2015-03-15

    The Demonstration Power Plant (DEMO) will be a fusion reactor prototype designed to demonstrate the capability to produce electrical power in a commercially acceptable way. Two of the key elements of the engineering development of the DEMO reactor are the definitions of reliability and availability requirements (or targets). The availability target for a hypothesized Fuel Cycle has been analysed as a test case. The analysis has been done on the basis of the experience gained in operating existing tokamak fusion reactors and developing the ITER design. Plant Breakdown Structure (PBS) and Functional Breakdown Structure (FBS) related to the DEMO Fuel Cycle and correlations between PBS and FBS have been identified. At first, a set of availability targets has been allocated to the various systems on the basis of their operating, protection and safety functions. 75% and 85% of availability has been allocated to the operating functions of fuelling system and tritium plant respectively. 99% of availability has been allocated to the overall systems in executing their safety functions. The chances of the systems to achieve the allocated targets have then been investigated through a Failure Mode and Effect Analysis and Reliability Block Diagram analysis. The following results have been obtained: 1) the target of 75% for the operations of the fuelling system looks reasonable, while the target of 85% for the operations of the whole tritium plant should be reduced to 80%, even though all the tritium plant systems can individually reach quite high availability targets, over 90% - 95%; 2) all the DEMO Fuel Cycle systems can reach the target of 99% in accomplishing their safety functions. (authors)

  18. Thomson scattering for core plasma on DEMO

    SciTech Connect

    Mukhin, E. E.; Kurskiev, G. S.; Tolstyakov, S. Yu.; Bukreev, I. M.; Chernakov, P. V.; Kochergin, M. M.; Koval, A. N.; Litvinov, A. E.; Masyukevich, S. V.; Razdobarin, A. G.; Semenov, V. V.; Kukushkin, A. B.; Sdvizhenskii, P. A.; Andrew, P.

    2014-08-21

    This paper describes the challenges of Thomson scattering implementation for core plasma on DEMO and evaluates the capability to measure extremely high electron temperature range 0.5-40keV. A number of solutions to be developed for ITER diagnostics are suggested in consideration of their realization for DEMO. New approaches suggested for DEMO may also be of interest to ITER and currently operating magnetic confinement devices.

  19. Compact DEMO, SlimCS: design progress and issues

    NASA Astrophysics Data System (ADS)

    Tobita, K.; Nishio, S.; Enoeda, M.; Kawashima, H.; Kurita, G.; Tanigawa, H.; Nakamura, H.; Honda, M.; Saito, A.; Sato, S.; Hayashi, T.; Asakura, N.; Sakurai, S.; Nishitani, T.; Ozeki, T.; Ando, M.; Ezato, K.; Hamamatsu, K.; Hirose, T.; Hoshino, T.; Ide, S.; Inoue, T.; Isono, T.; Liu, C.; Kakudate, S.; Kawamura, Y.; Mori, S.; Nakamichi, M.; Nishi, H.; Nozawa, T.; Ochiai, K.; Ogiwara, H.; Oyama, N.; Sakamoto, K.; Sakamoto, Y.; Seki, Y.; Shibama, Y.; Shimizu, K.; Suzuki, S.; Takahashi, K.; Tanigawa, H.; Tsuru, D.; Yamanishi, T.; Yoshida, T.

    2009-07-01

    The design progress in a compact low aspect ratio (low A) DEMO reactor, 'SlimCS', and its design issues are reported. The design study focused mainly on the torus configuration including the blanket, divertor, materials and maintenance scheme. For continuity with the Japanese ITER-TBM, the blanket is based on a water-cooled solid breeder blanket. For vertical stability of the elongated plasma and high beta access, the blanket is segmented into replaceable and permanent blankets and a sector-wide conducting shell is arranged inbetween these blankets. A numerical calculation indicates that fuel self-sufficiency can be satisfied when the blanket interior is ideally fabricated. An allowable heat load to the divertor plate should be 8 MW m-2 or lower, which can be a critical constraint for determining a handling power of DEMO.

  20. Progress in the RAMI analysis of a conceptual LHCD system for DEMO

    SciTech Connect

    Mirizzi, F.

    2014-02-12

    Reliability, Availability, Maintainability and Inspectability (RAMI) concepts and techniques, that acquired great importance during the first manned space missions, have been progressively extended to industrial, scientific and consumer equipments to assure them satisfactory performances and lifetimes. In the design of experimental facilities, like tokamaks, mainly aimed at demonstrating validity and feasibility of scientific theories, RAMI analysis has been often left aside. DEMO, the future prototype fusion reactors, will be instead designed for steadily delivering electrical energy to commercial grids, so that the RAMI aspects will assume an absolute relevance since their initial design phases. A preliminary RAMI analysis of the LHCD system for the conceptual EU DEMO reactor is given in the paper.

  1. Progress in the RAMI analysis of a conceptual LHCD system for DEMO

    NASA Astrophysics Data System (ADS)

    Mirizzi, F.

    2014-02-01

    Reliability, Availability, Maintainability and Inspectability (RAMI) concepts and techniques, that acquired great importance during the first manned space missions, have been progressively extended to industrial, scientific and consumer equipments to assure them satisfactory performances and lifetimes. In the design of experimental facilities, like tokamaks, mainly aimed at demonstrating validity and feasibility of scientific theories, RAMI analysis has been often left aside. DEMO, the future prototype fusion reactors, will be instead designed for steadily delivering electrical energy to commercial grids, so that the RAMI aspects will assume an absolute relevance since their initial design phases. A preliminary RAMI analysis of the LHCD system for the conceptual EU DEMO reactor is given in the paper.

  2. Evaluation of Potential Locations for Siting Small Modular Reactors near Federal Energy Clusters to Support Federal Clean Energy Goals

    SciTech Connect

    Belles, Randy J.; Omitaomu, Olufemi A.

    2014-09-01

    Geographic information systems (GIS) technology was applied to analyze federal energy demand across the contiguous US. Several federal energy clusters were previously identified, including Hampton Roads, Virginia, which was subsequently studied in detail. This study provides an analysis of three additional diverse federal energy clusters. The analysis shows that there are potential sites in various federal energy clusters that could be evaluated further for placement of an integral pressurized-water reactor (iPWR) to support meeting federal clean energy goals.

  3. FWCD technology issues for DEMO

    NASA Astrophysics Data System (ADS)

    Nightingale, M.; Wooldridge, E.; Monakhov, I.

    2014-02-01

    The technology implications of potential FWCD systems have been assessed at two frequencies of relevance to DEMO as part of a wider study of heating and current drive systems for the EFDA Power Plant Physics and Technology (PPP&T), based upon two reference DEMO designs. Using the results of Van Eester et al [1], systems studies carried out for a 62MHz mid-harmonic system mounted on a 23MA 5.74T 8.5m major radius DEMO suggested that antenna voltages close to 50kV, and the handling of the resultant sheath power loadings, are likely to be required if all of the 12.9MA non-bootstrap current drive is to be provided by FWCD. The "wall plug" electrical efficiency of the midharmonic option of 0.18A/W.m2, potentially rising to 0.23A/W.m2 with the future development of solid state generators, however, looks very attractive, and the coupling is less sensitive to plasma edge parameters than for existing antennas, due to the low k// of 2.8m-1. The design could be based upon that presently under consideration for ITER, except for the replacement of insulating vacuum windows located relatively close to the plasma with all-metal designs [2]. A 352MHz high-harmonic option also looks technologically feasible, using a waveguide-based design and a port plug layout has been provided. This option might bring sheath effect and voltage hold-off benefits, but this is far from proven. In this case, systems studies were not feasible due to a lack of firm results from the physics studies. For both options: (a) the RF generators, power supplies and transmission line components required are either already available, or are under development for ITER, and (b) mechanical and material issues associated with the proposed FWCD antenna structures appear challenging, but will need solving on a wider basis across DEMO.

  4. Diagnostics and control for the steady state and pulsed tokamak DEMO

    NASA Astrophysics Data System (ADS)

    Orsitto, F. P.; Villari, R.; Moro, F.; Todd, T. N.; Lilley, S.; Jenkins, I.; Felton, R.; Biel, W.; Silva, A.; Scholz, M.; Rzadkiewicz, J.; Duran, I.; Tardocchi, M.; Gorini, G.; Morlock, C.; Federici, G.; Litnovsky, A.

    2016-02-01

    The present paper is devoted to a first assessment of the DEMO diagnostics systems and controls in the context of pulsed and steady state reactor design under study in Europe. In particular, the main arguments treated are: (i) The quantities to be measured in DEMO and the requirements for the measurements; (ii) the present capability of the diagnostic and control technology, determining the most urgent gaps, and (iii) the program and strategy of the research and development (R&D) needed to fill the gaps. Burn control, magnetohydrodynamic stability, and basic machine protection require improvements to the ITER technology, and moderated efforts in R&D can be dedicated to infrared diagnostics (reflectometry, electron cyclotron emission, polarimetry) and neutron diagnostics. Metallic Hall sensors appear to be a promising candidate for magnetic measurements in the high neutron fluence and long/steady state discharges of DEMO.

  5. Design concept of K-DEMO for near-term implementation

    DOE PAGESBeta

    Kim, K.; Im, K.; Kim, H. C.; Oh, S.; Park, J. S.; Kwon, S.; Lee, Y. S.; Yeom, J. H.; Lee, C.; Lee, G -S.; et al

    2015-04-22

    A Korean fusion energy development promotion law (FEDPL) was enacted in 2007. As a following step, a conceptual design study for a steady-state Korean fusion demonstration reactor (K-DEMO) was initiated in 2012. After the thorough 0D system analysis, the parameters of the main machine characterized by the major and minor radii of 6.8 and 2.1 m, respectively, were chosen for further study. The analyses of heating and current drives were performed for the development of the plasma operation scenarios. Preliminary results on lower hybrid and neutral beam current drive are included herein. A high performance Nb₃Sn-based superconducting conductor is adopted,more » providing a peak magnetic field approaching 16 T with the magnetic field at the plasma centre above 7 T. Pressurized water is the prominent choice for the main coolant of K-DEMO when the balance of plant development details is considered. The blanket system adopts a ceramic pebble type breeder. Considering plasma performance, a double-null divertor is the reference configuration choice of K-DEMO. For a high availability operation, K-DEMO incorporates a design with vertical maintenance. A design concept for K-DEMO is presented together with the preliminary design parameters.« less

  6. Design concept of K-DEMO for near-term implementation

    SciTech Connect

    Kim, K.; Im, K.; Kim, H. C.; Oh, S.; Park, J. S.; Kwon, S.; Lee, Y. S.; Yeom, J. H.; Lee, C.; Lee, G -S.; Neilson, G.; Kessel, C.; Brown, T.; Titus, P.; Mikkelsen, D.; Zhai, Y.

    2015-04-22

    A Korean fusion energy development promotion law (FEDPL) was enacted in 2007. As a following step, a conceptual design study for a steady-state Korean fusion demonstration reactor (K-DEMO) was initiated in 2012. After the thorough 0D system analysis, the parameters of the main machine characterized by the major and minor radii of 6.8 and 2.1 m, respectively, were chosen for further study. The analyses of heating and current drives were performed for the development of the plasma operation scenarios. Preliminary results on lower hybrid and neutral beam current drive are included herein. A high performance Nb₃Sn-based superconducting conductor is adopted, providing a peak magnetic field approaching 16 T with the magnetic field at the plasma centre above 7 T. Pressurized water is the prominent choice for the main coolant of K-DEMO when the balance of plant development details is considered. The blanket system adopts a ceramic pebble type breeder. Considering plasma performance, a double-null divertor is the reference configuration choice of K-DEMO. For a high availability operation, K-DEMO incorporates a design with vertical maintenance. A design concept for K-DEMO is presented together with the preliminary design parameters.

  7. Design concept of K-DEMO for near-term implementation

    NASA Astrophysics Data System (ADS)

    Kim, K.; Im, K.; Kim, H. C.; Oh, S.; Park, J. S.; Kwon, S.; Lee, Y. S.; Yeom, J. H.; Lee, C.; Lee, G.-S.; Neilson, G.; Kessel, C.; Brown, T.; Titus, P.; Mikkelsen, D.; Zhai, Y.

    2015-05-01

    A Korean fusion energy development promotion law (FEDPL) was enacted in 2007. As a following step, a conceptual design study for a steady-state Korean fusion demonstration reactor (K-DEMO) was initiated in 2012. After the thorough 0D system analysis, the parameters of the main machine characterized by the major and minor radii of 6.8 and 2.1 m, respectively, were chosen for further study. The analyses of heating and current drives were performed for the development of the plasma operation scenarios. Preliminary results on lower hybrid and neutral beam current drive are included herein. A high performance Nb3Sn-based superconducting conductor is adopted, providing a peak magnetic field approaching 16 T with the magnetic field at the plasma centre above 7 T. Pressurized water is the prominent choice for the main coolant of K-DEMO when the balance of plant development details is considered. The blanket system adopts a ceramic pebble type breeder. Considering plasma performance, a double-null divertor is the reference configuration choice of K-DEMO. For a high availability operation, K-DEMO incorporates a design with vertical maintenance. A design concept for K-DEMO is presented together with the preliminary design parameters.

  8. Versatile Desktop Experiment Module (DEMo) on Heat Transfer

    ERIC Educational Resources Information Center

    Minerick, Adrienne R.

    2010-01-01

    This paper outlines a new Desktop Experiment Module (DEMo) engineered for a chemical engineering junior-level Heat Transfer course. This new DEMo learning tool is versatile, fairly inexpensive, and portable such that it can be positioned on student desks throughout a classroom. The DEMo system can illustrate conduction of various materials,…

  9. Development of an object-oriented dynamics simulator for a LFR DEMO

    SciTech Connect

    Ponciroli, R.; Bortot, S.; Lorenzi, S.; Cammi, A.

    2012-07-01

    A control-oriented dynamics simulator for a Generation IV Lead-cooled Fast Reactor (LFR) demonstrator (DEMO) has been developed aimed at providing a flexible, simple and fast-running tool allowing to perform design-basis transient and stability analyses, and to lay the foundations for the study of the system control strategy. For such purposes, a model representing a compromise between accuracy and straightforwardness has been necessarily sought, and in this view an object-oriented approach based on the Modelica language has been adopted. The reactor primary and secondary systems have been implemented by assembling both component models already available in a specific thermal-hydraulic library, and ad hoc developed nuclear component models suitably modified according to the specific DEMO configuration. The resulting overall plant simulator, incorporating also the balance of plant, consists in the following essential parts: core, integrated steam generator/primary pump block, cold and hot legs, primary coolant cold pool, turbine, heat sink, secondary coolant pump. Afterwards, the reactor response to typical transient initiators has been investigated: feedwater mass flow rate and temperature enhancement, turbine admission valve coefficient variation, increase of primary coolant mass flow rate, and transient of overpower have been simulated; results have been compared with the outcomes of analogous analyses performed by employing a lumped-parameter DEMO plant model. (authors)

  10. Innovative tokamak DEMO first wall and divertor material concepts

    NASA Astrophysics Data System (ADS)

    Wong, C. P. C.

    2009-06-01

    ITER has selected Be as the first wall and C and W as the divertor surface materials. When extrapolated to the DEMO design, C and Be layers will not be suitable due to radiation damage. The remaining material, W, could also suffer radiation damage from helium ion implantation and experience blistering at the first wall and form submicron fine structure at the divertor. In this paper we introduce a new concept called the boron W-mesh (BW-mesh) in which B is infiltrated into a W-mesh. The goal is to use a thin coating of B to protect the W-mesh from helium ion damage and to maintain a sufficient amount of B to protect the W from transient events like edge localized modes (ELMs) and disruptions. Critical issues and corresponding development of this BW-mesh concept have been identified, including the need for real time boronization.

  11. ADS-Demo Fuel Rod Performance: Multivariate Statistical Analysis

    SciTech Connect

    Calabrese, R.; Vettraino, F.; Luzzi, L.

    2004-07-01

    A forward step in the development of Accelerator Driven System (ADS) for the Pu, MA and LLFP transmutation, is the realisation of a 80 MWt ADS-demo (XADS) whose basic objective is the system feasibility demonstration. The XADS is forecasted to adopt the UO{sub 2}-PuO{sub 2} mixed-oxides fuel already experimented in the sodium cooled fast reactors such as the french SPX-1. The present multivariate statistical analysis performed by using the Transuranus Code, was carried out for the Normal Operation at the so-called Enhanced Nominal Conditions (120% nominal reactor power), aimed at verifying that the fuel system complies with the stated design limits, i.e. centerline fuel temperature, cladding temperature and damage, during all the in-reactor lifetime. A statistical input set similar to SPX and PEC fuel case, was adopted. One most relevant assumption in the present calculations was a 30% AISI-316 cladding thickness corrosion at EOL. Relative influence of main fuel rod parameters on fuel centerline temperature was also evaluated. (authors)

  12. Throttling Characteristics of the RL10 Derivative Common Extensible Cryogenic Engine -- Demo 1.6 and 1.7 Test Results

    NASA Technical Reports Server (NTRS)

    Devine, Matthew K.; Hulka, James; Adamski, Walt; Brown, Corey

    2010-01-01

    The Common Extensible Cryogenic Engine (CECE) is a deep throttling cryogenic Lunar Module Descent Engine (LMDE) technology development demonstrator based on the Pratt & Whitney Rocketdyne (PWR) RL10 engine. Previous testing on this engine occurred during 2006 as Demo 1.0, then Demo 1.5 in 2007, Demo 1.6 in 2008 and finally Demo 1.7 in 2010. A review of Demo 1.0, 1.5, and preliminary results of 1.6 were reported in previous JANNAF papers. Demo 1.6 was tested at the PWR E-6 test facility in November 2008. The primary goal of this series was to mitigate low frequency combustion instability observed at low power levels. To mitigate the chug, the Demo 1.6 injector was modified from the previous configurations to include an approximately 0.050 inch thick teflon-type spray-on insulation to reduce heat transfer to the LOX manifold, which was believed to be a significant contributor to the low power instability. In addition, gaseous helium injection into the LOX manifold was used as a means to stabilize the system. Also explored in this test series was mitigation for a low power 1 Hz fuel system oscillation caused by sub-critical hydrogen boiling in the chamber cooling jacket. Reduced area gas venturis were utilized to avoid the 1 Hz fuel-size oscillation by keeping the cooling jacket supercritical down to lower engine power levels. Demo 1.7 began testing in March 2010. Its primary objectives were to demonstrate closed loop control capability on mixture ratio and chamber pressure, start to lower power levels and increased throttling ramp rates. Secondary test objectives that are discussed include multiple engine starts, higher mixture ratio excursions and additional time at low power level. While the complete test series and data reduction is not yet complete for Demo 1.7, an overview and up-to-date status is provided.

  13. Fuelling and density control for DEMO

    NASA Astrophysics Data System (ADS)

    Vincenzi, P.; Koechl, F.; Garzotti, L.; King, D. B.; Tindale, E.; Bolzonella, T.; Lang, P. T.; Pegourié, B.; Romanelli, M.; Wenninger, R.

    2015-09-01

    Plasma fuelling and density control are an open issue regarding EU DEMO studies and solutions may be different from present day experiments. The present paper addresses through JINTRAC core transport code simulations the feasibility of different fuelling methods such as gas puff and pellet injection and the influence of neoclassical and anomalous inward pinch in the edge transport barrier in order to achieve and control the target DEMO density. Given the expected high fusion power production, He accumulation in the plasma core is a critical issue, and an estimation of the influence of impurities (He, Ar, and W) on core fuelling and plasma dilution is given together with a discussion on D-T core balance. The DEMO reference scenario investigated in this work is characterized by a peaked density profile, which requires a careful core fuelling. Due to the large pedestal temperature gradient, gas puff may not be a feasible option for core density control, unless assuming a large anomalous inward pinch in the edge transport barrier of more than ~2 m s-1. Pellet injection from the high field side of the torus, on the contrary, may represent a viable solution for core fuelling and D-T ratio control. The effect of pellet mass, speed, and injection geometry is also discussed in the present paper. Regardless, core fuelling efficiency with pellet injection is almost entirely determined by the presence of E  ×  B drift.

  14. Neutronics experiments for DEMO blanket at JAERI/FNS

    NASA Astrophysics Data System (ADS)

    Sato, S.; Ochiai, K.; Hori, J.; Verzilov, Y.; Klix, A.; Wada, M.; Terada, Y.; Yamauchi, M.; Morimoto, Y.; Nishitani, T.

    2003-07-01

    In order to verify the accuracy of the tritium production rate (TPR), neutron irradiation experiments have been performed with a mockup relevant to the fusion DEMO blanket consisting of F82H blocks, Li2TiO3 blocks with a 6Li enrichment of 40% and 95%, and beryllium blocks. Sample pellets of Li2TiO3 were irradiated and the TPR was measured by a liquid scintillation counter. The TPR was also calculated using the Monte Carlo code MCNP-4B with the nuclear data library JENDL-3.2 and ENDF-B/VI. The results agreed with experimental values within the statistical error (10%) of the experiment. Accordingly, it was clarified that the TPR could be evaluated within 10% uncertainty by the calculation code and the nuclear data. In order to estimate the induced activity caused by sequential reactions in cooling water pipes in the DEMO blanket, neutron irradiation experiments have been performed using test specimens simulating the pipes. Sample metals of Fe, W, Ti, Pb, Cu, V and reduced activation ferritic steel F82H were irradiated as typical fusion materials. The effective cross-sections needed to calculate the formation of the radioactive nuclei (56Co, 184Re, 48V, 206Bi, 65Zn and 51Cr) due to sequential reactions were measured. From the experimental results, it was found that the effective cross-sections increased remarkably while coming closer to polyethylene board, which was a substitute for water. As a result of this present study, it has become clear that the sequential reaction rates are important factors in the accurate evaluation of induced activity in fusion reactor design.

  15. Thermohydraulic responses of a water-cooled tokamak fusion DEMO to loss-of-coolant accidents

    NASA Astrophysics Data System (ADS)

    Nakamura, M.; Tobita, K.; Someya, Y.; Utoh, H.; Sakamoto, Y.; Gulden, W.

    2015-11-01

    Major in- and ex-vessel loss-of-coolant accidents (LOCAs) of a water-cooled tokamak fusion DEMO reactor have been analysed. Analyses have identified responses of the DEMO systems to these accidents and pressure loads to confinement barriers for radioactive materials. As for the in-VV LOCA, we analysed the multiple double-ended break of the first wall cooling pipes around the outboard toroidal circumference. As for the ex-VV LOCA, we analysed the double-ended break of the primary cooling pipe. The thermohydraulic analysis results suggest that the in- and ex-vessel LOCAs crucially threaten integrity of the primary and final confinement barriers, respectively. Mitigations of the loads to the confinement barriers are also discussed.

  16. Diagnostics for machine protection of DEMO

    SciTech Connect

    Felton, R.

    2014-08-21

    DEMO aims to (i) integrate, demonstrate and validate all relevant technology necessary to convert fusion energy to electrical energy and (ii) that the machine and its operations are economically and environmentally acceptable. To maintain the efficiency and availability of the machine, there are several physics and combined physics/technology issues as well as the engineering issues. Machine Protection (also known as Protection of Investment) addresses both the risks to plant (to avoid costly repair or replacement) and the risks to normal operating time (to avoid loss of productivity and the return on investment). The plasma-related Machine Protection issues involve measurement and control of plasma stability, plasma purity, and plasma-wall interactions. Machine Protection aims to avoid hitting catastrophic limits by using early warning alarm systems, and controlled termination or avoidance, involving coordinated actions of the magnets, gas and auxiliary heating or current-drive systems. This article outlines the key processes, some of which are used in present-day tokamaks and some of which are new specifically for DEMO (e.g. First wall and divertor power handling) and reveals the need to research and develop new science and technology for Machine Protections in DEMO's high radiation and thermal fields. This work was funded by the RCUK Energy Programme under grant EP/I501045 and the European Communities under the contract of Association between EURATOM and CCFE and conducted partly under EFDA PPPT (WP13-DAS04). The views and opinions expressed herein do not necessarily reflect those of the European Commission.

  17. Diagnostics for machine protection of DEMO

    NASA Astrophysics Data System (ADS)

    Felton, R.

    2014-08-01

    DEMO aims to (i) integrate, demonstrate and validate all relevant technology necessary to convert fusion energy to electrical energy and (ii) that the machine and its operations are economically and environmentally acceptable. To maintain the efficiency and availability of the machine, there are several physics and combined physics/technology issues as well as the engineering issues. Machine Protection (also known as Protection of Investment) addresses both the risks to plant (to avoid costly repair or replacement) and the risks to normal operating time (to avoid loss of productivity and the return on investment). The plasma-related Machine Protection issues involve measurement and control of plasma stability, plasma purity, and plasma-wall interactions. Machine Protection aims to avoid hitting catastrophic limits by using early warning alarm systems, and controlled termination or avoidance, involving coordinated actions of the magnets, gas and auxiliary heating or current-drive systems. This article outlines the key processes, some of which are used in present-day tokamaks and some of which are new specifically for DEMO (e.g. First wall and divertor power handling) and reveals the need to research and develop new science and technology for Machine Protections in DEMO's high radiation and thermal fields. This work was funded by the RCUK Energy Programme under grant EP/I501045 and the European Communities under the contract of Association between EURATOM and CCFE and conducted partly under EFDA PPPT (WP13-DAS04). The views and opinions expressed herein do not necessarily reflect those of the European Commission.

  18. Assessment of the LH wave for demo in pulsed and steady state scenario

    SciTech Connect

    Cardinali, A.; Barbato, E.; Castaldo, C.; Cesario, R.; Marinucci, M.; Ravera, G. L.; Tuccillo, A. A.; Ceccuzzi, S.; Mirizzi, F.; Panaccione, L.; Santini, F.; Schettini, G.

    2014-02-12

    The Lower Hybrid Current Drive (LHCD) has been analysed in DEMO tokamak plasma in the 'pulsed and steady state regime' considering two plasma scenarios characterized, respectively, by flat density profile and peaked density profiles. We have obtained LH deposition profiles in cases of neglecting the effect of spectral broadening produced by PI at the edge. By comparing the Power Deposition Profiles for both DEMO scenarios ('flat' and 'peaked'), the SOL of DEMO does not play any role in the absorption of the LH wave. In all cases the deposition is localized inside the separatrix layer r/a≤1. By lowering the parallel wave-number peak of the power spectrum from 1.8 to 1.5, the accessibility condition in both case prevents the power from reaching the deposition layer apart from a small fraction which pertains to the higher n∥ of the power spectrum. The spectrum centred at 1.8 is suggested to be useful in DEMO. More realistically, as supported by available data of LHCD in a wide range of operating densities, the effect of parametric decay instability (PDI) can produce a spectral broadening which should be included in the simulations. Further studies would be necessary for assessing the temperature profiles in the SOL at reactor-graded conditions. This is because, if the SOL temperature is at least of the order of 50 to 100 eV, the effect of PDI broads the spectrum up to n∥≤10, and the deposition profile is slightly wider but not much shifted outwards.

  19. Driver options and burn-cycle selection based on power-reactor considerations

    SciTech Connect

    Ehst, D.A.

    1983-04-01

    Reactor implications for noninductive current drive are presented based on a number of studies. First, the lower hybrid driver for the STARFIRE reactor is discussed and the disadvantages of this driver are reviewed. Next, the results of an extensive search for a better current driver are presented. A large number of alternatives were compared in a common context, the DEMO reactor, in order to examine their suitability on a standard basis. Finally, the methodology of a study, currently in progress, is described. The goals of this last study are to compare tokamak reactor designs optimized for operation under different burn cycles, in order to assess the actual benefits and costs of pulsed versus steady-state operation.

  20. ISS Update: The Role of OSO in Dragon's Demo Mission

    NASA Video Gallery

    NASA Public Affairs Office commentator Pat Ryan talks with Brandon Moncla, Lead Operations Support Officer (OSO) for the SpaceX Dragon Demo Mission, about preparations for the Dragon berthing and h...

  1. Progress in Developing the K-DEMO Device Configuration

    SciTech Connect

    Brown, Tom

    2013-06-27

    K-DEMO is being studied by South Korean researchers as a follow-on to ITER and the next step toward the construction of a commercial fusion power plant. The K-DEMO mission defines a staged approach targeting operation with an initial testing phase for plasma facing components and critical operating systems to be followed by a second phase which centers on upgrading the in-vessel components for operation at 200 to 600 MWe with a planned 70% availability.

  2. International Perspectives on a Path to MFE DEMO

    SciTech Connect

    Neilson, George H.; Abdou, M.; Federici, Gianfranco; Garofalo, A. M.; Kamendje, R.; Kaw, Predhiman K.; Kim, Keeman; Kurtz, Richard J.; Kuteev, Boris V.; Ward, David; Yamada, Hiroshi; Zohm, Hartmut

    2013-01-07

    The establishment of the ITER project marks a transition in the world fusion program to one increasingly focused on the demonstration of electricity generation from fusion, or DEMO. In recent years, planning and design activities for next steps toward DEMO have intensified in many countries, and international discussions have identified both needs and opportunities for greater international collaboration in developing a DEMO Programme. The scientific and technical issues for fusion are well known and, while there is no agreement on a single roadmap to fusion, there is substantial scope to add value through international cooperation, particularly in promoting a coordinated DEMO programme. The International Atomic Energy Agency, as a world organization dedicated to fostering international collaboration in the development of nuclear energy for peaceful purposes, is well suited to provide auspices for an activity promoting an international exchange of technical information and strategic thinking that would benefit all parties. Accordingly, an IAEA DEMO Programme Workshop series focus on the scientific and technical issues for fusion development toward DEMO has been established. The first workshop will be held 15-18 October 2012 in the U.S.A.

  3. Quasi-linear modeling of lower hybrid current drive in ITER and DEMO

    NASA Astrophysics Data System (ADS)

    Cardinali, A.; Cesario, R.; Panaccione, L.; Santini, F.; Amicucci, L.; Castaldo, C.; Ceccuzzi, S.; Mirizzi, F.; Tuccillo, A. A.

    2015-12-01

    First pass absorption of the Lower Hybrid waves in thermonuclear devices like ITER and DEMO is modeled by coupling the ray tracing equations with the quasi-linear evolution of the electron distribution function in 2D velocity space. As usually assumed, the Lower Hybrid Current Drive is not effective in a plasma of a tokamak fusion reactor, owing to the accessibility condition which, depending on the density, restricts the parallel wavenumber to values greater than n∥crit and, at the same time, to the high electron temperature that would enhance the wave absorption and then restricts the RF power deposition to the very periphery of the plasma column (near the separatrix). In this work, by extensively using the "raystar" code, a parametric study of the propagation and absorption of the LH wave as function of the coupled wave spectrum (as its width, and peak value), has been performed very accurately. Such a careful investigation aims at controlling the power deposition layer possibly in the external half radius of the plasma, thus providing a valuable aid to the solution of how to control the plasma current profile in a toroidal magnetic configuration, and how to help the suppression of MHD mode that can develop in the outer part of the plasma. This analysis is useful not only for exploring the possibility of profile control of a pulsed operation reactor as well as the tearing mode stabilization, but also in order to reconsider the feasibility of steady state regime for DEMO.

  4. Design of a W/steel functionally graded material for plasma facing components of DEMO

    NASA Astrophysics Data System (ADS)

    Missiaen, J. M.; Raharijaona, J. J.; Antoni, A.; Pascal, C.; Richou, M.; Magaud, P.

    2011-09-01

    The design of a graded transition between tungsten and steel for plasma facing components of a nuclear fusion reactor is proposed and the interest of such a transition is demonstrated by FEM calculations of the thermo-mechanical behaviour in the operating conditions of the DEMO reactor. The transition consists in stacked layers of W-WC and WC-Fe between W and Eurofer steel. The maximum surface temperature of the structural component could be maintained below 1300 °C for a very simple multilayer geometry, from FEM calculations. The maximum strains and equivalent elastic stresses could be reduced by a factor of about 3 as compared to a direct W/steel joint. Considerations about processing techniques of such a component are discussed, based on the literature background and a few preliminary tests.

  5. MOTIVATION: Goals and Goal Setting

    ERIC Educational Resources Information Center

    Stratton, Richard K.

    2005-01-01

    Goal setting has great impact on a team's performance. Goals enable a team to synchronize their efforts to achieve success. In this article, the author talks about goals and goal setting. This articles complements Domain 5--Teaching and Communication (p.14) and discusses one of the benchmarks listed therein: "Teach the goal setting process and…

  6. DEMOS: state-of-the-art application software for design, evaluation, and modeling of optical systems

    NASA Astrophysics Data System (ADS)

    Gan, Michael A.; Zhdanov, Dmitriy D.; Novoselskiy, Vadim V.; Ustinov, Sergey I.; Fedorov, Alexander O.; Potyemin, Igor S.

    1992-04-01

    A new version of the DEMOS program is presented. DEMOS (design, evaluation, and modeling of optical systems) is integrated dialog software for automatic modeling to estimate and design optical systems with conventional and hologram optical elements. The theoretical principles and the current state of the primary possibilities and application principles of the DEMOS program for optical systems design and simulation on computers are discussed.

  7. RF H and CD systems for DEMO - Challenges and opportunities

    SciTech Connect

    Franke, T.; Wenninger, R.; Barbato, E.; Cardinali, A.; Cesario, R.; Mirizzi, F.; Tuccillo, A. A.; Ceccuzzi, S.; Eester, D. V.; Lerche, E.

    2014-02-12

    The aim of driving a sufficient amount of plasma current with an appropriate radial current density profile is considered as one of the key challenges for a tokamak fusion power plant in steady state operation. Furthermore, efficient heating to enable transition to regime of enhanced confinement and to achieve breakeven plasma temperatures as well as MHD control and plasma breakdown assistance are required. In the framework of the EFDA Power Plant Physics and Technology (PPPT) activities, the ability of the Electron cyclotron (EC), Ion Cyclotron (IC) and Lower Hybrid (LH) systems to fulfil these requirements, was studied for a demonstration fusion power plant (DEMO). As boundary condition, a 1D description of the plasma for a pulsed DEMO based on system code studies combined with transport analysis was developed. The predicted 1D plasma parameters were used to calculate the current drive (CD) efficiency of each system and eventually optimised it. As an example, the EC current drive efficiency could be increased strongly by top launch compared to equatorial launch at least by a factor of two. For the IC system, two possible windows of operation for standard and higher frequencies were highlighted, whereby again top launch leads to higher CD-efficiencies. The efficiencies predicted for DEMO for the RF current drive systems will be presented. Finally, gaps in the feasibility of RF systems under DEMO relevant conditions will be identified.

  8. Quasi-linear modeling of lower hybrid current drive in ITER and DEMO

    SciTech Connect

    Cardinali, A. Cesario, R.; Panaccione, L.; Santini, F.; Amicucci, L.; Castaldo, C.; Ceccuzzi, S.; Mirizzi, F.; Tuccillo, A. A.

    2015-12-10

    First pass absorption of the Lower Hybrid waves in thermonuclear devices like ITER and DEMO is modeled by coupling the ray tracing equations with the quasi-linear evolution of the electron distribution function in 2D velocity space. As usually assumed, the Lower Hybrid Current Drive is not effective in a plasma of a tokamak fusion reactor, owing to the accessibility condition which, depending on the density, restricts the parallel wavenumber to values greater than n{sub ∥crit} and, at the same time, to the high electron temperature that would enhance the wave absorption and then restricts the RF power deposition to the very periphery of the plasma column (near the separatrix). In this work, by extensively using the “ray{sup star}” code, a parametric study of the propagation and absorption of the LH wave as function of the coupled wave spectrum (as its width, and peak value), has been performed very accurately. Such a careful investigation aims at controlling the power deposition layer possibly in the external half radius of the plasma, thus providing a valuable aid to the solution of how to control the plasma current profile in a toroidal magnetic configuration, and how to help the suppression of MHD mode that can develop in the outer part of the plasma. This analysis is useful not only for exploring the possibility of profile control of a pulsed operation reactor as well as the tearing mode stabilization, but also in order to reconsider the feasibility of steady state regime for DEMO.

  9. Massively Clustered CubeSats NCPS Demo Mission

    NASA Technical Reports Server (NTRS)

    Robertson, Glen A.; Young, David; Kim, Tony; Houts, Mike

    2013-01-01

    Technologies under development for the proposed Nuclear Cryogenic Propulsion Stage (NCPS) will require an un-crewed demonstration mission before they can be flight qualified over distances and time frames representative of a crewed Mars mission. In this paper, we describe a Massively Clustered CubeSats platform, possibly comprising hundreds of CubeSats, as the main payload of the NCPS demo mission. This platform would enable a mechanism for cost savings for the demo mission through shared support between NASA and other government agencies as well as leveraged commercial aerospace and academic community involvement. We believe a Massively Clustered CubeSats platform should be an obvious first choice for the NCPS demo mission when one considers that cost and risk of the payload can be spread across many CubeSat customers and that the NCPS demo mission can capitalize on using CubeSats developed by others for its own instrumentation needs. Moreover, a demo mission of the NCPS offers an unprecedented opportunity to invigorate the public on a global scale through direct individual participation coordinated through a web-based collaboration engine. The platform we describe would be capable of delivering CubeSats at various locations along a trajectory toward the primary mission destination, in this case Mars, permitting a variety of potential CubeSat-specific missions. Cameras on various CubeSats can also be used to provide multiple views of the space environment and the NCPS vehicle for video monitoring as well as allow the public to "ride along" as virtual passengers on the mission. This collaborative approach could even initiate a brand new Science, Technology, Engineering and Math (STEM) program for launching student developed CubeSat payloads beyond Low Earth Orbit (LEO) on future deep space technology qualification missions. Keywords: Nuclear Propulsion, NCPS, SLS, Mars, CubeSat.

  10. REACTOR

    DOEpatents

    Szilard, L.

    1963-09-10

    A breeder reactor is described, including a mass of fissionable material that is less than critical with respect to unmoderated neutrons and greater than critical with respect to neutrons of average energies substantially greater than thermal, a coolant selected from sodium or sodium--potassium alloys, a control liquid selected from lead or lead--bismuth alloys, and means for varying the quantity of control liquid in the reactor. (AEC)

  11. REACTOR

    DOEpatents

    Christy, R.F.

    1961-07-25

    A means is described for co-relating the essential physical requirements of a fission chain reaction in order that practical, compact, and easily controllable reactors can be built. These objects are obtained by employing a composition of fissionsble isotope and moderator in fluid form in which the amount of fissionsble isotcpe present governs the reaction. The size of the reactor is no longer a critical factor, the new criterion being the concentration of the fissionable isotope.

  12. REACTOR

    DOEpatents

    Roman, W.G.

    1961-06-27

    A pressurized water reactor in which automatic control is achieved by varying the average density of the liquid moderator-cooiant is patented. Density is controlled by the temperature and power level of the reactor ftself. This control can be effected by the use of either plate, pellet, or tubular fuel elements. The fuel elements are disposed between upper and lower coolant plenum chambers and are designed to permit unrestricted coolant flow. The control chamber has an inlet opening communicating with the lower coolant plenum chamber and a restricted vapor vent communicating with the upper coolant plenum chamber. Thus, a variation in temperature of the fuel elements will cause a variation in the average moderator density in the chamber which directly affects the power level of the reactor.

  13. REACTORS

    DOEpatents

    Spitzer, L. Jr.

    1961-10-01

    Thermonuclear reactors, methods, and apparatus are described for controlling and confining high temperature plasma. Main axial confining coils in combination with helical windings provide a rotational transform that avoids the necessity of a figure-eight shaped reactor tube. The helical windings provide a multipolar helical magnetic field transverse to the axis of the main axial confining coils so as to improve the effectiveness of the confining field by counteracting the tendency of the more central lines of force in the stellarator tube to exchange positions with the magnetic lines of force nearer the walls of the tube. (AEC)

  14. Simulations of fast-wave current drive in pulsed and steady-state DEMO designs

    NASA Astrophysics Data System (ADS)

    Bilato, R.; Brambilla, M.; Fable, E.

    2014-11-01

    Electromagnetic waves in the ion-cyclotron (IC) range of frequencies are presently investigated as possible current drive (CD) systems in fusion reactors. Among many physical and technical issues, an accurate description of radio-frequency (RF) power absorption by fusion- born alpha particles is of special importance, since RF heating of these particles is not only detrimental for the CD efficiency, but might worsen the operative conditions by increasing their prompt losses. The capability of the full-wave TORIC code has been recently augmented to account for RF absorption by fusion-born alpha particles, calculated to all-orders in finite Larmor radius and with a realistic distribution function. Here, we present simulation with TORIC addressing the sensitivity of current drive efficiency on the design of a future reactor, in particular density and temperature profiles, magnetic field intensity, and plasma dimensions. For this purpose, we have investigated possible frequency windows for CD for two proposed versions of the DEMO reactor, namely its pulsed and its more ambitious steady-state design. The important role of the antenna for a realistic estimate of the CD efficiency is pointed out.

  15. Cost goals

    NASA Technical Reports Server (NTRS)

    Hoag, J.

    1981-01-01

    Cost goal activities for the point focusing parabolic dish program are reported. Cost goals involve three tasks: (1) determination of the value of the dish systems to potential users; (2) the cost targets of the dish system are set out; (3) the value side and cost side are integrated to provide information concerning the potential size of the market for parabolic dishes. The latter two activities are emphasized.

  16. Demo III: reconnaissance, surveilance, and target acquisition (RSTA) preliminary design

    NASA Astrophysics Data System (ADS)

    Klarquist, William N.; Bonner, Kevin G.; Gothard, Benny M.

    1999-01-01

    One of the principal roles of the Demo III Experimental Unmanned Ground Vehicle will be as a forward scout performing Reconnaissance, Surveillance, and Target Acquisition (RSTA) operations. This paper will present the elements of the preliminary design process for satisfying the rigorous Demo III ATR requirements, including military vehicle deductibility at a maximum range of 6 km and dismounted soldier detection at 2km. The constituent design issues include sensor selection, sensor suite mounting and stabilization, processing architecture, and algorithm selection. In the context of this selection and design process the lessons learned from previous Unmanned Ground Vehicle RSTA efforts will be introduced and the contractual and subsystem derived requirements will be presented as well as the interface issues for the RSTA subsystem in conjunction with the navigation, mission execution, and communication subsystems.

  17. Evolving targets for DEMO: Implications for materials development

    NASA Astrophysics Data System (ADS)

    Cook, Ian; Maisonnier, David; Ward, David

    2009-04-01

    Current reference fusion development scenarios assume the sequential achievement of key milestones. Firstly, the qualification of the plasma physics basis in ITER, together with the qualification of materials for in-vessel components in IFMIF. Secondly, the qualification of components and processes in DEMO. However, the circumstances, within which fusion development planning is undertaken, are changing, and it is becoming reasonable to plan on the assumption that within 20 years ITER and IFMIF will have been successful and the world will be eager for clean, secure energy supplies. This motivates supplementing the reference scenario with the consideration of reduced targets for the economic performance of a first generation of fusion power plants that could be deployed as early as possible, and so reduced targets for the technical performance of early DEMOs. The implications of the reference scenario and variants for fusion materials development are considerable, and these are discussed in this paper.

  18. REACTOR

    DOEpatents

    Spitzer, L. Jr.

    1962-01-01

    The system conteraplates ohmically heating a gas to high temperatures such as are useful in thermonuclear reactors of the stellarator class. To this end the gas is ionized and an electric current is applied to the ionized gas ohmically to heat the gas while the ionized gas is confined to a central portion of a reaction chamber. Additionally, means are provided for pumping impurities from the gas and for further heating the gas. (AEC)

  19. The Fluid Dynamics Demo Kit: Part I

    NASA Astrophysics Data System (ADS)

    Flack, Karen; Underhill, Patrick; Prestridge, Kathy

    2012-11-01

    The goal of this project is to develop a fluid dynamics demonstration/experiment kit that can be used by professors and graduate students at high school outreach events. The demonstrations in the kit will be easy to use and true crowd pleasers in order to inspire understanding and pique curiosity about the physics of flow. The kits will be inexpensive, containing readily available materials so that teachers can duplicate the demonstrations and experiments. The kits will be left with the teachers as a gift from the American Physics Society. The experiments and demonstrations cover the concepts of conservation of mass, momentum, and energy, Bernoulli's equation, frictional losses and the ideal gas law. For each experiment, the teachers will receive presentation material, access to instructional videos, plus a worksheet that can be used in a high school physics classroom. This kit has been developed through the efforts of the APS-DFD Mentoring and Outreach Committee and has received funding from the APS-DFD. Work funded by the APS-DFD.

  20. Reactor

    DOEpatents

    Evans, Robert M.

    1976-10-05

    1. A neutronic reactor having a moderator, coolant tubes traversing the moderator from an inlet end to an outlet end, bodies of material fissionable by neutrons of thermal energy disposed within the coolant tubes, and means for circulating water through said coolant tubes characterized by the improved construction wherein the coolant tubes are constructed of aluminum having an outer diameter of 1.729 inches and a wall thickness of 0.059 inch, and the means for circulating a liquid coolant through the tubes includes a source of water at a pressure of approximately 350 pounds per square inch connected to the inlet end of the tubes, and said construction including a pressure reducing orifice disposed at the inlet ends of the tubes reducing the pressure of the water by approximately 150 pounds per square inch.

  1. The Role of Community Colleges in Advancing Upward Mobility: A Demos Perspective

    ERIC Educational Resources Information Center

    Huelsman, Mark

    2015-01-01

    This article provides a short background on Demos, a public policy organization that works on issues of political and economic inequality. Demos views community colleges as a linchpin in the American higher education system, and it has worked over several years to research ways to increase state support for higher education and direct support…

  2. Demos as an Explanatory Lens in Teacher Educators' Elusive Search for Social Justice

    ERIC Educational Resources Information Center

    Oikonomidoy, Eleni M.; Brock, Cynthia H.; Obenchain, Kathryn M.; Pennington, Julie L.

    2013-01-01

    Borrowing insights from the Ancient Greek ideal conceptions of a democratic civic space (demos), this article examines the applicability of this framework to four teacher educators' journey to implement social justice in their programs. It is proposed that the three constitutive dimensions of demos (freedom of speech, equality to vote and…

  3. Neutral Particle Analysis on ITER and requirements for DEMO

    SciTech Connect

    Afanasyev, V. I.; Mironov, M. I.; Khudoleev, A. V.; Petrov, M. P.; Nesenevich, V. G.; Petrov, S. Ya.; Kislyakov, A. I.; Chernyshev, F. V.; Melnik, A. D.; Konovalov, S. V.; Kozlovsky, S. S.; Lyublin, B. V.

    2008-03-12

    The use of the neutral particle analysis (NPA) to study the ion component of plasma on ITER has been reviewed. Both thermal (10-200 keV) and supra-thermal (0.2-4 MeV) energy ranges of neutral fluxes are studied in respect to feasibility of the fusion fuel isotopic composition measurements. Influence of heating neutral beams and diagnostic neutral beam on the measurements is also shown. Possible application of the NPA to measure the energy distribution function of fusion alpha particles is discussed. Low- and high-energy NPA monitors have been proposed for DEMO machine to control the DT fuel isotope ratio.

  4. An FPGA computing demo core for space charge simulation

    SciTech Connect

    Wu, Jinyuan; Huang, Yifei; /Fermilab

    2009-01-01

    In accelerator physics, space charge simulation requires large amount of computing power. In a particle system, each calculation requires time/resource consuming operations such as multiplications, divisions, and square roots. Because of the flexibility of field programmable gate arrays (FPGAs), we implemented this task with efficient use of the available computing resources and completely eliminated non-calculating operations that are indispensable in regular micro-processors (e.g. instruction fetch, instruction decoding, etc.). We designed and tested a 16-bit demo core for computing Coulomb's force in an Altera Cyclone II FPGA device. To save resources, the inverse square-root cube operation in our design is computed using a memory look-up table addressed with nine to ten most significant non-zero bits. At 200 MHz internal clock, our demo core reaches a throughput of 200 M pairs/s/core, faster than a typical 2 GHz micro-processor by about a factor of 10. Temperature and power consumption of FPGAs were also lower than those of micro-processors. Fast and convenient, FPGAs can serve as alternatives to time-consuming micro-processors for space charge simulation.

  5. Overview of EU activities on DEMO liquid metal breeder blanket

    SciTech Connect

    Giancarli, L.; Proust, E.

    1994-12-31

    The European test-blanket development programme, started in 1988, is aiming at the selection by 1995 of two DEMO-relevant blanket lines to be tested in ITER. At present, four lines of blanket are under development, two of them using solid and the other two liquid breeder materials. As far as liquid breeders are concerned, two lines of blankets have been selected within the European Union, the water-cooled lithium-lead (the eutectic Pb-17Li) blankets and the dual-coolant Pb-17Li blankets. Designs have been developed considering an agreed set of DEMO specifications, such as, for instance, a fusion power of 2,200 MW, a neutron wall-loading of 2MW/m{sup 2}, a life-time of 20,000 hours, and the use of martensitic steel as a structural material. Moreover, an experimental program has been set up in order to address the main critical issues for each line. The present paper gives an overview of both design and experimental activities within the European Union concerning these two lines of liquid breeder blankets.

  6. Ion source development for a photoneutralization based NBI system for fusion reactors

    SciTech Connect

    Simonin, A.; Esch, H. P. L. de; Garibaldi, P.; Grand, C.; Bechu, S.; Bès, A.; Lacoste, A.

    2015-04-08

    The next step after ITER is to demonstrate the viability and generation of electricity by a future fusion reactor (DEMO). The specifications required to operate an NBI system on DEMO are very demanding. The system has to provide a very high level of power and energy, ~100MW of D° beam at 1MeV, including high wall-plug efficiency (η > 60%). For this purpose, a new injector concept, called Siphore, is under investigation between CEA and French universities. Siphore is based on the stripping of the accelerated negative ions by photo-detachment provided by several Fabry-Perot cavities (3.5MW of light power per cavity) implemented along the D{sup −} beam. The beamline is designed to be tall and narrow in order that the photon flux overlaps the entire negative ion beam. The paper will describe the present R and D at CEA which addresses the development of an ion source and pre-accelerator prototypes for Siphore, the main goal being to produce an intense negative ion beam sheet. The negative ion source Cybele is based on a magnetized plasma column where hot electrons are emitted from the source center. Parametric studies of the source are performed using Langmuir probes in order to characterize the plasma and to compare with numerical models being developed in French universities.

  7. Ion source development for a photoneutralization based NBI system for fusion reactors

    NASA Astrophysics Data System (ADS)

    Simonin, A.; de Esch, H. P. L.; Garibaldi, P.; Grand, C.; Bechu, S.; Bès, A.; Lacoste, A.

    2015-04-01

    The next step after ITER is to demonstrate the viability and generation of electricity by a future fusion reactor (DEMO). The specifications required to operate an NBI system on DEMO are very demanding. The system has to provide a very high level of power and energy, ~100MW of D° beam at 1MeV, including high wall-plug efficiency (η > 60%). For this purpose, a new injector concept, called Siphore, is under investigation between CEA and French universities. Siphore is based on the stripping of the accelerated negative ions by photo-detachment provided by several Fabry-Perot cavities (3.5MW of light power per cavity) implemented along the D- beam. The beamline is designed to be tall and narrow in order that the photon flux overlaps the entire negative ion beam. The paper will describe the present R&D at CEA which addresses the development of an ion source and pre-accelerator prototypes for Siphore, the main goal being to produce an intense negative ion beam sheet. The negative ion source Cybele is based on a magnetized plasma column where hot electrons are emitted from the source center. Parametric studies of the source are performed using Langmuir probes in order to characterize the plasma and to compare with numerical models being developed in French universities.

  8. Normal operation and maintenance safety lessons from the ITER US PbLi test blanket module program for a US FNSF and DEMO

    SciTech Connect

    L. C. Cadwallader; C. P. C. Wong; M. Abdou; B. B. Morely; B.J Merrill

    2014-10-01

    A leading power reactor breeding blanket candidate for a fusion demonstration power plant (DEMO) being pursued by the US Fusion Community is the Dual Coolant Lead Lithium (DCLL) concept. The safety hazards associated with the DCLL concept as a reactor blanket have been examined in several US design studies. These studies identify the largest radiological hazards as those associated with the dust generation by plasma erosion of plasma blanket module first walls, oxidation of blanket structures at high temperature in air or steam, inventories of tritium bred in or permeating through the ferritic steel structures of the blanket module and blanket support systems, and the 210Po and 203Hg produced in the PbLi breeder/coolant. What these studies lack is the scrutiny associated with a licensing review of the DCLL concept. An insight into this process was gained during the US participation in the International Thermonuclear Experimental Reactor (ITER) Test Blanket Module (TBM) Program. In this paper we discuss the lessons learned during this activity and make safety proposals for the design of a Fusion Nuclear Science Facility (FNSF) or a DEMO that employs a lead lithium breeding blanket.

  9. NEXT-DEMO: a prototype for the NEXT experiment

    NASA Astrophysics Data System (ADS)

    Ferrario, P.

    2012-11-01

    NEXT is a high-pressure (10-15 bar) xenon Time Projection Chamber dedicated to neutrinoless double beta decay searches. NEXT-DEMO is a large prototype of the NEXT experiment, constructed to demonstrate the feasibility of the NEXT detector concept, in particular the capability of the TPC to achieve an optimal energy resolution at the Xe Qββ energy (2.458 MeV). It has been operating at IFIC, in Valencia, for one year and a half and a number of results has been achieved. Recently, the reflector panels of the prototype have been coated with a wavelength shifter (TPB), in order to improve light collection. We have obtained an energy resolution of 2.3% FWHM at 511 keV, using Na-22 radioactive sources, corresponding to 1% FWHM once extrapolated to Qββ.

  10. MKID multicolor array status and results from DemoCam

    NASA Astrophysics Data System (ADS)

    Schlaerth, James A.; Czakon, Nicole G.; Day, Peter K.; Downes, Thomas P.; Duan, Ran; Gao, Jiansong; Glenn, Jason; Golwala, Sunil R.; Hollister, Matthew I.; LeDuc, Henry G.; Mazin, Benjamin A.; Maloney, Philip R.; Noroozian, Omid; Nguyen, Hien T.; Sayers, Jack; Siegel, Seth; Vaillancourt, John E.; Vayonakis, Anastasios; Wilson, Philip R.; Zmuidzinas, Jonas

    2010-07-01

    We present the results of the latest multicolor Microwave Kinetic Inductance Detector (MKID) focal plane arrays in the submillimeter. The new detectors on the arrays are superconducting resonators which combine a coplanar waveguide section with an interdigitated capacitor, or IDC. To avoid out-of-band pickup by the capacitor, a stepped-impedance filter is used to prevent radiation from reaching the absorptive aluminum section of the resonator. These arrays are tested in the preliminary demonstration instrument, DemoCam, a precursor to the Multicolor Submillimeter Inductance Camera, MUSIC. We present laboratory results of the responsivity to light both in the laboratory and at the Caltech Submillimeter Observatory. We assess the performance of the detectors in filtering out-of-band radiation, and find the level of excess load and its effect on detector performance. We also look at the array design characteristics, and the implications for the optimization of sensitivities expected by MUSIC.

  11. Demo III: Department of Defense testbed for unmanned ground mobility

    NASA Astrophysics Data System (ADS)

    Shoemaker, Chuck M.; Bornstein, Jonathan A.; Myers, Scott D.; Brendle, Bruce E., Jr.

    1999-07-01

    Robotics has been identified by numerous recent Department of Defense (DOD) studies as a key enabling technology for future military operational concepts. The Demo III Program is a multiyear effort encompassing technology development and demonstration on testbed platforms, together with modeling simulation and experimentation directed toward optimization of operational concepts to employ this technology. Primary program focus is the advancement of capabilities for autonomous mobility through unstructured environments, concentrating on both perception and intelligent control technology. The scout mission will provide the military operational context for demonstration of this technology, although a significant emphasis is being placed upon both hardware and software modularity to permit rapid extension to other military missions. The Experimental Unmanned Vehicle (XUV) is a small (approximately 1150 kg, V-22 transportable) technology testbed vehicle designed for experimentation with multiple military operational concepts. Currently under development, the XUV is scheduled for roll-out in Summer 1999, with an initial troop experimentation to be conducted in September 1999. Though small, and relatively lightweight, modeling has shown the chassis capable of automotive mobility comparable to the current Army lightweight high-mobility, multipurpose, wheeled vehicle (HMMWV). The XUV design couples multisensor perception with intelligent control to permit autonomous cross-country navigation at speeds of up to 32 kph during daylight and 16 kph during hours of darkness. A small, lightweight, highly capable user interface will permit intuitive control of the XUV by troops from current-generation tactical vehicles. When it concludes in 2002, Demo III will provide the military with both the technology and the initial experience required to develop and field the first generation of semi-autonomous tactical ground vehicles for combat, combat support, and logistics applications.

  12. Maximal design basis accident of fusion neutron source DEMO-TIN

    NASA Astrophysics Data System (ADS)

    Kolbasov, B. N.

    2015-12-01

    When analyzing the safety of nuclear (including fusion) facilities, the maximal design basis accident at which the largest release of activity is expected must certainly be considered. Such an accident is usually the failure of cooling systems of the most thermally stressed components of a reactor (for a fusion facility, it is the divertor or the first wall). The analysis of safety of the ITER reactor and fusion power facilities (including hybrid fission-fusion facilities) shows that the initial event of such a design basis accident is a large-scale break of a pipe in the cooling system of divertor or the first wall outside the vacuum vessel of the facility. The greatest concern is caused by the possibility of hydrogen formation and the inrush of air into the vacuum chamber (VC) with the formation of a detonating mixture and a subsequent detonation explosion. To prevent such an explosion, the emergency forced termination of the fusion reaction, the mounting of shutoff valves in the cooling systems of the divertor and the first wall or blanket for reducing to a minimum the amount of water and air rushing into the VC, the injection of nitrogen or inert gas into the VC for decreasing the hydrogen and oxygen concentration, and other measures are recommended. Owing to a continuous feed-out of the molten-salt fuel mixture from the DEMO-TIN blanket with the removal period of 10 days, the radioactivity release at the accident will mainly be determined by tritium (up to 360 PBq). The activity of fission products in the facility will be up to 50 PBq.

  13. Maximal design basis accident of fusion neutron source DEMO-TIN

    SciTech Connect

    Kolbasov, B. N.

    2015-12-15

    When analyzing the safety of nuclear (including fusion) facilities, the maximal design basis accident at which the largest release of activity is expected must certainly be considered. Such an accident is usually the failure of cooling systems of the most thermally stressed components of a reactor (for a fusion facility, it is the divertor or the first wall). The analysis of safety of the ITER reactor and fusion power facilities (including hybrid fission–fusion facilities) shows that the initial event of such a design basis accident is a large-scale break of a pipe in the cooling system of divertor or the first wall outside the vacuum vessel of the facility. The greatest concern is caused by the possibility of hydrogen formation and the inrush of air into the vacuum chamber (VC) with the formation of a detonating mixture and a subsequent detonation explosion. To prevent such an explosion, the emergency forced termination of the fusion reaction, the mounting of shutoff valves in the cooling systems of the divertor and the first wall or blanket for reducing to a minimum the amount of water and air rushing into the VC, the injection of nitrogen or inert gas into the VC for decreasing the hydrogen and oxygen concentration, and other measures are recommended. Owing to a continuous feed-out of the molten-salt fuel mixture from the DEMO-TIN blanket with the removal period of 10 days, the radioactivity release at the accident will mainly be determined by tritium (up to 360 PBq). The activity of fission products in the facility will be up to 50 PBq.

  14. Development of DEMO-FNS tokamak for fusion and hybrid technologies

    NASA Astrophysics Data System (ADS)

    Kuteev, B. V.; Azizov, E. A.; Alexeev, P. N.; Ignatiev, V. V.; Subbotin, S. A.; Tsibulskiy, V. F.

    2015-07-01

    The history of fusion-fission hybrid systems based on a tokamak device as an extremely efficient DT-fusion neutron source has passed through several periods of ample research activity in the world since the very beginning of fusion research in the 1950s. Recently, a new roadmap of the hybrid program has been proposed with the goal to build a pilot hybrid plant (PHP) in Russia by 2030. Development of the DEMO-FNS tokamak for fusion and hybrid technologies, which is planned to be built by 2023, is the key milestone on the path to the PHP. This facility is in the phase of conceptual design aimed at providing feasibility studies for a full set of steady state tokamak technologies at a fusion energy gain factor Q ˜ 1, fusion power of ˜40 MW and opportunities for testing a wide range of hybrid technologies with the emphasis on continuous nuclide processing in molten salts. This paper describes the project motivations, its current status and the key issues of the design.

  15. Helium-cooled divertor for DEMO: Manufacture and high heat flux tests of tungsten-based mock-ups

    NASA Astrophysics Data System (ADS)

    Norajitra, P.; Gervash, A.; Giniyatulin, R.; Hirai, T.; Janeschitz, G.; Krauss, W.; Kuznetsov, V.; Makhankov, A.; Mazul, I.; Ovchinnikov, I.; Reiser, J.; Widak, V.

    2009-04-01

    A helium-cooled divertor concept for DEMO has been investigated extensively at the Forschungszentrum Karlsruhe under the EU power plant conceptual study, the goal being to demonstrate performance under heat flux of 10 MW/m 2 at least. Work covers different areas ranging from conceptual design to analysis, materials and fabrication issues to experiments. Meanwhile, the He-cooled modular divertor concept with jet cooling (HEMJ) has been proposed as reference design. In cooperation with the Efremov Institute, manufacture and high heat flux testing of divertor elements was performed for design verification and proof-of-principle. This paper focuses on the technological study of the fabrication of mock-ups from W/W alloy and Eurofer steel supporting structure material. The high heat flux test results of 2006 and 2007 are summarised and discussed.

  16. Recent ASDEX Upgrade research in support of ITER and DEMO

    NASA Astrophysics Data System (ADS)

    H. Zohmthe ASDEX Upgrade Team; the EUROfusion MST1 Team

    2015-10-01

    Recent experiments on the ASDEX Upgrade tokamak aim at improving the physics base for ITER and DEMO to aid the machine design and prepare efficient operation. Type I edge localized mode (ELM) mitigation using resonant magnetic perturbations (RMPs) has been shown at low pedestal collisionality (νped\\ast <0.4) . In contrast to the previous high ν* regime, suppression only occurs in a narrow RMP spectral window, indicating a resonant process, and a concomitant confinement drop is observed due to a reduction of pedestal top density and electron temperature. Strong evidence is found for the ion heat flux to be the decisive element for the L-H power threshold. A physics based scaling of the density at which the minimum PLH occurs indicates that ITER could take advantage of it to initiate H-mode at lower density than that of the final Q = 10 operational point. Core density fluctuation measurements resolved in radius and wave number show that an increase of R/LTe introduced by off-axis electron cyclotron resonance heating (ECRH) mainly increases the large scale fluctuations. The radial variation of the fluctuation level is in agreement with simulations using the GENE code. Fast particles are shown to undergo classical slowing down in the absence of large scale magnetohydrodynamic (MHD) events and for low heating power, but show signs of anomalous radial redistribution at large heating power, consistent with a broadened off-axis neutral beam current drive current profile under these conditions. Neoclassical tearing mode (NTM) suppression experiments using electron cyclotron current drive (ECCD) with feedback controlled deposition have allowed to test several control strategies for ITER, including automated control of (3,2) and (2,1) NTMs during a single discharge. Disruption mitigation studies using massive gas injection (MGI) can show an increased fuelling efficiency with high field side injection, but a saturation of the fuelling efficiency is observed at high injected

  17. Optical modeling of the Jefferson Laboratory IR demo FEL

    NASA Astrophysics Data System (ADS)

    Neil, George R.; Benson, Stephen V.; Shinn, Michelle D.; Davidson, Paul C.; Kloeppel, Peter K.

    1997-05-01

    The Thomas Jefferson National Accelerator Facility (formerly known as CEBAF) has embarked on the construction of a 1 kW free-electron laser operating initially at 3 microns that is designed for laser-material interaction experiments and to explore the feasibility of scaling the system in power and wavelength for industrial and Navy defense applications. The accelerator system for this IR demo includes a 10 MeV photocathode-based injector, a 32 MeV CEBAF-style superconducting radio-frequency linac, and single-pass transport which accelerates the beam from injector to wiggler, followed by energy-recovery deceleration to a dump. The electron and optical beam time structure in the design consists of a train of picosecond pulses at 37.425 MHz pulse repetition rate. The initial optical configuration is a conventional near-concentric resonator with transmissive outcoupling. Future upgrades of the system will increase the power and shorten the operating wavelength, and utilize a more advanced resonator system capable of scaling to high powers. The optical system of the laser has been modeled using the GLADR code by using a Beer's-law region to mimic the FEL interaction. Effects such as mirror heating have been calculated and compared with analytical treatments. The magnitude of the distortion for several materials and wavelengths has been estimated. The advantages as well as the limitations of this approach are discussed.

  18. Monitoring reticle molecular contamination in ASML EUV Alpha Demo Tool

    NASA Astrophysics Data System (ADS)

    Okoroanyanwu, Uzodinma; Jiang, Aiqin; Dittmar, Kornelia; Fahr, Torsten; Laursen, Thomas; Wood, Obert; Cummings, Kevin; Holfeld, Christian; Peters, Jan-Hendrik; Gullikson, Eric; La Fontaine, Bruno

    2010-04-01

    Molecular contamination risk to an EUV reticle exposed to up to 1600J/cm2 of 13.5 nm EUV radiation in ASML Alpha Demo Tool (ADT) is negligible. Carbon film (< 0.5 nm) deposition and oxidation (surface oxides ~1 nm) are the two main molecular contaminants observed on this EUV reticle. These results run counter to recent empirical results obtained from EUV micro-exposure tools (MET) which suggest that molecular contamination of EUV reticles, even at the very low partial pressures expected in the exposure chamber of EUV exposure tools, poses challenges in the implementation of EUV lithography in large-scale volume manufacturing of devices. To assess the molecular contamination risk to the use and lifetime of a given EUV reticle, we monitored the contamination buildup on a specially designed reticle during one year as it was exposed on ASML ADT located in Albany, New York. The reticle was analyzed with a suite of complementary surface analytical technique (such as Auger Electron Spectroscopy, AES) and chemical analytical techniques (such as Grazing Incidence Reflection Fourier Transform Infra-red Spectroscopy, GIR-FTIR), as well as imaging technique (such as Scanning Electron Microscopy). The influence of molecular contamination on the reflectivity of this reticle was measured at the Lawrence Berkeley Advanced Light Source EUV reflectometry. The differences in the contamination outcome of EUV reticles exposed in ASML ADT and MET may be related to the implementation of active contamination mitigation schemes in ADT and the lack of similar schemes in METs.

  19. UAS-NAS Project Demo - Mini HITL Week 2 Stats

    NASA Technical Reports Server (NTRS)

    Murphy, James R.; Fern, Lisa C.; Rorie, Robert C.; Shively, Robert; Jovic, Srboljub

    2016-01-01

    The UAS-NAS Project demo will showcase recent research efforts to ensure the interoperability between proposed UAS detect and avoid (DAA) human machine interface requirements (developed within RTCA SC-228) and existing collision avoidance displays. Attendees will be able to view the current state of the art of the DAA pilot traffic, alerting and guidance displays integrated with Traffic advisory and Collision Avoidance (TCAS) II in the UAS-NAS Project's research UAS ground control station (developed in partnership with the Air Force Research Laboratory). In addition, attendees will have the opportunity to interact with the research UAS ground control station and "fly" encounters, using the DAA and TCAS II displays to avoid simulated aircraft. The display of the advisories will be hosted on a laptop with an external 30" monitor, running the Vigilant Spirit system. DAA advisories will be generated by the JADEM software tool, connected to the system via the LVC Gateway. A repeater of the primary flight display will be shown on a 55" monitor mounted on a stand at the back of the booth to show the pilot interaction to the passersby.

  20. Review of SRC-II process product hydrotreating data, for completeness and applicability to the demo plant

    SciTech Connect

    Frazier, G.C.; Faruqi, A.

    1981-03-01

    The SRC-II product naphtha, gas oil, and whole liquid product hydrotreating data base was reviewed for completeness and applicability to the design of the SRC-II Demonstration Plant. Primary data sources were the Chevron and the UOP experimental hydrotreating work and the PNL bioassay investigations on UOP hydrotreated samples. Secondary data were the hydrotreating data for both the EDS and the H-Coal liquid products. The SRC-II product hydrotreating data are sparse at this point, but in view of the fact that these data can be supplemented through correlation with the corresponding data for the EDS and H-Coal liquid fractions, it is concluded that a sufficient data base exists for the closure of a hydrotreating plant material balance at least in the hydrotreating severity range of the Phase 0 design goals. Little thermal property data appear in the literature for coal-derived liquids; thus it will be necessary to draw upon correlations developed in the petroleum industry for closure of the plant energy balance unless experimental thermal property data are forthcoming. An area of uncertainty and concern at this time is the extent to which the Demo Plant product mutagenicity would be reduced by hydrotreatment. Although bioassay tests were conducted on both moderately and severely hydrotreated SRC-II Pilot Plant gas oil, the Demo Plant product is expected to contain an appreciable fraction of 800/sup 0/F/sup +/ material, compared with the Pilot Plant product, which contained essentially no material in this higher boiling range.

  1. X-ray diagnostic developments in the perspective of DEMO

    NASA Astrophysics Data System (ADS)

    Pacella, D.; Romano, A.; Gabellieri, L.; Causa, F.; Murtas, F.; Claps, G.; Choe, W.; Lee, S. H.; Jang, S.; Jang, J.; Hong, J.; Jeon, T.; Lee, H.

    2014-08-01

    laboratory both as imaging optical device (full lens) or to define a line of sight (cylinder lens); the preliminary results are encouraging toward the goal of using these lenses to transport X-ray radiation far from the reactor. Reflective or diffractive X-ray optics can be also an option for tomography. A GEM detector has been installed at KSTAR and in the next future hopefully the other approaches will be tested there: once their feasibility will be demonstrated, the issue of the improvement of the radiation tolerance will be faced and the development of algorithms for data analysis as well.

  2. X-ray diagnostic developments in the perspective of DEMO

    SciTech Connect

    Pacella, D.; Romano, A.; Gabellieri, L.; Causa, F.; Murtas, F.; Claps, G.; Choe, W.; Lee, S. H.; Jang, S.; Jang, J.; Hong, J.; Jeon, T.; Lee, H.

    2014-08-21

    studied in the laboratory both as imaging optical device (full lens) or to define a line of sight (cylinder lens); the preliminary results are encouraging toward the goal of using these lenses to transport X-ray radiation far from the reactor. Reflective or diffractive X-ray optics can be also an option for tomography. A GEM detector has been installed at KSTAR and in the next future hopefully the other approaches will be tested there: once their feasibility will be demonstrated, the issue of the improvement of the radiation tolerance will be faced and the development of algorithms for data analysis as well.

  3. Developing structural, high-heat flux and plasma facing materials for a near-term DEMO fusion power plant: The EU assessment

    NASA Astrophysics Data System (ADS)

    Stork, D.; Agostini, P.; Boutard, J. L.; Buckthorpe, D.; Diegele, E.; Dudarev, S. L.; English, C.; Federici, G.; Gilbert, M. R.; Gonzalez, S.; Ibarra, A.; Linsmeier, Ch.; Li Puma, A.; Marbach, G.; Morris, P. F.; Packer, L. W.; Raj, B.; Rieth, M.; Tran, M. Q.; Ward, D. J.; Zinkle, S. J.

    2014-12-01

    The findings of the EU 'Materials Assessment Group' (MAG), within the 2012 EU Fusion Roadmap exercise, are discussed. MAG analysed the technological readiness of structural, plasma facing and high heat flux materials for a DEMO concept to be constructed in the early 2030s, proposing a coherent strategy for R&D up to a DEMO construction decision. A DEMO phase I with a 'Starter Blanket' and 'Starter Divertor' is foreseen: the blanket being capable of withstanding ⩾2 MW yr m-2 fusion neutron fluence (∼20 dpa in the front-wall steel). A second phase ensues for DEMO with ⩾5 MW yr m-2 first wall neutron fluence. Technical consequences for the materials required and the development, testing and modelling programmes, are analysed using: a systems engineering approach, considering reactor operational cycles, efficient maintenance and inspection requirements, and interaction with functional materials/coolants; and a project-based risk analysis, with R&D to mitigate risks from material shortcomings including development of specific risk mitigation materials. The DEMO balance of plant constrains the blanket and divertor coolants to remain unchanged between the two phases. The blanket coolant choices (He gas or pressurised water) put technical constraints on the blanket steels, either to have high strength at higher temperatures than current baseline variants (above 650 °C for high thermodynamic efficiency from He-gas coolant), or superior radiation-embrittlement properties at lower temperatures (∼290-320 °C), for construction of water-cooled blankets. Risk mitigation proposed would develop these options in parallel, and computational and modelling techniques to shorten the cycle-time of new steel development will be important to achieve tight R&D timescales. The superior power handling of a water-cooled divertor target suggests a substructure temperature operating window (∼200-350 °C) that could be realised, as a baseline-concept, using tungsten on a copper

  4. An analysis of AMTEC, multi-cell ground-demo for the Pluto/Express mission

    SciTech Connect

    Tournier, J.M.; El-Genk, M.S.

    1998-07-01

    Results of recent tests of an 8-cell, AMTEC ground-demo are analyzed and the performance of individual cells compared. The ground-demo produced a peak electric power of 27 W{sub e} at an output voltage of 16 V, when tested at hot and cold side temperatures of 1123 K and 553 K. The electric power output and terminal voltage of the individual cells, however, differed by as much as 25%, from 2.94 to 3.76 W{sub e}, and 1.73 to 2.21 V, respectively. These variations were attributed to differences in: (a) contact resistance between electrode / BASE / current collector; (b) current (or electrons) leakage between anode and cathode electrodes through the metal-ceramic braze joint between BASE tubes and support plate; and (c) the charge-exchange polarization losses. Model's predictions compared very well with measured voltage and electric power output of individual cells and of the ground-demo. At the operating conditions for the Pluto/Express spacecraft (T{sub hot} {approximately} 1200 K, T{sub cd} {approximately} 573 K), the best performing ground-demo cell would have delivered 5 W{sub e} at an output voltage of 3 V. These values, however, are still significantly lower than those needed to meet the Pluto/Express mission power requirements (8.2 W{sub e} at 3.5 V, per cell).

  5. Modelling of ICRF heating in DEMO with special emphasis on bulk ion heating

    SciTech Connect

    Gallart, Dani; Mantsinen, Mervi; Kazakov, Yevgen

    2015-12-10

    Ion cyclotron resonance frequency (ICRF) heating is one of the auxiliary heating schemes presently envisaged for ITER and DEMO. In this paper we analyse the potential of ICRF waves to heat the fuel ions in DEMO. Our analysis is carried out for the DEMO1 Reference Scenario from October 2013 (B = 6.8 T, I = 18.6 MA, R = 9.25 m, a = 2.64 m) optimized for a maximum pulse length of 2.3 hrs using the ICRF modelling codes PION and TORIC. We focus on second harmonic heating of tritium and fundamental minority heating of {sup 3}He ions (with a few percent of {sup 3}He) in a 50%:50% D-T plasma. The dependence of the ICRF characteristics and the ICRF-accelerated ions on the ICRF and plasma parameters is investigated, giving special attention to the DEMO design point at a core plasma temperature of 30 keV and an electron density of 1.2·10{sup 20} m{sup −3}.

  6. 77 FR 51849 - Agency Information Collection: Emergency Submission for OMB Review (PACT Demo Lab, Clinical...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-08-27

    ... AFFAIRS Agency Information Collection: Emergency Submission for OMB Review (PACT Demo Lab, Clinical... to the Office of Management and Budget (OMB) the following emergency proposal for the collection of.... ADDRESSES: Send comments and recommendations concerning any aspect of the information collection to VA's...

  7. Modelling of ICRF heating in DEMO with special emphasis on bulk ion heating

    NASA Astrophysics Data System (ADS)

    Gallart, Dani; Mantsinen, Mervi; Kazakov, Yevgen

    2015-12-01

    Ion cyclotron resonance frequency (ICRF) heating is one of the auxiliary heating schemes presently envisaged for ITER and DEMO. In this paper we analyse the potential of ICRF waves to heat the fuel ions in DEMO. Our analysis is carried out for the DEMO1 Reference Scenario from October 2013 (B = 6.8 T, I = 18.6 MA, R = 9.25 m, a = 2.64 m) optimized for a maximum pulse length of 2.3 hrs using the ICRF modelling codes PION and TORIC. We focus on second harmonic heating of tritium and fundamental minority heating of 3He ions (with a few percent of 3He) in a 50%:50% D-T plasma. The dependence of the ICRF characteristics and the ICRF-accelerated ions on the ICRF and plasma parameters is investigated, giving special attention to the DEMO design point at a core plasma temperature of 30 keV and an electron density of 1.2.1020 m-3.

  8. An Assessment of the Penetrations in the First Wall Required for Plasma Measurments for Control of an Advanced Tokamak Plasma Demo

    SciTech Connect

    Kenneth M. Young

    2010-02-22

    A Demonstration tokamak (Demo) is an essential next step toward a magnetic-fusion based reactor. One based on advanced-tokamak (AT) plasmas is especially appealing because of its relative compactness. However, it will require many plasma measurements to provide the necessary signals to feed to ancillary systems to protect the device and control the plasma. This note addresses the question of how much intrusion into the blanket system will be required to allow the measurements needed to provide the information required for plasma control. All diagnostics will require, at least, the same shielding designs as planned for ITER, while having the capability to maintain their calibration through very long pulses. Much work is required to define better the measurement needs and the quantity and quality of the measurements that will have to be made, and how they can be integrated into the other tokamak structures.

  9. Alloying and coating strategies for improved Pb-Li compatibility in DEMO-type fusion reactors

    NASA Astrophysics Data System (ADS)

    Unocic, K. A.; Pint, B. A.

    2014-12-01

    Two strategies were explored to improve the Pb-16Li compatibility of Fe-base alloys for a fusion energy blanket system. The use of thin (∼50 μm) Al-rich diffusion coatings on Grade 92 (9Cr-2W) substrates significantly reduced the mass loss in static Pb-Li capsule tests for up to 5000 h at 600 °C and 700 °C. However, significant Al loss was observed at 700 °C. Thicker coatings with Fe-Al intermetallic layers partially spalled after exposure at 700 °C, suggesting that coating strategies are limited to lower temperatures. To identify compositions for further alloy development, model FeCrAlY alloys with 10-20 wt.%Cr and 3-5%Al were exposed for 1000 h at 700 °C. There was little effect on mass change of varying the Cr content, however, alloys with <5% Al showed mass losses in these experiments. For both coatings and FeCrAl alloys, the surface reaction product was LiAlO2 after exposure and cleaning.

  10. Effective Goal-Setting.

    ERIC Educational Resources Information Center

    West, Michael

    1993-01-01

    Setting organizational or program objectives is seen as requiring three steps (brainstorming goals for the year, prioritizing them, and visualizing them as smaller, discrete tasks) and six principles (making goals group-specific, setting deadlines, being realistic and explicit, writing down goals, defining measurable steps, and creating…

  11. Diagnostics and required R&D for control of DEMO grade plasmas

    NASA Astrophysics Data System (ADS)

    Park, Hyeon K.

    2014-08-01

    Even if the diagnostics of ITER performs as expected, installation and operation of the diagnostic systems in Demo device will be much harsher than those of the present ITER device. In order to operate the Demo grade plasmas, which may have a higher beta limit, safely with very limited number of simple diagnostic system, it requires a well defined predictable plasma modelling in conjunction with the reliable control system for burn control and potential harmful instabilities. Development of such modelling in ITER is too risky and the logical choice would be utilization of the present day steady state capable devices such as KSTAR and EAST. In order to fulfill this mission, sophisticated diagnostic systems such as 2D/3D imaging systems can validate the physics in the theoretical modeling and challenge the predictable capability.

  12. Applicability of tungsten/EUROFER blanket module for the DEMO first wall

    NASA Astrophysics Data System (ADS)

    Igitkhanov, Yu.; Bazylev, B.; Landman, I.; Boccaccini, L.

    2013-07-01

    In this paper we analyse a sandwich-type blanket configuration of W/EUROFER for DEMO first wall under steady-state normal operation and off-normal conditions, such as vertical displacements and runaway electrons. The heat deposition and consequent erosion of the tungsten armour is modelled under condition of helium cooling of the first wall blanket module and by taking into account the conversion of the magnetic energy stored in the runaway electron current into heat through the ohmic dissipation of the return current induced in the metallic armour structure. It is shown that under steady-state DEMO operation the first wall sandwich type module will tolerate heat loads up to ˜14 MW/m2. It will also sustain the off-normal events, apart from the hot vertical displacement events, which will melt the tungsten armour surface.

  13. Diagnostics and required R and D for control of DEMO grade plasmas

    SciTech Connect

    Park, Hyeon K.

    2014-08-21

    Even if the diagnostics of ITER performs as expected, installation and operation of the diagnostic systems in Demo device will be much harsher than those of the present ITER device. In order to operate the Demo grade plasmas, which may have a higher beta limit, safely with very limited number of simple diagnostic system, it requires a well defined predictable plasma modelling in conjunction with the reliable control system for burn control and potential harmful instabilities. Development of such modelling in ITER is too risky and the logical choice would be utilization of the present day steady state capable devices such as KSTAR and EAST. In order to fulfill this mission, sophisticated diagnostic systems such as 2D/3D imaging systems can validate the physics in the theoretical modeling and challenge the predictable capability.

  14. Physics and Engineering Assessmetns of the K-DEMO Magnet Configuration

    SciTech Connect

    Neilson, George H.; Brown, Thomas

    2014-09-01

    Increased attention is being given now to studies of next-step fusion facilities with nuclear missions. Among these, South Korea's K DEMO is unique in its focus on a high toroidal magnetic field, large major radius, steady-state tokamak design for the core of a facility to test fusion nuclear components in Phase I and, after upgrades, produce 500 MW of electricity in a Phase II. Innovative features of the K DEMO magnet set include the use of two toroidal field (TF) coil winding packs with conductor grading and a machine configuration designed for vertical maintenance. The magnet arrangement features large TF coils and widely spaced poloidal field (PF) coils to accommodate removal of in-vessel components as large modules. Physics and engineering assessments of the pre-conceptual K-DEMO magnet configuration are reported, including: 1) design point and operating space assessment, 2) conductor assessment, and 3) structural assessment. It is found that a reference design point at 6.8 m major radius and 7.4 T toroidal field provides sufficient operating margins for the 500 MWe Phase II mission. Analyses of candidate cable-in-conduit conductors provide predictions of critical current degradation, both in the initial load cycle and an additionally with cyclic loading. A first-pass global analysis of the magnet system found minimal out-of-plane deformations of the TF coil, but an overstress condition in the inner leg of the TF coil. However an analysis taking into account elastic-plastic behavior, frictional sliding, and displacement shows that the structure can safely carry the load. Although the design evolution is still at an early stage, these assessments support the design point choices to date and the expectation that a feasible solution for the high-field K DEMO magnet system can be found.

  15. The Selfish Goal

    PubMed Central

    Bargh, John A.; Green, Michelle; Fitzsimons, Gráinne

    2008-01-01

    Three experiments tested the hypothesis that consciously intended goal pursuits have unintended consequences for social judgment and behavior. From evolutionary theory (Dawkins 1976/2006) and empirical evidence of a nonconscious mode of goal pursuit (Bargh, 2005) we derive the hypothesis that most human goal pursuits are open-ended in nature: Once active, goals will operate on goal-relevant content in the environment, even if that content is not the intended focus of the conscious goal. Experiments 1 and 2 demonstrate that goals to evaluate a job applicant for either a waiter or crime reporter position also shape impressions of incidental bystanders in the situation, such that the bystander is later liked or disliked not on his own merits, but on how well his behavior matches the criteria consciously applied in evaluating the job applicant. Experiment 3 finds that a goal to help a specific target person spills over to influence actions toward incidental bystanders, but only while active. Implications of these findings for goal pursuit in everyday life are discussed. PMID:19081795

  16. Addressees of Performance Goals

    ERIC Educational Resources Information Center

    Ziegler, Albert; Dresel, Markus; Stoeger, Heidrun

    2008-01-01

    As performance goals aim to both procure acknowledgment of one's abilities and to avoid revealing a lack of one's abilities, the authors hypothesized that students hold specific performance goals for different addressees and that there are specific correlational patterns with other motivational constructs. They analyzed a data set of 2,675 pupils…

  17. Can Goals Motivate Students?

    ERIC Educational Resources Information Center

    Usher, Alexandra; Kober, Nancy

    2012-01-01

    This is the third in a series of six papers by the Center on Education Policy exploring issues related to students' motivation to learn. This paper examines various programs that use test performance or postsecondary attendance as motivational goals and the effects of these goals on students. How do policies surrounding assessments and college…

  18. THE GOALS OF INTEGRATION.

    ERIC Educational Resources Information Center

    HANDLIN, OSCAR

    THE LACK OF CLEARLY DEFINED GOALS WITHIN THE CIVIL RIGHTS MOVEMENT IS IMPEDING ITS TACTICS AND MOMENTUM. THE STATED GOAL OF INTEGRATION ACTUALLY HAS TWO ALTERNATIVE INTERPRETATIONS--FULL LEGAL EQUALITY AND RACIAL BALANCE. THE NEWER STRESS ON RACIAL BALANCE RESTS ON THE FALLACIOUS ASSUMPTIONS THAT THE NEGRO'S SITUATION IS UNIQUE BECAUSE OF SLAVERY…

  19. Goal-Directed Schools

    ERIC Educational Resources Information Center

    Bernstein, Marc F.; Troisi, Thomas J.; Pompilio, Joseph P.

    2009-01-01

    The goal of every school district is to help students succeed academically and personally. But does every district leverage its most valuable resource, its teachers, to meet that goal? At the Valley Stream Central High School District in Nassau County, New York, these authors know how important teacher commitment is to student success, so they…

  20. Goal Setting and Hope

    ERIC Educational Resources Information Center

    Curran, Katie; Reivich, Karen

    2011-01-01

    The science behind the mechanisms and mediators that lead to successful goal accomplishment has been a focus of research since the 1970s. When an individual desires to make a change or accomplish an outcome, research shows that he or she will be more successful if he or she attends to a number of variables that are key in goal setting.…

  1. Critical design factors for sector transport maintenance in DEMO

    NASA Astrophysics Data System (ADS)

    Utoh, Hiroyasu; Someya, Youji; Tobita, Kenji; Asakura, Nobuyuki; Hoshino, Kazuo; Nakamura, Makoto

    2013-12-01

    This paper mainly focuses on a sector transport maintenance scheme from the aspects of high plant availability. In this study, three different maintenance schemes are considered based on (1) the number of maintenance ports and (2) the insertion direction. The design study clarifies critical design factors and key engineering issues on the maintenance scheme: (1) how to support an enormous overturning force of the toroidal field coils in the large open port for sector transport and (2) define the transferring mechanism of sectors in the vacuum vessel. On reviewing these assessment factors, the sector transport using a limited number of horizontal maintenance ports is found to be a more realistic maintenance scheme. In addition, evaluating maintenance scenarios under high decay heat is proposed for the first time. The key design factors are the cool-down time in the reactor and the cooling method in the maintenance scheme to keep components under operational temperature. Based on one-dimensional heat conduction analysis, after one month cool-down time, each sector of SlimCS could be transported to the hot cell facility by gas cooling.

  2. Environment and safety: major goals for MARS

    SciTech Connect

    Maninger, R.C.

    1983-03-16

    The Mirror Advanced Reactor Study (MARS) is a conceptual design study for a commercial fusion power reactor. One of the major goals of MARS is to develop design guidance so that fusion reactors can meet reasonable expectations for environmental health and safety. One of the first steps in the assessment of health and safety requirements was to examine what the guidelines might be for health and safety in disposal of radioactive wastes from fusion reactors. Then, using these quidelines as criteria, the impact of materials selection upon generation of radioactive wastes through neutron activation of structural materials was investigated. A conclusion of this work is that fusion power systems may need substantial engineering effort in new materials development and selection to meet the probable publicly acceptable levels of radioactivity for waste disposal in the future.

  3. High frequency fast wave current drive for DEMO

    SciTech Connect

    Koch, R.; Lerche, E.; Van Eester, D.

    2011-12-23

    A steady-state tokamak reactor (SSTR) requires a high efficiency current drive system, from plug to driven mega-amps. RF systems working in the ion-cyclotron range of frequencies (ICRF) have high efficiency from plug to antenna but a limited current drive (CD) efficiency and centrally peaked CD profiles. The latter feature is not adequate for a SSTR where the current should be sufficiently broad to keep the central safety factor (possibly significantly) above 1. In addition, the fact that the fast wave (FW) is evanescent at the edge limits coupling, requiring high voltage operation, which makes the system dependent on plasma edge properties and prone to arcing, reducing its reliability. A possible way to overcome these weaknesses is to operate at higher frequency (10 times or more the cyclotron frequency). The advantages are: (1) The coupling can be much better (waves propagate in vacuum) if the parallel refractive index n{sub ||} is kept below one, (2) The FW group velocity tends to align to the magnetic field, so the power circumnavigates the magnetic axis and can drive off-axis current, (3) Due to the latter property, n{sub ||} can be upshifted along the wave propagation path, allowing low n{sub ||} launch (hence good coupling, large CD efficiency) with ultimately good electron absorption (which requires higher n{sub ||}. Note however that the n{sub ||} upshift is a self-organized feature, that electron absorption is in competition with {alpha}-particle absorption and that uncoupling of the FW from the lower hybrid resonance at the edge requires n{sub ||} slightly above one. The latter possibly counterproductive features might complicate the picture. The different aspects of this potentially attractive off-axis FWCD scheme are discussed.

  4. SIPHORE: Conceptual Study of a High Efficiency Neutral Beam Injector Based on Photo-detachment for Future Fusion Reactors

    SciTech Connect

    Simonin, A.; Christin, L.; Esch, H. de; Garibaldi, P.; Grand, C.; Villecroze, F.; Blondel, C.; Delsart, C.; Drag, C.; Vandevraye, M.; Brillet, A.; Chaibi, W.

    2011-09-26

    An innovative high efficiency neutral beam injector concept for future fusion reactors is under investigation (simulation and R and D) between several laboratories in France, the goal being to perform a feasibility study for the neutralization of intense high energy (1 MeV) negative ion (NI) beams by photo-detachment.The objective of the proposed project is to put together the expertise of three leading groups in negative ion quantum physics, high power stabilized lasers and neutral beam injectors to perform studies of a new injector concept called SIPHORE (SIngle gap PHOto-neutralizer energy REcovery injector), based on the photo-detachment of negative ions and energy recovery of unneutralised ions; the main feature of SIPHORE being the relevance for the future Fusion reactors (DEMO), where high injector efficiency (up to 70-80%), technological simplicity and cost reduction are key issues to be addressed.The paper presents the on-going developments and simulations around this project, such as, a new concept of ion source which would fit with this injector topology and which could solve the remaining uniformity issue of the large size ion source, and, finally, the presentation of the R and D program in the laboratories (LAC, ARTEMIS) around the photo-neutralization for Siphore.

  5. Interrelationships among Employee Participation, Individual Differences, Goal Difficulty, Goal Acceptance, Goal Instrumentality, and Performance.

    ERIC Educational Resources Information Center

    Yukl, Gary A.; Latham, Gary P.

    1978-01-01

    Discussed is a model for goal setting, which is based on Locke's theory that difficult but clear and specific goals, if accepted, will result in higher performance than easy goals, nonspecific goals, or no goals at all. (Author/RK)

  6. NIFFTE Overview and Goals

    NASA Astrophysics Data System (ADS)

    Stewart, Scott

    2008-10-01

    The Neutron Induced Fission Fragment Tracking Experiment (NIFFTE) will make fission cross section measurements for next generation nuclear reactors using a Time Projection Chamber (TPC). Collaborating institutions are Lawrence Livermore National Laboratory, Los Alamos National Laboratory, Idaho National Laboratory, Georgia Institute of Technology, Abilene Christian University, Oregon State University, Cal Poly San Luis Obispo, Colorado School of Mines, and Ohio University. It is funded under the Global Nuclear Energy Partnership (GNEP) in order to increase the precision needed for the design of a new generation of fast neutron reactors. The TPC is a new tool to improve the existing measurements that used fission chambers. The TPC will allow an overall view of the fission event and will distinguish it from background processes; primarily alpha decay. The experiments are planned at the Los Alamos Neutron Scattering Center (LANSCE) utilizing neutron beams from 10 keV to 10 MeV where existing fission cross sections have typical uncertainties of 5%.

  7. Science Goals to Requirements

    NASA Technical Reports Server (NTRS)

    Reuter, Dennis

    2015-01-01

    The presentation will be given at the 26th Annual Thermal Fluids Analysis Workshop (TFAWS 2015) hosted by the Goddard SpaceFlight Center (GSFC) Thermal Engineering Branch (Code 545): This short course will present the science goals for a variety of types of imaging and spectral measurements, the thermal requirements that these goals impose on the instruments designed to obtain the measurements, and some of the types of trades that can be made among instrument subsystems to ensure the required performance is maintained. Examples of thermal system evolution from initial concept to final implementation will be given for several actual systems.

  8. A program toward a fusion reactor

    NASA Astrophysics Data System (ADS)

    Rebut, P.-H.; Watkins, M. L.; Gambier, D. J.; Boucher, D.

    1991-08-01

    Near breakeven conditions have been attained in the JET tokamak [Fusion Technol. 11, 13 (1987)], with beryllium as the first-wall material. A fusion triple product (nDτETi) of 8-9×1020 m-3 sec keV has been reached (within a factor of 8 of that required in a fusion reactor). However, this has only been achieved transiently. At high heating powers, an influx of impurities still limits the achievement of better performance and steady-state operation. In parallel, an improved quantitative understanding of fusion plasmas has emerged from the development of a particular plasma model. Good quantitative agreement is obtained between the model and JET data. The main predictions are also consistent with statistical scaling laws. With such a model, a predictive capability begins to emerge to define the parameters and operating conditions of a DEMO, including impurity levels. Present experimental results and model predictions suggest that impurity dilution is a major threat to a reactor. A divertor concept must be developed further to ensure impurity control before a DEMO can be constructed. A New Phase for JET is planned in which an axisymmetric pumped divertor configuration will be used to address the problems of impurity control, plasma fueling, and helium ash exhaust. It should demonstrate a concept of impurity control and the operational domain for such a device. A single Next Step facility (ITER) is a high risk strategy in terms of physics, technology, and management, since it does not provide a sufficiently sound foundation for a DEMO. A Next Step program is proposed, which could comprise several complementary facilities, each optimized with respect to specific clear objectives. In a minimum program, there could be two Next Step tokamaks, and a Materials Test Facility. Such a program would allow division of effort and sharing of risk across the various scientific and technical problems, permit cross comparison, and ensure continuity of results. It could even be

  9. Materialistic Values and Goals.

    PubMed

    Kasser, Tim

    2016-01-01

    Materialism comprises a set of values and goals focused on wealth, possessions, image, and status. These aims are a fundamental aspect of the human value/goal system, standing in relative conflict with aims concerning the well-being of others, as well as one's own personal and spiritual growth. Substantial evidence shows that people who place a relatively high priority on materialistic values/goals consume more products and incur more debt, have lower-quality interpersonal relationships, act in more ecologically destructive ways, have adverse work and educational motivation, and report lower personal and physical well-being. Experimentally activating materialistic aims causes similar outcomes. Given these ills, researchers have investigated means of decreasing people's materialism. Successful interventions encourage intrinsic/self-transcendent values/goals, increase felt personal security, and/or block materialistic messages from the environment. These interventions would likely be more effective if policies were also adopted that diminished contemporary culture's focus on consumption, profit, and economic growth. PMID:26273896

  10. Reaching Your Fitness Goals

    MedlinePlus

    Everyday Fitness Ideas from the National Institute on Aging at NIH www.nia.nih.gov/Go4Life Reaching Your Fitness Goals You’ll begin to see results in ... longer, and more easily. As you increase your fitness level, you also might find that you need ...

  11. RTT Goals Challenge Recipients

    ERIC Educational Resources Information Center

    McNeil, Michele

    2011-01-01

    Ambitious student-achievement targets turn up the heat, as winners of the $4 billion federal grant effort push to deliver. Winners of the $4 billion Race to the Top jackpot committed to grand goals in using the federal grants to raise student achievement, as measured by higher test scores, narrowed achievement gaps, and increased graduation and…

  12. Exploring Goals. Career Guidance.

    ERIC Educational Resources Information Center

    Mesa Public Schools, AZ.

    Materials contained in this career guidance unit are designed to enable senior high school students to relate their abilities scores from the Developed Abilities Performance (DAP) instrument to actual vocational areas and Long Range [occupational] Goals (LRG) for later indepth study. The length of the unit is six 55-minute periods. Instructional…

  13. Mathematics: Common Curriculum Goals.

    ERIC Educational Resources Information Center

    Oregon State Dept. of Education, Salem.

    This document defines what are considered to be the essentials in a strong mathematics program for the state of Oregon for grades K-12. The common curriculum goals are organized into nine content strands: (1) number and numeration; (2) appropriate computational skills; (3) problem solving; (4) geometry and visualization skills; (5) measurement;…

  14. Archimede solar energy molten salt parabolic trough demo plant: Improvements and second year of operation

    NASA Astrophysics Data System (ADS)

    Maccari, Augusto; Donnola, Sandro; Matino, Francesca; Tamano, Shiro

    2016-05-01

    Since July 2013, the first stand-alone Molten Salt Parabolic Trough (MSPT) demo plant, which was built in collaboration with Archimede Solar Energy and Chiyoda Corporation, is in operation, located adjacent to the Archimede Solar Energy (ASE) manufacturing plant in Massa Martana (Italy). During the two year's operating time frame, the management of the demo plant has shown that MSPT technology is a suitable and reliable option. Several O&M procedures and tests have been performed, as Heat Loss and Minimum Flow Test, with remarkable results confirming that this technology is ready to be extended to standard size CSP plant, if the plant design takes into account molten salt peculiarities. Additionally, the plant has been equipped on fall 2014 with a Steam Generator system by Chiyoda Corporation, in order to test even this important MSPT plant subsystem and to extend the solar field active time, overcoming the previous lack of an adequate thermal load. Here, a description of the plant improvements and the overall plant operation figures will be presented.

  15. Endogenising demographic variables in demo-economic models: the Bachue experience.

    PubMed

    Wery, R; Rodgers, G

    1980-01-01

    The attempt is made in this discussion to describe and draw lessons from the treatment of behavioral demographic variables in the Bachue demo-economic models constructed for the Philippines, Kenya, Brazil and Yugoslavia. Focus is on certain theoretical, technical and practical problems encountered in inserting demographic variables in the system as a whole; how they have been measured in the various applications of the Bachue models, how they are behaviorally explained and linked to the other elements in the system, the data sources used, and some issues of econometric estimates and modelling. 8 issues are dealt with: population accounting and lag structure; fertility; mortality; migration; nuptiality; household formation; schooling; and labor force participation. In each case model structure, dependent and explanatory variables, and empirical strategy are discussed. Summary tables compare the approaches of the different models. The specifics of each country situation rule out the identification of the best solution. Some suggestions regarding more promising approaches are included with respect to choice of variables and the estimation of behavioral models. The endogenous nature of certain demographic elements of a demo-economic model are clear, but construction of the Bachue models has shown that there are no exact rules valid for all cases. There is considerable variety in the way characteristics of the population have been represented in the various applications. PMID:12262480

  16. Integrated modelling of DEMO-FNS current ramp-up scenario and steady-state regime

    NASA Astrophysics Data System (ADS)

    Dnestrovskij, A. Yu.; Kuteev, B. V.; Bykov, A. S.; Ivanov, A. A.; Lukash, V. E.; Medvedev, S. Yu.; Sergeev, V. Yu.; Sychugov, D. Yu.; Khayrutdinov, R. R.

    2015-06-01

    An approach to the integrated modelling of plasma regimes in the projected neutron source DEMO-FNS based on different codes is developed. The consistency check of the steady-state regime is carried out, namely, the possibility of the plasma current ramp-up, acceptance of growth rates of MHD modes in the steady-state regime, heat loads to the wall and divertor plates and neutron yield value. The following codes are employed for the integrated modelling. ASTRA transport code for calculation of plasma parameters in the steady-state regime, NUBEAM Monte Carlo code for NBI incorporated into the ASTRA code, DINA free boundary equilibrium and evolution code, SPIDER free boundary equilibrium and equilibrium reconstruction code, KINX ideal MHD stability code, TOKSTAB rigid shift vertical stability code, edge and divertor plasma B2SOLPS5.2 code and Semi-analytic Hybrid Model (SHM) code for self-consistent description of the core, edge and divertor plasmas based on the experimental scaling laws. The consistent steady-state regime for the DEMO-FNS plasma and the plasma current ramp-up scenario are developed using the integrated modelling approach. Passive copper coils are suggested to reduce the plasma vertical instability growth rate to below ˜30 s-1.The outer divertor operation in the ‘high-recycling’ regime is numerically demonstrated with a maximal heat flux density of 7-9 MW m-2 that is technically acceptable.

  17. Self-Image Goals and Compassionate Goals: Costs and Benefits

    PubMed Central

    Crocker, Jennifer; Olivier, Marc-Andre; Nuer, Noah

    2010-01-01

    Two types of interpersonal goals—self-image goals and compassionate goals—reflect distinct motivational perspectives on the relationship between the self and others—egosystem and ecosystem perspectives, respectively. Research on the associations of self-image goals and compassionate goals with students’ experiences in their first semester of college is described. Chronic self-image goals and compassionate goals predict changes in learning and achievement goals, self-regulation and goal progress, social support and friendships, emotions, and symptoms of anxiety and depression. Self-image goals have costs for belonging, and compassionate goals have benefits for belonging. PMID:21218194

  18. The Role of Goal Attainment Expectancies in Achievement Goal Pursuit

    ERIC Educational Resources Information Center

    Senko, Corwin; Hulleman, Chris S.

    2013-01-01

    The current studies introduce the goal attainment expectancy construct to achievement goal theory. Three studies, 2 in college classrooms and the other using a novel math task in the laboratory, converged on the same finding. For mastery-approach goals and performance-approach goals alike, the harder the goal appeared to attain, the less likely…

  19. People Demos.

    ERIC Educational Resources Information Center

    Chiaverina, Chris; Hicks, Jim

    1983-01-01

    Describes demonstrations in which individuals participate in activities to illustrate physics concepts. No equipment other than the individuals participating is required. Demonstrations are provided for the topics of gas laws, thermodynamics, wave phenomena, optics, acoustics, kinematics, and dynamics. (JN)

  20. Dynamic Demos.

    ERIC Educational Resources Information Center

    Sae, Andy S. W.

    1991-01-01

    Discusses 27 chemical demonstrations involving inexpensive, readily available materials that illustrate the following concepts: acid/base properties, gas properties, characteristics of carbon dioxide, chemiluminescence, freezing point depression, heat of vaporization; density, polymers, surface tension, polarity/nonpolarity, UV absorption,…

  1. GMUGLE: A goal lattice constructor

    NASA Astrophysics Data System (ADS)

    Hintz, Kenneth J.

    2001-08-01

    Goal lattices are a method for ordering the goals of a system and associating with each goal the value of performing that goal in terms of how much it contributes to the accomplishment of the topmost goal of a system. This paper presents a progress report on the development of a web-based implementation of the George Mason University Goal Lattice Engine (GMUGLE). GMUGLE allows a user to interactively create goal lattices, add/delete goals, and specify their ordering relations through a web-based interface. The database portion automatically computes the GLB and LUB of pairs of goals which have been entered to form them into a lattice. Yet to be implemented is the code to input goal values, automatically apportion the values among included goals, and accrue value among the included goals.

  2. DeMO: An Ontology for Discrete-event Modeling and Simulation

    PubMed Central

    Silver, Gregory A; Miller, John A; Hybinette, Maria; Baramidze, Gregory; York, William S

    2011-01-01

    Several fields have created ontologies for their subdomains. For example, the biological sciences have developed extensive ontologies such as the Gene Ontology, which is considered a great success. Ontologies could provide similar advantages to the Modeling and Simulation community. They provide a way to establish common vocabularies and capture knowledge about a particular domain with community-wide agreement. Ontologies can support significantly improved (semantic) search and browsing, integration of heterogeneous information sources, and improved knowledge discovery capabilities. This paper discusses the design and development of an ontology for Modeling and Simulation called the Discrete-event Modeling Ontology (DeMO), and it presents prototype applications that demonstrate various uses and benefits that such an ontology may provide to the Modeling and Simulation community. PMID:22919114

  3. Evaluation of Demo 1C composite flywheel rotor burst test and containment design

    SciTech Connect

    Kass, M.D.; McKeever, J.W.; Akerman, M.A.; Goranson, P.L.; Litherland, P.S.; O`Kain, D.U.

    1998-07-01

    Laboratory-Directed funds were provided in FY 1995 for research to develop flywheel containment specifications and to consider concepts that could satisfy these specifications and produce a prototype small, lightweight, inexpensive, mobile flywheel containment. Research activities have included an analytical and pictorial review of the Demo 1C flywheel failure test, which provided significant insight about radial and axial failure modes; calculations of the thickness of ultra-conservative pressure vessel containment; entertainment of advanced containment concepts using lightweight materials and armor literature; consideration of fabrication assembly procedures; and participation in a Flywheel Energy Storage Workshop during which additional flywheel failure experiences were discussed. Based on these activities, calculations, and results, a list of conclusions concerning flywheel containment and its relation to the flywheel are presented followed by recommendations for further research.

  4. Development of advanced tritium breeders and neutron multipliers for DEMO solid breeder blankets

    NASA Astrophysics Data System (ADS)

    Tsuchiya, K.; Hoshino, T.; Kawamura, H.; Mishima, Y.; Yoshida, N.; Terai, T.; Tanaka, S.; Munakata, K.; Kato, S.; Uchida, M.; Nakamichi, M.; Yamada, H.; Yamaki, D.; Hayashi, K.

    2007-09-01

    In efforts to develop advanced tritium breeders, the effects of additives to lithium titanate (Li2TiO3) have been investigated, and good prospects have been obtained by using oxide additives such as TiO2, CaO and Li2O. As for the neutron multiplier, the development of a real-size electrode fabrication technique and the characterization of beryllium-based intermetallic compounds such as Be-Ti and Be-V have been performed. Properties of Be-Ti alloys have been found to be better than those of beryllium metal. In particular, steam interaction of a Be-Ti alloy was about 1/1000 as small as that of beryllium metal. These activities have led to bright prospects for the realization of the water-cooled DEMO breeder blanket by application of these advanced materials.

  5. Operation and first results of the NEXT-DEMO prototype using a silicon photomultiplier tracking array

    NASA Astrophysics Data System (ADS)

    Álvarez, V.; Borges, F. I. G.; Cárcel, S.; Castel, J.; Cebrián, S.; Cervera, A.; Conde, C. A. N.; Dafni, T.; Dias, T. H. V. T.; Díaz, J.; Egorov, M.; Esteve, R.; Evtoukhovitch, P.; Fernandes, L. M. P.; Ferrario, P.; Ferreira, A. L.; Freitas, E. D. C.; Gehman, V. M.; Gil, A.; Goldschmidt, A.; Gómez, H.; Gómez-Cadenas, J. J.; González-Díaz, D.; Gutiérrez, R. M.; Hauptman, J.; Hernando Morata, J. A.; Herrera, D. C.; Iguaz, F. J.; Irastorza, I. G.; Jinete, M. A.; Labarga, L.; Laing, A.; Liubarsky, I.; Lopes, J. A. M.; Lorca, D.; Losada, M.; Luzón, G.; Marí, A.; Martín-Albo, J.; Martínez, A.; Martínez, G.; Miller, T.; Moiseenko, A.; Monrabal, F.; Monserrate, M.; Monteiro, C. M. B.; Mora, F. J.; Moutinho, L. M.; Muñoz Vidal, J.; Natal da Luz, H.; Navarro, G.; Nebot-Guinot, M.; Nygren, D.; Oliveira, C. A. B.; Palma, R.; Pérez, J.; Pérez Aparicio, J. L.; Renner, J.; Ripoll, L.; Rodríguez, A.; Rodríguez, J.; Santos, F. P.; dos Santos, J. M. F.; Seguí, L.; Serra, L.; Shuman, D.; Simón, A.; Sofka, C.; Sorel, M.; Toledo, J. F.; Tomás, A.; Torrent, J.; Tsamalaidze, Z.; Veloso, J. F. C. A.; Villar, J. A.; Webb, R.; White, J. T.; Yahlali, N.

    2013-09-01

    NEXT-DEMO is a high-pressure xenon gas TPC which acts as a technological test-bed and demonstrator for the NEXT-100 neutrinoless double beta decay experiment. In its current configuration the apparatus fully implements the NEXT-100 design concept. This is an asymmetric TPC, with an energy plane made of photomultipliers and a tracking plane made of silicon photomultipliers (SiPM) coated with TPB. The detector in this new configuration has been used to reconstruct the characteristic signature of electrons in dense gas, demonstrating the ability to identify the MIP and ``blob'' regions. Moreover, the SiPM tracking plane allows for the definition of a large fiducial region in which an excellent energy resolution of 1.82% FWHM at 511 keV has been measured (a value which extrapolates to 0.83% at the xenon Qββ).

  6. Transient Mirror Heating Theory and Experiment in the Jefferson Lab IR Demo FEL

    SciTech Connect

    Benson, S.; Michelle D. Shinn.; Neil, G.R.

    2001-01-01

    During commissioning of the IR Demo FEL at Jefferson Lab, we noticed that the FEL exhibited a rapid power drop with time when the first set of 3 mu-m mirrors was used. Thought the rate of power drop was unexpected, it was thought that it could be due to a distortion of the mirrors during a time short compared to a the thermal diffusion time. This transient distortion might affect the laser more than the steady state distortion. This paper presents some analysis of the transient mirror heating problem and some recent experimental results using different mirror substrates and coatings. It is found that the behavior of the first mirror set cannot be reconciled with the observed power fall-off if a linear absorption is assumed. The power drop in more recent experiments is consistent with linear thermal analysis. No anomalous transient effects are seen.

  7. CBM with Goal Setting: Impacting Students' Understanding of Reading Goals

    ERIC Educational Resources Information Center

    Swain, Kristine D.

    2005-01-01

    This pilot study investigated if goal setting with curriculum-based measurement (CBM) was effective in increasing student awareness of goal knowledge and if students could set realistic daily reading goals. Nineteen 6th and 7th grade students with learning disabilities participated in a goal setting treatment group or a control group. During the…

  8. Potential-Based Achievement Goals

    ERIC Educational Resources Information Center

    Elliot, Andrew; Murayama, Kou; Kobeisy, Ahmed; Lichtenfeld, Stephanie

    2015-01-01

    Background: Self-based achievement goals use one's own intrapersonal trajectory as a standard of evaluation, and this intrapersonal trajectory may be grounded in one's past (past-based goals) or one's future potential (potential-based goals). Potential-based goals have been overlooked in the literature to date. Aims: The primary aim of the present…

  9. A RE-LOOK AT THE US NRC SAFETY GOALS

    SciTech Connect

    mubayi v.

    2013-09-22

    Since they were adopted in 1986, the US NRC’s Safety Goals have played a valuable role as a de facto risk acceptance criterion against which the predicted performance of a commercial nuclear power reactor can be evaluated and assessed. The current safety goals are cast in terms of risk metrics called quantitative health objectives (QHOs), limiting numerical values of the risks of the early and latent health effects of accidental releases of radioactivity to the offsite population. However, while demonstrating compliance with current safety goals has been an important step in assessing the acceptance of the risk posed by LWRs, new or somewhat different goals may be needed that go beyond the current early fatality and latent cancer fatality QHOs in assessing reactor risk. Natural phenomena such as hurricanes seem to be suitable candidates for establishing a background rate to derive a risk goal as their order of magnitude cost of damages is similar to those estimated in severe accident Level 3 PRAs done for nuclear power plants. This paper obtains a risk goal that could have a wider applicability, compared to the current QHOs, as a technology-neutral goal applicable to future reactors and multi-unit sites.

  10. The Evaluation of Goal and Goal-Free Training Innovation.

    ERIC Educational Resources Information Center

    James, Carl; Roffe, Ian

    2000-01-01

    Goal-based training has specific, predetermined objectives, whereas goal-free training involves implementation of innovations whose outcomes cannot be predicted. Evaluation of goal-free training must consider clients' requirements, the effectiveness of the initiative, and application of feedback. (SK)

  11. Goal Contents and Goal Contexts: Experiments with Chinese Students

    ERIC Educational Resources Information Center

    Wang, Ze; Hu, Xiao Yong; Guo, Yong Yu

    2013-01-01

    Using samples of Chinese middle school students, the 2 experimental studies presented here examined the effects of goal content and goal context on test performance, free-choice engagement, and test anxiety within the framework of self-determination theory. Students' learning goals were induced as intrinsic or extrinsic with the learning…

  12. Punishment goals of crime victims.

    PubMed

    Orth, Uli

    2003-04-01

    Research on subjective punishment goals has focused on the perspective of third-party observers of criminal offenses and neglected the perspective of victims. This study investigates punishment goals among 174 adult crime victims (rape and nonsexual assault) for each participant's real criminal case. Scales measuring support for punishment goals are constructed by factor analysis of an 18-item list. Results show that 5 highly supported goals can be distinguished: retaliation, recognition of victim status, confirmation of societal values, victim security, and societal security. Analysis of relations between punishment goal scales and personal variables, situational variables, and demanded punishment severity corroborates the view that the punishment goals revealed can be classified according to the two independent dichotomies of moral versus instrumental goals, and micro versus macro goals. PMID:12733420

  13. Dynamic Emulation Modelling (DEMo) of large physically-based environmental models

    NASA Astrophysics Data System (ADS)

    Galelli, S.; Castelletti, A.

    2012-12-01

    In environmental modelling large, spatially-distributed, physically-based models are widely adopted to describe the dynamics of physical, social and economic processes. Such an accurate process characterization comes, however, to a price: the computational requirements of these models are considerably high and prevent their use in any problem requiring hundreds or thousands of model runs to be satisfactory solved. Typical examples include optimal planning and management, data assimilation, inverse modelling and sensitivity analysis. An effective approach to overcome this limitation is to perform a top-down reduction of the physically-based model by identifying a simplified, computationally efficient emulator, constructed from and then used in place of the original model in highly resource-demanding tasks. The underlying idea is that not all the process details in the original model are equally important and relevant to the dynamics of the outputs of interest for the type of problem considered. Emulation modelling has been successfully applied in many environmental applications, however most of the literature considers non-dynamic emulators (e.g. metamodels, response surfaces and surrogate models), where the original dynamical model is reduced to a static map between input and the output of interest. In this study we focus on Dynamic Emulation Modelling (DEMo), a methodological approach that preserves the dynamic nature of the original physically-based model, with consequent advantages in a wide variety of problem areas. In particular, we propose a new data-driven DEMo approach that combines the many advantages of data-driven modelling in representing complex, non-linear relationships, but preserves the state-space representation typical of process-based models, which is both particularly effective in some applications (e.g. optimal management and data assimilation) and facilitates the ex-post physical interpretation of the emulator structure, thus enhancing the

  14. Effectively Using IEP Goal Banks

    ERIC Educational Resources Information Center

    Kowalski, Ellen; McCall, Renee; Aiello, Rocco; Lieberman, Lauren

    2009-01-01

    For students with disabilities, annual goals are the nuts and bolts of the everyday program outlined in their individualized education program (IEP). According to the Individuals with Disabilities Education Improvement Act (IDEA) of 2004, a present level of performance with measurable annual goals must be outlined in a student's IEP. Goals should…

  15. Simultaneous saccharification and co-fermentation for bioethanol production using corncobs at lab, PDU and demo scales

    PubMed Central

    2013-01-01

    Background While simultaneous saccharification and co-fermentation (SSCF) is considered to be a promising process for bioconversion of lignocellulosic materials to ethanol, there are still relatively little demo-plant data and operating experiences reported in the literature. In the current work, we designed a SSCF process and scaled up from lab to demo scale reaching 4% (w/v) ethanol using xylose rich corncobs. Results Seven different recombinant xylose utilizing Saccharomyces cerevisiae strains were evaluated for their fermentation performance in hydrolysates of steam pretreated corncobs. Two strains, RHD-15 and KE6-12 with highest ethanol yield and lowest xylitol yield, respectively were further screened in SSCF using the whole slurry from pretreatment. Similar ethanol yields were reached with both strains, however, KE6-12 was chosen as the preferred strain since it produced 26% lower xylitol from consumed xylose compared to RHD-15. Model SSCF experiments with glucose or hydrolysate feed in combination with prefermentation resulted in 79% of xylose consumption and more than 75% of the theoretical ethanol yield on available glucose and xylose in lab and PDU scales. The results suggest that for an efficient xylose conversion to ethanol controlled release of glucose from enzymatic hydrolysis and low levels of glucose concentration must be maintained throughout the SSCF. Fed-batch SSCF in PDU with addition of enzymes at three different time points facilitated controlled release of glucose and hence co-consumption of glucose and xylose was observed yielding 76% of the theoretical ethanol yield on available glucose and xylose at 7.9% water insoluble solids (WIS). With a fed-batch SSCF in combination with prefermentation and a feed of substrate and enzymes 47 and 40 g l-1 of ethanol corresponding to 68% and 58% of the theoretical ethanol yield on available glucose and xylose were produced at 10.5% WIS in PDU and demo scale, respectively. The strain KE6-12 was able to

  16. Establishing Physical and Engineering Science Base to Bridge from ITER to Demo

    NASA Astrophysics Data System (ADS)

    Peng, Y.-K. Martin; Abdou, M.; Gates, D.; Hegna, C.; Hill, D.; Najmabadi, F.; Navratil, G.; Parker, R.

    2007-11-01

    A Nuclear Component Testing (NCT) Discussion Group emerged recently to clarify how ``a lowered-risk, reduced-cost approach can provide a progressive fusion environment beyond the ITER level to explore, discover, and help establish the remaining, critically needed physical and engineering sciences knowledge base for Demo.'' The group, assuming success of ITER and other contemporary projects, identified critical ``gap-filling'' investigations: plasma startup, tritium self-sufficiency, plasma facing surface performance and maintainability, first wall/blanket/divertor materials defect control and lifetime management, and remote handling. Only standard or spherical tokamak plasma conditions below the advanced regime are assumed to lower the anticipated physics risk to continuous operation (˜2 weeks). Modular designs and remote handling capabilities are included to mitigate the risk of component failure and ease replacement. Aspect ratio should be varied to lower the cost, accounting for the contending physics risks and the near-term R&D. Cost and time-effective staging from H-H, D-D, to D-T will also be considered. *Work supported by USDOE.

  17. Characterisation of NEXT-DEMO using xenon Kα X-rays

    NASA Astrophysics Data System (ADS)

    Lorca, D.; Martín-Albo, J.; Laing, A.; Ferrario, P.; Gómez-Cadenas, J. J.; Álvarez, V.; Borges, F. I. G.; Camargo, M.; Cárcel, S.; Cebrián, S.; Cervera, A.; Conde, C. A. N.; Dafni, T.; Díaz, J.; Esteve, R.; Fernandes, L. M. P.; Ferreira, A. L.; Freitas, E. D. C.; Gehman, V. M.; Goldschmidt, A.; Gómez, H.; González-Díaz, D.; Gutiérrez, R. M.; Hauptman, J.; Hernando Morata, J. A.; Herrera, D. C.; Irastorza, I. G.; Labarga, L.; Liubarsky, I.; Losada, M.; Luzón, G.; Marí, A.; Martínez-Lema, G.; Martínez, A.; Miller, T.; Monrabal, F.; Monserrate, M.; Monteiro, C. M. B.; Mora, F. J.; Moutinho, L. M.; Muñoz Vidal, J.; Nebot-Guinot, M.; Nygren, D.; Oliveira, C. A. B.; Pérez, J.; Pérez Aparicio, J. L.; Renner, J.; Ripoll, L.; Rodríguez, A.; Rodríguez, J.; Santos, F. P.; dos Santos, J. M. F.; Seguí, L.; Serra, L.; Shuman, D.; Simón, A.; Sofka, C.; Sorel, M.; Toledo, J. F.; Torrent, J.; Tsamalaidze, Z.; Veloso, J. F. C. A.; Webb, R.; White, J. T.; Yahlali, N.

    2014-10-01

    The NEXT experiment aims to observe the neutrinoless double beta decay of 136Xe in a high-pressure xenon gas TPC using electroluminescence (EL) to amplify the signal from ionization. Understanding the response of the detector is imperative in achieving a consistent and well understood energy measurement. The abundance of xenon K-shell X-ray emission during data taking has been identified as a multitool for the characterisation of the fundamental parameters of the gas as well as the equalisation of the response of the detector. The NEXT-DEMO prototype is a ~ 1.5 kg volume TPC filled with natural xenon. It employs an array of 19 PMTs as an energy plane and of 256 SiPMs as a tracking plane with the TPC light tube and SiPM surfaces being coated with tetraphenyl butadiene (TPB) which acts as a wavelength shifter for the VUV scintillation light produced by xenon. This paper presents the measurement of the properties of the drift of electrons in the TPC, the effects of the EL production region, and the extraction of position dependent correction constants using Kα X-ray deposits. These constants were used to equalise the response of the detector to deposits left by gammas from 22Na.

  18. Conceptual design of divertor and first wall for DEMO-FNS

    NASA Astrophysics Data System (ADS)

    Sergeev, V. Yu.; Kuteev, B. V.; Bykov, A. S.; Gervash, A. A.; Glazunov, D. A.; Goncharov, P. R.; Dnestrovskij, A. Yu.; Khayrutdinov, R. R.; Klishchenko, A. V.; Lukash, V. E.; Mazul, I. V.; Molchanov, P. A.; Petrov, V. S.; Rozhansky, V. A.; Shpanskiy, Yu. S.; Sivak, A. B.; Skokov, V. G.; Spitsyn, A. V.

    2015-11-01

    Key issues of design of the divertor and the first wall of DEMO-FNS are presented. A double null closed magnetic configuration was chosen with long external legs and V-shaped corners. The divertor employs a cassette design similar to that of ITER. Water-cooled first wall of the tokamak is made of Be tiles and CuCrZr-stainless steel shells. Lithium injection and circulation technologies are foreseen for protection of plasma facing components. Simulations of thermal loads onto the first wall and divertor plates suggest a possibility to distribute heat loads making them less than 10 MW m-2. Evaluations of sputtering and evaporation of plasma-facing materials suggest that lithium may protect the first wall. To prevent Be erosion at the outer divertor plates either the full detached divertor operation or arrangement of the renewal lithium flow on targets should be implemented. Test bed experiments on the Tsefey-M facility with the first wall mockup coated by Ве tiles and cooled by water are presented. The temperature of the surface of tiles reached 280-300 °С at 5 MW m-2 and 600-650 °С at 10.5 MW m-2. The mockup successfully withstood 1000 cycles with the lower thermal loading and 100 cycles with higher thermal loading.

  19. Participation as Post-Fordist Politics: Demos, New Labour, and Science Policy

    PubMed Central

    2010-01-01

    In recent years, British science policy has seen a significant shift ‘from deficit to dialogue’ in conceptualizing the relationship between science and the public. Academics in the interdisciplinary field of Science and Technology Studies (STS) have been influential as advocates of the new public engagement agenda. However, this participatory agenda has deeper roots in the political ideology of the Third Way. A framing of participation as a politics suited to post-Fordist conditions was put forward in the magazine Marxism Today in the late 1980s, developed in the Demos thinktank in the 1990s, and influenced policy of the New Labour government. The encouragement of public participation and deliberation in relation to science and technology has been part of a broader implementation of participatory mechanisms under New Labour. This participatory program has been explicitly oriented toward producing forms of social consciousness and activity seen as essential to a viable knowledge economy and consumer society. STS arguments for public engagement in science have gained influence insofar as they have intersected with the Third Way politics of post-Fordism. PMID:21258426

  20. European ceramic B.I.T. blanket for DEMO: Recent development for the zirconate version

    SciTech Connect

    Bielak, B.; Eid, M.; Fuetterer, M.

    1994-12-31

    Within the framework of the European test-blanket program, CEA and ENEA are jointly developing a DEMO-relevant, helium-cooled, Breeder-Inside-Tube (BIT) ceramic blanket. Two ceramics are possible breeder material candidate: LiAlO{sub 2} and Li{sub 2}ZrO{sub 3}. Despite the design has been originally developed for aluminate, the CEA has recently focused its work on zirconate. This concept blanket segments are made by a directly-cooled vacuum-tight steel box which contains banana-shaped poloidal breeder modules arranged in rows (6 rows in an outboard segment and 4 rows in an inboard one). A breeder module consists of a pressure vessel containing a bundle of breeder rods surrounded by baffles. Each one of the rods is made-up of a steel tube containing a stack of annular pellets of sintered lithium-zirconate, through which flows helium (the tritium purge gas). The thermo-mechanical analysis has shown that the thermal gradient in the ceramics can be kept at acceptable levels despite the poorer out-of-pile thermo-mechanical properties of zirconate compared to aluminate. Moreover, the neutronic analysis has shown that, besides the maintained tritium-breeding self-sufficiency capability of this blanket, the lower lithium burn-up could be an indication that the zirconate characteristics remains more stable after long term irradiation (i.e., close to the end-of-life fluence of 5 MWa/m{sup 2}).

  1. The role of risk management in the design of diagnostics for fusion reactors

    NASA Astrophysics Data System (ADS)

    Ingesson, L. C.; F4E Diagnostic Project Team

    2014-08-01

    A project-oriented approach is beneficial for the selection and design of viable diagnostics for fusion reactors because of the associated complex physical and organizational environment. The project-oriented approach includes rigorous risk management. The nature and impact of risks related to technical, organizational and commercial aspects in relation to the development of ITER diagnostics under EU responsibility are analyzed. The majority of risks are related to organizational aspects and technical feasibility issues. The experience with ITER is extrapolated to DEMO and beyond. It should not be taken for granted that technical solutions will be found, while a risk analysis of various diagnostic techniques with quantitative assessments undertaken early in the design of DEMO would be beneficial.

  2. The role of risk management in the design of diagnostics for fusion reactors

    SciTech Connect

    Ingesson, L. C.; Collaboration: F4E Diagnostic Project Team

    2014-08-21

    A project-oriented approach is beneficial for the selection and design of viable diagnostics for fusion reactors because of the associated complex physical and organizational environment. The project-oriented approach includes rigorous risk management. The nature and impact of risks related to technical, organizational and commercial aspects in relation to the development of ITER diagnostics under EU responsibility are analyzed. The majority of risks are related to organizational aspects and technical feasibility issues. The experience with ITER is extrapolated to DEMO and beyond. It should not be taken for granted that technical solutions will be found, while a risk analysis of various diagnostic techniques with quantitative assessments undertaken early in the design of DEMO would be beneficial.

  3. Achieving the Goals. Goal 4: Teacher Education and Professional Development.

    ERIC Educational Resources Information Center

    Department of Education, Washington, DC.

    Goal 4 of the National Education Goals envisions that teachers will have access to programs for the continued improvement of their professional skills. This book examines what federal agencies are doing to enhance teacher preparation, presents information on career-long development, and offers program descriptions and contact names. The first…

  4. Goal!

    ERIC Educational Resources Information Center

    Pauls, Anthony

    2007-01-01

    In this article, the author shares the story of his son, Joshua Pauls. Josh is an energetic young man who learned at a very young age not to let anything stop him from achieving his dreams. Born with a birth defect known as bilateral bibia hemimelia, which means he was born without his tibia bone in both of his legs, Josh was only 10 months old…

  5. Goals.

    ERIC Educational Resources Information Center

    Phillips, David A., Ed.; Phillips, Prudence, Ed.

    1987-01-01

    Presented are two brief articles related to teaching the history of chemistry in college chemistry, "Utilizing a Historical Perspective in the Teaching of Chemistry" (Joseph W. Kamsar), and "History of Chemistry" (George B. Kauffman). (RH)

  6. Goal Setting to Achieve Results

    ERIC Educational Resources Information Center

    Newman, Rich

    2012-01-01

    Both districts and individual schools have a very clear set of goals and skills for their students to achieve and master. In fact, except in rare cases, districts and schools develop very detailed goals they wish to pursue. In most cases, unfortunately, only the teachers and staff at a particular school or district-level office are aware of the…

  7. Ground Operations Aerospace Language (GOAL)

    NASA Technical Reports Server (NTRS)

    1973-01-01

    GOAL, is a test engineer oriented language designed to be used to standardize procedure terminology and as the test programming language to be used for ground checkout operations in a space vehicle launch environment. The material presented concerning GOAL includes: (1) a historical review, (2) development objectives and requirements, (3) language scope and format, and (4) language capabilities.

  8. What about Those Dietary Goals?

    ERIC Educational Resources Information Center

    Goodman, S. Jane

    1980-01-01

    This elaboration of the Dietary Goals for the United States, set by the U.S. Senate and Select Committee on Nutrition and Human Needs in 1977, details all seven dietary goals and includes a discussion of possible risk factors associated with certain chronic diseases. (JN)

  9. Goals and Personality in Adolescents

    ERIC Educational Resources Information Center

    Sanz de Acedo Lizarraga, M. L.; Ugarte, M. D.; Lumbreras, M. Victoria; Sanz de Acedo Baquedano, M. T.

    2006-01-01

    The purpose of this study was to investigate the influence of personality factors in the value allotted by adolescents to various groups of goals. For this purpose, the "Cuestionario de Personalidad Situacional, CPS" (Situational Personality Questionnaire) and the "Cuestionario de Metas para Adolescentes, CMA" (Goals for Adolescents Questionnaire)…

  10. Theme: Achieving 2020 Goal 4.

    ERIC Educational Resources Information Center

    Agricultural Education Magazine, 2000

    2000-01-01

    This issue focuses on the Reinventing Agricultural Education 2020 Project's goal of partnerships and strategic alliances, which serves as a catalyst to ensure that the other goals are accomplished and sustained. Eleven articles discuss establishing partnerships at local, state, and national levels and balancing old alliances with new connections.…

  11. Assessment of GPS Reflectometry from TechDemoSat-1 for Scatterometry and Altimetry Applications

    NASA Astrophysics Data System (ADS)

    Shah, R.; Hajj, G. A.

    2015-12-01

    The value of GPS reflectometry for scatterometry and altimetry applications has been a topic of investigation for the past two decades. TechDemoSat-1 (TDS-1), a technology demonstration satellite launched in July of 2014, with an instrument to collect GPS reflections from 4 GPS satellites simultaneously, provide the first extensive data that allows for validation and evaluation of GPS reflectometry from space against more established techniques. TDS-1 uses a high gain (~13 dBi) L1 antenna pointing 6 degrees off nadir with a 60ohalf-beam width. Reflected GPS L1 signals are processed into Delay Doppler Maps (DDMs) inside the receiver and made available (through Level-1b) along with metadata describing the bistatic geometry, antenna gain, etc., on a second-by-second basis for each of the 4 GPS tracks recorded at any given time. In this paper we examine level-1b data from TDS-1 for thousands of tracks collected over the span of Jan.-Feb., 2015. This data corresponds to reflections from various types of surfaces throughout the globe including ice, deserts, forests, oceans, lakes, wetlands, etc. Our analysis will consider how the surface type manifests itself in the DDMs (e.g., coherence vs. non-coherence reflection) and derivable physical quantities. We will consider questions regarding footprint resolution, waveform rise time and corresponding bistatic range accuracy, and level of precision for altimetry (sea surface height) and scatterometry (significant wave height and sea surface wind). Tracks from TDS-1 that coincide with Jason-1 or 2 tracks will be analyzed, where the latter can be used as truth for comparison and validation. Where coincidences are found, vertical delay introduced by the media as measured by Jason will be mapped to bistatic propagation path to correct for neutral atmospheric and ionospheric delays.

  12. Space Charge Neutralization of DEMO Relevant Negative Ion Beams at Low Gas Density

    SciTech Connect

    Surrey, Elizabeth; Porton, Michael

    2011-09-26

    The application of neutral beams to future power plant devices (DEMO) is dependent on achieving significantly improved electrical efficiency and the most promising route to achieving this is by implementing a photoneutralizer in place of the traditional gas neutralizer. A corollary of this innovation would be a significant reduction in the background gas density through which the beam is transported between the accelerator and the neutralizer. This background gas is responsible for the space charge neutralization of the beam, enabling distances of several metres to be traversed without significant beam expansion. This work investigates the sensitivity of a D{sup -} beam to reduced levels of space charge compensation for energies from 100 keV to 1.5 MeV, representative of a scaled prototype experiment, commissioning and full energy operation. A beam transport code, following the evolution of the phase space ellipse, is employed to investigate the effect of space charge on the beam optics. This shows that the higher energy beams are insensitive to large degrees of under compensation, unlike the lower energies. The probable degree of compensation at low gas density is then investigated through a simple, two component beam-plasma model that allows the potential to be negative. The degree of under-compensation is dependent on the positive plasma ion energy, one source of which is dissociation of the gas by the beam. The subsequent space charge state of the beam is shown to depend upon the relative times for equilibration of the dissociation energy and ionization by the beam ions.

  13. NEUTRONIC REACTOR

    DOEpatents

    Fermi, E.; Zinn, W.H.; Anderson, H.L.

    1958-09-16

    Means are presenied for increasing the reproduction ratio of a gaphite- moderated neutronic reactor by diminishing the neutron loss due to absorption or capture by gaseous impurities within the reactor. This means comprised of a fluid-tight casing or envelope completely enclosing the reactor and provided with a valve through which the casing, and thereby the reactor, may be evacuated of atmospheric air.

  14. Goals Analysis Procedure Guidelines for Applying the Goals Analysis Process

    NASA Technical Reports Server (NTRS)

    Motley, Albert E., III

    2000-01-01

    One of the key elements to successful project management is the establishment of the "right set of requirements", requirements that reflect the true customer needs and are consistent with the strategic goals and objectives of the participating organizations. A viable set of requirements implies that each individual requirement is a necessary element in satisfying the stated goals and that the entire set of requirements, taken as a whole, is sufficient to satisfy the stated goals. Unfortunately, it is the author's experience that during project formulation phases' many of the Systems Engineering customers do not conduct a rigorous analysis of the goals and objectives that drive the system requirements. As a result, the Systems Engineer is often provided with requirements that are vague, incomplete, and internally inconsistent. To complicate matters, most systems development methodologies assume that the customer provides unambiguous, comprehensive and concise requirements. This paper describes the specific steps of a Goals Analysis process applied by Systems Engineers at the NASA Langley Research Center during the formulation of requirements for research projects. The objective of Goals Analysis is to identify and explore all of the influencing factors that ultimately drive the system's requirements.

  15. Career Goals in Young Adults: Personal Resources, Goal Appraisals, Attitudes, and Goal Management Strategies

    ERIC Educational Resources Information Center

    Haratsis, Jessica M.; Hood, Michelle; Creed, Peter A.

    2015-01-01

    We tested a model based on the dual-process framework that assessed the relationships among personal resources, career goal appraisals, career attitudes, and career goal management, which have not been previously assessed together. The model (tested on a sample of 486 young adults: 74% female, M[subscript]age = 22 years) proposed that personal…

  16. Goal Statements and Goal-Directed Behavior: A Relational Frame Account of Goal Setting in Organizations

    ERIC Educational Resources Information Center

    O'Hora, Denis; Maglieri, Kristen A.

    2006-01-01

    Goal setting has consistently been shown to increase performance under specific conditions. These goal setting effects have previously been explored from both a cognitive perspective and in terms of traditional behavioral concepts. We highlight limitations of these approaches and propose a novel account based on Relational Frame Theory. This…

  17. Science Goal Monitor: Science Goal Driven Automation for NASA Missions

    NASA Technical Reports Server (NTRS)

    Koratkar, Anuradha; Grosvenor, Sandy; Jung, John; Pell, Melissa; Matusow, David; Bailyn, Charles

    2004-01-01

    Infusion of automation technologies into NASA s future missions will be essential because of the need to: (1) effectively handle an exponentially increasing volume of scientific data, (2) successfully meet dynamic, opportunistic scientific goals and objectives, and (3) substantially reduce mission operations staff and costs. While much effort has gone into automating routine spacecraft operations to reduce human workload and hence costs, applying intelligent automation to the science side, i.e., science data acquisition, data analysis and reactions to that data analysis in a timely and still scientifically valid manner, has been relatively under-emphasized. In order to introduce science driven automation in missions, we must be able to: capture and interpret the science goals of observing programs, represent those goals in machine interpretable language; and allow spacecrafts onboard systems to autonomously react to the scientist's goals. In short, we must teach our platforms to dynamically understand, recognize, and react to the scientists goals. The Science Goal Monitor (SGM) project at NASA Goddard Space Flight Center is a prototype software tool being developed to determine the best strategies for implementing science goal driven automation in missions. The tools being developed in SGM improve the ability to monitor and react to the changing status of scientific events. The SGM system enables scientists to specify what to look for and how to react in descriptive rather than technical terms. The system monitors streams of science data to identify occurrences of key events previously specified by the scientist. When an event occurs, the system autonomously coordinates the execution of the scientist s desired reactions. Through SGM, we will improve om understanding about the capabilities needed onboard for success, develop metrics to understand the potential increase in science returns, and develop an operational prototype so that the perceived risks associated

  18. ERDA Recasts Nation's Energy Goals

    ERIC Educational Resources Information Center

    Science News, 1975

    1975-01-01

    Describes five major policy changes of the Energy Research and Development Administration (ERDA), one of which sharply decreased its emphasis on breeder reactors and another which elevated solar-generated electricity to a new high priority as a long-range energy source. (BR)

  19. New Goals for Atomic Energy

    ERIC Educational Resources Information Center

    Parsegian, V. L.

    1971-01-01

    There should be a "shifting of emphasis from fossil fuel to nuclear systems as quickly as possible," but with a major change in the design of reactor systems to enable more efficient use of the total energy produced. Waste heat may be used for agriculture. (AL)

  20. Development of advanced blanket materials for a solid breeder blanket of a fusion reactor

    NASA Astrophysics Data System (ADS)

    Kawamura, H.; Ishitsuka, E.; Tsuchiya, K.; Nakamichi, M.; Uchida, M.; Yamada, H.; Nakamura, K.; Ito, H.; Nakazawa, T.; Takahashi, H.; Tanaka, S.; Yoshida, N.; Kato, S.; Ito, Y.

    2003-08-01

    The design of an advanced solid breeding blanket in a DEMO reactor requires a tritium breeder and a neutron multiplier that can withstand high temperatures and high neutron fluences, and the development of such advanced blanket materials has been carried out by collaboration between JAERI, universities and industries in Japan. The Li2TiO3 pebble fabricated by a wet process is a reference material as a tritium breeder, but its stability at high temperatures has to be improved for its application in a DEMO blanket. One of these improved materials, TiO2-doped Li2TiO3 pebbles, was successfully fabricated and studied. For the advanced neutron multiplier, beryllides that have a high melting point and good chemical stability have been studied. Some characterization of Be12Ti was conducted, and it became clear that it had lower swelling and tritium inventory than beryllium metal. Pebble fabrication study for Be12Ti was also performed and Be12Ti pebbles were successfully fabricated. These activities have shown that there is a bright prospect in realizing a DEMO blanket by the application of TiO2-doped Li2TiO3 and beryllides.

  1. Probabilistic reliability analysis, quantitative safety goals, and nuclear licensing in the United Kingdom.

    PubMed

    Cannell, W

    1987-09-01

    Although unpublicized, the use of quantitative safety goals and probabilistic reliability analysis for licensing nuclear reactors has become a reality in the United Kingdom. This conclusion results from an examination of the process leading to the licensing of the Sizewell B PWR in England. The licensing process for this reactor has substantial implications for nuclear safety standards in Britain, and is examined in the context of the growing trend towards quantitative safety goals in the United States. PMID:3685540

  2. Reading Education: Student Terminal Goals, Program Goals, and Behavioral Objectives.

    ERIC Educational Resources Information Center

    Mesa Public Schools, AZ.

    This pamphlet of behavioral objectives for teachers of elementary school reading instruction was compiled by the Mesa Public School System, Mesa, Arizona. Terminal goals are stated behaviorally for prereading and readiness skills, which include comprehension, interests in letters and books, visual perception, and psychomotor awareness. Terminal…

  3. Science Goal Monitor: science goal driven automation for NASA missions

    NASA Astrophysics Data System (ADS)

    Koratkar, Anuradha; Grosvenor, Sandy; Jung, John; Pell, Melissa; Matusow, David; Bailyn, Charles

    2004-09-01

    Infusion of automation technologies into NASA's future missions will be essential because of the need to: (1) effectively handle an exponentially increasing volume of scientific data, (2) successfully meet dynamic, opportunistic scientific goals and objectives, and (3) substantially reduce mission operations staff and costs. While much effort has gone into automating routine spacecraft operations to reduce human workload and hence costs, applying intelligent automation to the science side, i.e., science data acquisition, data analysis and reactions to that data analysis in a timely and still scientifically valid manner, has been relatively under-emphasized. In order to introduce science driven automation in missions, we must be able to: capture and interpret the science goals of observing programs, represent those goals in machine interpretable language; and allow spacecrafts' onboard systems to autonomously react to the scientist's goals. In short, we must teach our platforms to dynamically understand, recognize, and react to the scientists' goals. The Science Goal Monitor (SGM) project at NASA Goddard Space Flight Center is a prototype software tool being developed to determine the best strategies for implementing science goal driven automation in missions. The tools being developed in SGM improve the ability to monitor and react to the changing status of scientific events. The SGM system enables scientists to specify what to look for and how to react in descriptive rather than technical terms. The system monitors streams of science data to identify occurrences of key events previously specified by the scientist. When an event occurs, the system autonomously coordinates the execution of the scientist's desired reactions. Through SGM, we will improve our understanding about the capabilities needed onboard for success, develop metrics to understand the potential increase in science returns, and develop an "operational" prototype so that the perceived risks

  4. Progress Toward National Aeronautics Goals

    NASA Technical Reports Server (NTRS)

    Russo, Carlo J.; Sehra, Arun K.

    1999-01-01

    NASA has made definitive progress towards achieving several bold U.S. goals in aeronautics related to air breathing engines. The advanced technologies developed towards these goals span applications from general aviation to large subsonic and supersonic aircraft. The proof of successful technology development is demonstrated through successful technology transfer to U.S. industry and projected fleet impact. Specific examples of progress are discussed that quantifies the achievement towards these goals. In addition, a more detailed vision for NASA aeronautics is defined and key strategic issues are explored which invite international and national debate and involvement especially in reduced environmental impact for subsonic and supersonic aircraft, dramatic new capabilities in general aviation engines, and reduced development cycle time and costs.

  5. BOILING REACTORS

    DOEpatents

    Untermyer, S.

    1962-04-10

    A boiling reactor having a reactivity which is reduced by an increase in the volume of vaporized coolant therein is described. In this system unvaporized liquid coolant is extracted from the reactor, heat is extracted therefrom, and it is returned to the reactor as sub-cooled liquid coolant. This reduces a portion of the coolant which includes vaporized coolant within the core assembly thereby enhancing the power output of the assembly and rendering the reactor substantially self-regulating. (AEC)

  6. NEUTRONIC REACTOR

    DOEpatents

    Daniels, F.

    1959-10-27

    A reactor in which at least a portion of the moderator is in the form of movable refractory balls is described. In addition to their moderating capacity, these balls may serve as carriers for fissionable material or fertile material, or may serve in a coolant capacity to remove heat from the reactor. A pneumatic system is used to circulate the balls through the reactor.

  7. Federal Financing and University Goals.

    ERIC Educational Resources Information Center

    Morse, John F.

    Universities that base their priorities on the availability of government funds rather than on carefully designed institutional goals and realistic calculations of their resources often overextend their financial resources. Since participation in federal programs requires a commitment of institutional funds, the reduction or curtailment of federal…

  8. Cost goals for biofuels technologies

    SciTech Connect

    Gaines, L.L.; Flaim, S.J.

    1987-01-01

    Federally funded energy research seeks to demonstrate that alternative fuels can be produced and then to induce private sector involvement by showing that they can be produced profitably. Prices for fossil fuels may be used as cost goals for biofuels to determine when profitability may be achieved. Achieving equality with fossil fuel prices drives out the highest-cost sources of supply and enables initial market penetration; as costs decrease, biofuels can potentially gain a greater market share. However, achieving competitive costs is not a sufficient condition for success unless prices of conventional substitutes are expected to rise. Cost goals are used for research planning purposes, as a common denominator to allow comparisons among many biofuels options. Application of standard investment criteria to biofuels R and D would require that benefits from their use pay back research costs. These benefits must be discounted because they are realized in the future. Furthermore, realization of future savings is uncertain, so risks must be accounted for. Research may be justified if the expected value of the discounted benefits is greater than the discounted cost of the research. Cost goals satisfying this condition might be substantially lower than projected fuel prices. This paper examines recent fossil fuel price projections and discusses the challenges biofuels research faces just to produce competitive products. In light of the difficult goals, researchers should adopt a strategy targeting major technological breakthroughs rather than incremental improvements. Production of ethanol from wood is used as an example of this strategy. 35 refs., 8 figs., 7 tabs.

  9. Organizational Constraints and Goal Setting

    ERIC Educational Resources Information Center

    Putney, Frederick B.; Wotman, Stephen

    1978-01-01

    Management modeling techniques are applied to setting operational and capital goals using cost analysis techniques in this case study at the Columbia University School of Dental and Oral Surgery. The model was created as a planning tool used in developing a financially feasible operating plan and a 100 percent physical renewal plan. (LBH)

  10. CONVECTION REACTOR

    DOEpatents

    Hammond, R.P.; King, L.D.P.

    1960-03-22

    An homogeneous nuclear power reactor utilizing convection circulation of the liquid fuel is proposed. The reactor has an internal heat exchanger looated in the same pressure vessel as the critical assembly, thereby eliminating necessity for handling the hot liquid fuel outside the reactor pressure vessel during normal operation. The liquid fuel used in this reactor eliminates the necessity for extensive radiolytic gas rocombination apparatus, and the reactor is resiliently pressurized and, without any movable mechanical apparatus, automatically regulates itself to the condition of criticality during moderate variations in temperature snd pressure and shuts itself down as the pressure exceeds a predetermined safe operating value.

  11. Research reactors

    SciTech Connect

    Tonneson, L.C.; Fox, G.J.

    1996-04-01

    There are currently 284 research reactors in operation, and 12 under construction around the world. Of the operating reactors, nearly two-thirds are used exclusively for research, and the rest for a variety of purposes, including training, testing, and critical assembly. For more than 50 years, research reactor programs have contributed greatly to the scientific and educational communities. Today, six of the world`s research reactors are being shut down, three of which are in the USA. With government budget constraints and the growing proliferation concerns surrounding the use of highly enriched uranium in some of these reactors, the future of nuclear research could be impacted.

  12. Spectroscopic diagnostics of superthermal electrons with high-number harmonic EC radiation in tokamak reactor plasmas

    NASA Astrophysics Data System (ADS)

    Minashin, P. V.; Kukushkin, A. B.

    2015-03-01

    A method of spectroscopic diagnostics of the average perpendicular-to-magnetic-field momentum of the superthermal component of the electron velocity distribution (EVD), based on the high-number-harmonic electron cyclotron (EC) radiation, is suggested for nuclear fusion-reactor plasmas under condition of a strong auxiliary heating (e.g. in tokamak DEMO, a next step after tokamak ITER). The method is based on solving an inverse problem for reconstruction of the EVD in parallel and perpendicular-to-magnetic-field components of electron momentum at high and moderate energies responsible for the emission of the high-number-harmonic EC radiation.

  13. Dynamic behavior of chemical exchange column in a water detritiation system for a fusion reactor

    SciTech Connect

    Yamanishi, T.; Iwai, Y.

    2008-07-15

    The dynamic behavior of a CECE column used for a demonstration reactor (DEMO) plant has been studied. In the case where the column was filled with natural water, the time required to achieve steady state was almost the same as that for the column operated under the total reflux mode. The manipulated variables were flow rate of the bottom stream for the control of the bottom tritium concentration, and flow rate of the hydrogen stream for the control of the top tritium concentration. For both the variables, the response curve was expressed by the first-order lag system, and a PID controller could be applied. (authors)

  14. Transmutation analysis of realistic low-activation steels for magnetic fusion reactors and IFMIF

    SciTech Connect

    Cabellos, O; Sanz, J; Garc?a-Herranz, N; D?az, S; Reyes, S; Piedloup, S

    2005-11-22

    A comprehensive transmutation study for steels considered in the selection of structural materials for magnetic and inertial fusion reactors has been performed in the IFMIF neutron irradiation scenario, as well as in the ITER and DEMO ones for comparison purposes. An element-by-element transmutation approach is used in the study, addressing the generation of: (1) H and He and (2) solid transmutants. The IEAF-2001 activation library and the activation code ACAB were applied to the IFMIF transmutation analysis, after proving the applicability of ACAB for transmutation calculations of this kind of intermediate energy systems.

  15. Demonstrating soil moisture remote sensing with observations from the UK TechDemoSat-1 satellite mission

    NASA Astrophysics Data System (ADS)

    Chew, Clara; Shah, Rashmi; Zuffada, Cinzia; Hajj, George; Masters, Dallas; Mannucci, Anthony J.

    2016-04-01

    The ability of spaceborne Global Navigation Satellite System (GNSS) bistatic radar receivers to sense changes in soil moisture is investigated using observations from the low Earth orbiting UK TechDemoSat-1 satellite (TDS-1). Previous studies using receivers on aircraft or towers have shown that ground-reflected GNSS signals are sensitive to changes in soil moisture, though the ability to sense this variable from space has yet to be quantified. Data from TDS-1 show a 7 dB sensitivity of reflected signals to temporal changes in soil moisture. If the effects of surface roughness and vegetation on the reflected signals can be quantified, spaceborne GNSS bistatic radar receivers could provide soil moisture on relatively small spatial and temporal scales.

  16. Relations between Classroom Goal Structures and Students' Goal Orientations in Mathematics Classes: When Is a Mastery Goal Structure Adaptive?

    ERIC Educational Resources Information Center

    Skaalvik, Einar M.; Federici, Roger A.

    2016-01-01

    The purpose of this study was to test possible interactions between mastery and performance goal structures in mathematics classrooms when predicting students' goal orientations. More specifically, we tested if the degree of performance goal structure moderated the associations between mastery goal structure and students' goal orientations.…

  17. The interaction between dietary and life goals: using goal systems theory to explore healthy diet and life goals

    PubMed Central

    Turner-McGrievy, Gabrielle M.; Wright, Julie A.; Migneault, Jeffrey P.; Quintiliani, Lisa; Friedman, Robert H.

    2014-01-01

    Objective: To examine the types of life and dietary goals individuals report and how these goal domains interact as framed by goal systems theory. Methods: This work is a cross-sectional survey study. Measures included the incidence of common life and dietary goals and how these goals interact with and facilitate each other. Results: The results of a quantitative survey (n = 46 participants), which was informed by two focus groups (n = 17 participants), showed that participants are trying to achieve several different life (e.g. achieving financial success) and dietary goals (e.g. eating more fruits and vegetables, drinking more water, and losing weight) and that these two types of goals interact to both facilitate and conflict with each other. Having a life goal of exercising was significantly associated with healthy eating goals when compared with other life goals (p's < .05), suggesting these goals may be linked and help to facilitate one another. Being in the maintenance phase with the goal of healthy eating was associated with participants feeling like they were more successful in their other non-diet-related health goals (p < .05), suggesting maintenance of goals can facilitate success in achieving other goals. Conclusions: Life goals can have an impact on a person's ability to achieve and maintain dietary and other health goals. Health educators may help to facilitate long-term behavior change by examining a person's life goals as well as dietary goals. PMID:25750817

  18. Therapeutic Effectiveness of Setting and Monitoring Goals.

    ERIC Educational Resources Information Center

    Hart, Russell R.

    1978-01-01

    Evaluated therapeutic effectiveness of setting goals in behavioral terms while monitoring subject's progress in attaining these goals. Greater beneficial changes in patient attainment of goals were effected using a structured patient-therapist collaboration on weekly goals. Results indicate the goal attainment model with periodic monitoring is…

  19. Self-Beliefs and Student Goal Achievement

    ERIC Educational Resources Information Center

    Wesson, Caroline J.; Derrer-Rendall, Nicola M.

    2011-01-01

    Two preliminary studies are presented investigating the self-beliefs that may affect goal achievement in a student population. In Study 1, goal achievement on an abstract task, where goals are externally set by others, is considered in relation to students' levels of optimism. In Study 2, goal achievement on academic performance, where goals are…

  20. NEUTRONIC REACTOR

    DOEpatents

    Fraas, A.P.; Mills, C.B.

    1961-11-21

    A neutronic reactor in which neutron moderation is achieved primarily in its reflector is described. The reactor structure consists of a cylindrical central "island" of moderator and a spherical moderating reflector spaced therefrom, thereby providing an annular space. An essentially unmoderated liquid fuel is continuously passed through the annular space and undergoes fission while contained therein. The reactor, because of its small size, is particularly adapted for propulsion uses, including the propulsion of aircraft. (AEC)

  1. REACTOR COOLING

    DOEpatents

    Quackenbush, C.F.

    1959-09-29

    A nuclear reactor with provisions for selectively cooling the fuel elements is described. The reactor has a plurality of tubes extending throughout. Cylindrical fuel elements are disposed within the tubes and the coolant flows through the tubes and around the fuel elements. The fuel elements within the central portion of the reactor are provided with roughened surfaces of material. The fuel elements in the end portions of the tubes within the reactor are provlded with low conduction jackets and the fuel elements in the region between the central portion and the end portions are provided with smooth surfaces of high heat conduction material.

  2. EC Radiative Transport and Losses in DEMO-like High-Temperature Plasmas

    NASA Astrophysics Data System (ADS)

    Albajar, F.; Bornatici, M.; Engelmann, F.

    2015-03-01

    Electron cyclotron (EC) wave power losses tend to play a significant role in the local electron power balance of a tokamak fusion reactor for electron temperatures above 35 keV as considered for steady-state operation. Using the RAYTEC code a comparative study of EC wave and bremsstrahlung contributions to the local and total power balance in relation to the α-particle heating power was carried out for a range of plasma conditions, wall reflection coefficients of the EC waves, and magnetic fields.

  3. NEUTRONIC REACTOR

    DOEpatents

    Metcalf, H.E.; Johnson, H.W.

    1961-04-01

    BS>A nuclear reactor incorporating fuel rods passing through a moderator and including tubes of a material of higher Thermal conductivity than the fuel in contact with the fuel is described. The tubes extend beyond the active portion of the reactor into contant with a fiuld coolant.

  4. NEUTRONIC REACTOR

    DOEpatents

    Wigner, E.P.

    1958-04-22

    A nuclear reactor for isotope production is described. This reactor is designed to provide a maximum thermal neutron flux in a region adjacent to the periphery of the reactor rather than in the center of the reactor. The core of the reactor is generally centrally located with respect tn a surrounding first reflector, constructed of beryllium. The beryllium reflector is surrounded by a second reflector, constructed of graphite, which, in tune, is surrounded by a conventional thermal shield. Water is circulated through the core and the reflector and functions both as a moderator and a coolant. In order to produce a greatsr maximum thermal neutron flux adjacent to the periphery of the reactor rather than in the core, the reactor is designed so tbat the ratio of neutron scattering cross section to neutron absorption cross section averaged over all of the materials in the reflector is approximately twice the ratio of neutron scattering cross section to neutron absorption cross section averaged over all of the material of the core of the reactor.

  5. Goal directed behavior and dyslexia.

    PubMed

    Chiarenza, Giuseppe Augusto

    2016-01-01

    Goal directed behavior is explained by two approaches: the first, which can be named as cybertetic (behavior is wieved as homeostatic and reflexive), and second, as cognitive approach, a learned response, (skills developed by whaching the behavior of another individual). The aim of the paper is to present a noninvasive method described as an interaction of human beings with environment, recording the electrical activity of the brain from the human scalp. Obtained results are in agreement of psychological theories that place at determined levels of age the acquisition of the capacities of abstract thinking and with the functional neuroanatomic studies according to which biological maturation is necessary for learning processes to develop. An acquired level of learning is in close relationship with the maturation level of the cerebral structures. PMID:27442417

  6. Risk segmentation: goal or problem?

    PubMed

    Feldman, R; Dowd, B

    2000-07-01

    This paper traces the evolution of economists' views about risk segmentation in health insurance markets. Originally seen as a desirable goal, risk segmentation has come to be viewed as leading to abnormal profits, wasted resources, and inefficient limitations on coverage and services. We suggest that risk segmentation may be efficient if one takes an ex post view (i.e., after consumers' risks are known). From this perspective, managed care may be a much better method for achieving risk segmentation than limitations on coverage. The most serious objection to risk segmentation is the ex ante concern that it undermines long-term insurance contracts that would protect consumers against changes in lifetime risk. PMID:11010237

  7. Materials issues in fusion reactors

    NASA Astrophysics Data System (ADS)

    Suri, A. K.; Krishnamurthy, N.; Batra, I. S.

    2010-02-01

    The world scientific community is presently engaged in one of the toughest technological tasks of the current century, namely, exploitation of nuclear fusion in a controlled manner for the benefit of mankind. Scientific feasibility of controlled fusion of the light elements in plasma under magnetic confinement has already been proven. International efforts in a coordinated and co-operative manner are presently being made to build ITER - the International Thermonuclear Experimental Reactor - to test, in this first step, the concept of 'Tokamak' for net fusion energy production. To exploit this new developing option of making energy available through the route of fusion, India too embarked on a robust fusion programme under which we now have a working tokamak - the Aditya and a steady state tokamak (SST-1), which is on the verge of functioning. The programme envisages further development in terms of making SST-2 followed by a DEMO and finally the fusion power reactor. Further, with the participation of India in the ITER program in 2005, and recent allocation of half - a - port in ITER for placing our Lead - Lithium Ceramic Breeder (LLCB) based Test Blanket Module (TBM), meant basically for breeding tritium and extracting high grade heat, the need to understand and address issues related to materials for these complex systems has become all the more necessary. Also, it is obvious that with increasing power from the SST stages to DEMO and further to PROTOTYPE, the increasing demands on performance of materials would necessitate discovery and development of new materials. Because of the 14.1 MeV neutrons that are generated in the D+T reaction exploited in a tokamak, the materials, especially those employed for the construction of the first wall, the diverter and the blanket segments, suffer crippling damage due to the high He/dpa ratios that result due to the high energy of the neutrons. To meet this challenge, the materials that need to be developed for the tokamaks

  8. Current drive for stability of thermonuclear plasma reactor

    NASA Astrophysics Data System (ADS)

    Amicucci, L.; Cardinali, A.; Castaldo, C.; Cesario, R.; Galli, A.; Panaccione, L.; Paoletti, F.; Schettini, G.; Spigler, R.; Tuccillo, A.

    2016-01-01

    To produce in a thermonuclear fusion reactor based on the tokamak concept a sufficiently high fusion gain together stability necessary for operations represent a major challenge, which depends on the capability of driving non-inductive current in the hydrogen plasma. This request should be satisfied by radio-frequency (RF) power suitable for producing the lower hybrid current drive (LHCD) effect, recently demonstrated successfully occurring also at reactor-graded high plasma densities. An LHCD-based tool should be in principle capable of tailoring the plasma current density in the outer radial half of plasma column, where other methods are much less effective, in order to ensure operations in the presence of unpredictably changes of the plasma pressure profiles. In the presence of too high electron temperatures even at the periphery of the plasma column, as envisaged in DEMO reactor, the penetration of the coupled RF power into the plasma core was believed for long time problematic and, only recently, numerical modelling results based on standard plasma wave theory, have shown that this problem should be solved by using suitable parameter of the antenna power spectrum. We show here further information on the new understanding of the RF power deposition profile dependence on antenna parameters, which supports the conclusion that current can be actively driven over a broad layer of the outer radial half of plasma column, thus enabling current profile control necessary for the stability of a reactor.

  9. Rehabilitation Goals: Their Hierarchical and Multifaceted Nature.

    ERIC Educational Resources Information Center

    Livneh, Hanoch

    1988-01-01

    Rehabilitation goals are analyzed from a hierarchical, multifaceted perspective, illustrating reduction of the ultimate goal of life adjustment to smaller goals. Addressed are: the contexts within which rehabilitation takes place, the activity levels defining human performance, and the functional levels achieved. A matrix of 12 sets of goals is…

  10. Differential Valuations of Elementary Educational Goals.

    ERIC Educational Resources Information Center

    Doherty, William J.

    Based upon a comprehensive approach to educational goal selection, a national sampling of elementary school principals, teachers, and parents was compared over various demographic variables in terms of their goal priorities. The data consisted of the rating of 106 goals by each person sampled in the study. In addition to the goal ratings, each…

  11. Promoting Physical Activity through Goal Setting Strategies

    ERIC Educational Resources Information Center

    Martinez, Ray

    2004-01-01

    Physical educators are used to setting specific goals for students within a given unit. Here, the author emphasizes that they should also encourage students to set their own goals. Goal setting engages students in the learning process and allows them to develop the skills that support an active lifestyle. The author presents goal setting…

  12. A 2 X 2 achievement goal framework.

    PubMed

    Elliot, A J; McGregor, H A

    2001-03-01

    A 2 x 2 achievement goal framework comprising mastery-approach, mastery-avoidance, performance-approach, and performance-avoidance goals was proposed and tested in 3 studies. Factor analytic results supported the independence of the 4 achievement goal constructs. The goals were examined with respect to several important antecedents (e.g., motive dispositions, implicit theories, socialization histories) and consequences (e.g., anticipatory test anxiety, exam performance, health center visits), with particular attention allocated to the new mastery-avoidance goal construct. The results revealed distinct empirical profiles for each of the achievement goals; the pattern for mastery-avoidance goals was, as anticipated, more negative than that for mastery-approach goals and more positive than that for performance-avoidance goals. Implications of the present work for future theoretical development in the achievement goal literature are discussed. PMID:11300582

  13. Compact Reactor

    SciTech Connect

    Williams, Pharis E.

    2007-01-30

    Weyl's Gauge Principle of 1929 has been used to establish Weyl's Quantum Principle (WQP) that requires that the Weyl scale factor should be unity. It has been shown that the WQP requires the following: quantum mechanics must be used to determine system states; the electrostatic potential must be non-singular and quantified; interactions between particles with different electric charges (i.e. electron and proton) do not obey Newton's Third Law at sub-nuclear separations, and nuclear particles may be much different than expected using the standard model. The above WQP requirements lead to a potential fusion reactor wherein deuterium nuclei are preferentially fused into helium nuclei. Because the deuterium nuclei are preferentially fused into helium nuclei at temperatures and energies lower than specified by the standard model there is no harmful radiation as a byproduct of this fusion process. Therefore, a reactor using this reaction does not need any shielding to contain such radiation. The energy released from each reaction and the absence of shielding makes the deuterium-plus-deuterium-to-helium (DDH) reactor very compact when compared to other reactors, both fission and fusion types. Moreover, the potential energy output per reactor weight and the absence of harmful radiation makes the DDH reactor an ideal candidate for space power. The logic is summarized by which the WQP requires the above conditions that make the prediction of DDH possible. The details of the DDH reaction will be presented along with the specifics of why the DDH reactor may be made to cause two deuterium nuclei to preferentially fuse to a helium nucleus. The presentation will also indicate the calculations needed to predict the reactor temperature as a function of fuel loading, reactor size, and desired output and will include the progress achieved to date.

  14. Fourth goal of perinatal medicine.

    PubMed Central

    Ounsted, C; Roberts, J C; Gordon, M; Milligan, B

    1982-01-01

    Reduction in maternal mortality, infant mortality, and infant morbidity have been successively the goals of perinatal medicine. The fourth is to reduce bonding failure. In July 1978 a preventive service was started in the John Radcliffe Maternity Hospital. A twice-weekly round is made. Midwives refer families who cause them concern. In the first year the referral rate ws 20.5 per 1000 liveborn babies. The referred sample differed from the hospital population in terms of maternal psychiatric history, marital state and babies' admission to special care. The main reasons for referral were: doubt about parenting ability (27%), psychiatric history (15%), disturbed behaviour in hospital (14%), and diffuse social and medical problems (17%). Long-term care was needed for only 14% of families. At their first birthdays, six babies were placed away from their natural parents; the sample had had a slightly higher than expected admission rate to hospital; the distribution of weights did not differ from the expected; doctors and health visitors were still concerned about one-quarter of the families. Seven cases of screening failure were found among those not referred to our service, but only one was seriously abused. No child referred in the first year has been seriously neglected or abused. PMID:6802338

  15. Goal-based dictator game

    NASA Astrophysics Data System (ADS)

    Zaibidi, Nerda Zura; Ibrahim, Adyda; Abidin, Norhaslinda Zainal

    2014-12-01

    A considerable number of studies have been conducted to study fairness issues using two-player game. Dictator Game is one of the two-player games that receive much attention. In this paper, we develop an evolutionary approach to the Dictator Game by using Goal programming to build a model of human decision-making for cooperation. The model is formulated based on the theories of cognitive neuroscience that is capable in capturing a more realistic fairness concerns between players in the games. We show that fairness will evolve by taking into account players' aspirations and preferences explicitly in terms of profit and fairness concerns. The model is then simulated to investigate any possible effective strategy for people in economics to deal with fairness coalition. Parallels are drawn between the approach and concepts of human decision making from the field of cognitive neuroscience and psychology. The proposed model is also able to help decision makers to plan or enhance the effective strategies for business purposes.

  16. NUCLEAR REACTOR

    DOEpatents

    Moore, R.V.; Bowen, J.H.; Dent, K.H.

    1958-12-01

    A heterogeneous, natural uranium fueled, solid moderated, gas cooled reactor is described, in which the fuel elements are in the form of elongated rods and are dlsposed within vertical coolant channels ln the moderator symmetrically arranged as a regular lattice in groups. This reactor employs control rods which operate in vertical channels in the moderator so that each control rod is centered in one of the fuel element groups. The reactor is enclosed in a pressure vessel which ls provided with access holes at the top to facilitate loading and unloadlng of the fuel elements, control rods and control rod driving devices.

  17. Scientific goals of SCHOOLS & QUAKES

    NASA Astrophysics Data System (ADS)

    Brückl, Ewald; Köberl, Christian; Lenhardt, Wolfgang; Mertl, Stefan; Rafeiner-Magor, Walter; Stark, Angelika; Stickler, Gerald; Weber, Robert

    2015-04-01

    In many countries around the world seismometers are used in schools to broaden the knowledge in seismology in a vivid way and to take part in the observation of the current worldwide seismic activity. SCHOOLS & QUAKES is a project within the Sparkling Science program (http://www.sparklingscience.at), which not only pursues the given educational goals but also integrates scholars in seismological research permitting their own contributions. Research within SCHOOLS & QUAKES concentrates on the seismic activity of the Mürz Valley - Semmering - Vienna Basin transfer fault system in Austria because of its relatively high earthquake hazard and risk. The detection of low magnitude local earthquakes (magnitude ≤ 2), precise location of hypocenters, determination of the focal mechanisms, and correlation of hypocenters with active geological structures are the main scientific goals in this project. Furthermore, the long term build-up of tectonic stress, slip deficit and aseismic slip, and the maximum credible earthquake in this area are issues to be addressed. The scientific efforts of SCHOOLS & QUAKES build on the work of the Seismological Service of Austria at the Zentralanstalt für Meteorologie und Geodynamik (ZAMG), and benefit from the findings on the lithospheric structure of the Eastern Alps gained by the CELEBRATION 2000 and ALP 2002 projects. Regional Vp and Vs-models were derived from this data covering the SCHOOLS & QUAKES target area. Within the ALPAACT project (Seismological and geodetic monitoring of ALpine-PAnnonian ACtive Tectonics) the seismic network of the target area was densified by 7 broadband und 2 short period stations. Relocations based on a 3D-velocity model and the densified seismic network yielded substantially higher spatial resolution of seismically active structures. A new method based on waveform stacking (GRA, 16, EGU2014-5722) allowed for focal mechanism solutions of low magnitude (Ml ~2.5) events. Data from 22 GNSS stations have been

  18. NUCLEAR REACTOR

    DOEpatents

    Sherman, J.; Sharbaugh, J.E.; Fauth, W.L. Jr.; Palladino, N.J.; DeHuff, P.G.

    1962-10-23

    A nuclear reactor incorporating seed and blanket assemblies is designed. Means are provided for obtaining samples of the coolant from the blanket assemblies and for varying the flow of coolant through the blanket assemblies. (AEC)

  19. NEUTRONIC REACTOR

    DOEpatents

    Anderson, H.L.

    1960-09-20

    A nuclear reactor is described comprising fissionable material dispersed in graphite blocks, helium filling the voids of the blocks and the spaces therebetween, and means other than the helium in thermal conductive contact with the graphite for removing heat.

  20. NEUTRONIC REACTOR

    DOEpatents

    Hurwitz, H. Jr.; Brooks, H.; Mannal, C.; Payne, J.H.; Luebke, E.A.

    1959-03-24

    A reactor of the heterogeneous, liquid cooled type is described. This reactor is comprised of a central region of a plurality of vertically disposed elongated tubes surrounded by a region of moderator material. The central region is comprised of a central core surrounded by a reflector region which is surrounded by a fast neutron absorber region, which in turn is surrounded by a slow neutron absorber region. Liquid sodium is used as the primary coolant and circulates through the core which contains the fuel elements. Control of the reactor is accomplished by varying the ability of the reflector region to reflect neutrons back into the core of the reactor. For this purpose the reflector is comprised of moderator and control elements having varying effects on reactivity, the control elements being arranged and actuated by groups to give regulation, shim, and safety control.

  1. NEUTRONIC REACTOR

    DOEpatents

    Fermi, E.

    1960-04-01

    A nuclear reactor is described consisting of blocks of graphite arranged in layers, natural uranium bodies disposed in holes in alternate layers of graphite blocks, and coolant tubes disposed in the layers of graphite blocks which do not contain uranium.

  2. REACTOR SHIELD

    DOEpatents

    Wigner, E.P.; Ohlinger, L.E.; Young, G.J.; Weinberg, A.M.

    1959-02-17

    Radiation shield construction is described for a nuclear reactor. The shield is comprised of a plurality of steel plates arranged in parallel spaced relationship within a peripheral shell. Reactor coolant inlet tubes extend at right angles through the plates and baffles are arranged between the plates at right angles thereto and extend between the tubes to create a series of zigzag channels between the plates for the circulation of coolant fluid through the shield. The shield may be divided into two main sections; an inner section adjacent the reactor container and an outer section spaced therefrom. Coolant through the first section may be circulated at a faster rate than coolant circulated through the outer section since the area closest to the reactor container is at a higher temperature and is more radioactive. The two sections may have separate cooling systems to prevent the coolant in the outer section from mixing with the more contaminated coolant in the inner section.

  3. NUCLEAR REACTOR

    DOEpatents

    Miller, H.I.; Smith, R.C.

    1958-01-21

    This patent relates to nuclear reactors of the type which use a liquid fuel, such as a solution of uranyl sulfate in ordinary water which acts as the moderator. The reactor is comprised of a spherical vessel having a diameter of about 12 inches substantially surrounded by a reflector of beryllium oxide. Conventionnl control rods and safety rods are operated in slots in the reflector outside the vessel to control the operation of the reactor. An additional means for increasing the safety factor of the reactor by raising the ratio of delayed neutrons to prompt neutrons, is provided and consists of a soluble sulfate salt of beryllium dissolved in the liquid fuel in the proper proportion to obtain the result desired.

  4. NUCLEAR REACTOR

    DOEpatents

    Anderson, C.R.

    1962-07-24

    A fluidized bed nuclear reactor and a method of operating such a reactor are described. In the design means are provided for flowing a liquid moderator upwardly through the center of a bed of pellets of a nentron-fissionable material at such a rate as to obtain particulate fluidization while constraining the lower pontion of the bed into a conical shape. A smooth circulation of particles rising in the center and falling at the outside of the bed is thereby established. (AEC)

  5. NUCLEAR REACTOR

    DOEpatents

    Breden, C.R.; Dietrich, J.R.

    1961-06-20

    A water-soluble non-volatile poison may be introduced into a reactor to nullify excess reactivity. The poison is removed by passing a side stream of the water containing the soluble poison to an evaporation chamber. The vapor phase is returned to the reactor to decrease the concentration of soluble poison and the liquid phase is returned to increase the concentration of soluble poison.

  6. Daya Bay Neutrino Experiment: Goal, Progress and Schedule

    NASA Astrophysics Data System (ADS)

    Wang, Zhe; Daya Bay Neutrino Experiment Collaboration

    2011-04-01

    The discovery of neutrino oscillation, as a breakthrough in particle physics, prompted the Daya Bay Neutrino Experiment, which is designed to make a precise measurement of the last unknown neutrino mixing angle theta13, with a sensitivity of 0.01 for sin2(2 * θ13), using reactor anti-neutrinos from the 17.4GW Daya Bay Nuclear Power Plant located in Shenzhen, China. This talk will introduce the goal of this experiment including an overall introduction of the selection of the site and baseline, the detector optimization, the current construction progress and the schedule for expected data taking.

  7. NUCLEAR REACTOR

    DOEpatents

    Grebe, J.J.

    1959-07-14

    High temperature reactors which are uniquely adapted to serve as the heat source for nuclear pcwered rockets are described. The reactor is comprised essentially of an outer tubular heat resistant casing which provides the main coolant passageway to and away from the reactor core within the casing and in which the working fluid is preferably hydrogen or helium gas which is permitted to vaporize from a liquid storage tank. The reactor core has a generally spherical shape formed entirely of an active material comprised of fissile material and a moderator material which serves as a diluent. The active material is fabricated as a gas permeable porous material and is interlaced in a random manner with very small inter-connecting bores or capillary tubes through which the coolant gas may flow. The entire reactor is divided into successive sections along the direction of the temperature gradient or coolant flow, each section utilizing materials of construction which are most advantageous from a nuclear standpoint and which at the same time can withstand the operating temperature of that particular zone. This design results in a nuclear reactor characterized simultaneously by a minimum critiral size and mass and by the ability to heat a working fluid to an extremely high temperature.

  8. Tritium self-sufficiency time and inventory evolution for solid-type breeding blanket materials for DEMO

    NASA Astrophysics Data System (ADS)

    Packer, L. W.; Pampin, R.; Zheng, S.

    2011-10-01

    One of the primary functions of a fusion blanket is to generate enough tritium to make a fusion power plant (FPP) self-sufficient. To ensure that there is satisfactory tritium production in a real plant the tritium breeding ratio (TBR) in the blanket must be greater than 1 + M, where M is the breeding margin. For solid-type blanket designs, the initial TBR must be significantly higher than 1 + M, since the blanket TBR will be reduced over time as the lithium fuel is consumed. The rate of TBR reduction will impact on the overall blanket self-sufficiency time, the time in which the net tritium inventory of the system is positive. DEMO relevant blanket materials, Li 4SiO 4 and Li 2TiO 3, are investigated by computational simulation using radiation transport tools coupled with time-dependent inventory calculations. The results include tritium inventory assessments and depletion of breeding materials over time, which enable self-sufficiency times and maximum surplus tritium inventories to be evaluated, which are essential quantities to determine to allow one to design a credible FPP using solid-type breeding material concepts. The blanket concepts investigated show self-sufficiency times of several years in some cases and maximum surplus inventories of up to a few tens of kg.

  9. Comparative study of goal contents and goal characteristics between medical and business students

    PubMed Central

    Park, Soowon; Kim, Ji Eun; Lee, Jun-Young; Shin, Jongho

    2016-01-01

    Purpose: Medical and business are one of the most popular majors among students, and both fields require intensive training to reach certain level of expertise. During the development of professionalism, goal can become a crucial role in psychological impetus. The purpose of this study is to compare goal contents, goal characteristics, and effect of goal characteristics on student’s major satisfaction between medical and business. Methods: A total of 193 undergraduate students (97 medical students, 96 business students) answered survey questions including goal contents, goal characteristics (goal autonomy, goal attainability, social value of goal) and satisfaction on their majors. Qualitative analysis of goal contents and quantitative analysis of goal characteristics, and their effects on student major satisfaction were performed. Results: Goal content analysis showed percentage of social concern goal was higher in medical students (25.8%) than business students (6.3%), whereas percentage of wealth goal was higher business students (24.0%) than medical students (3.1%). Among goal characteristics, goal attainability and social value of goal were higher in medical students than business students. In both groups, social value of goal was significantly predict major satisfaction. Conclusion: Goal contents and goal characteristics are different between medical and business students. Curriculum and educational interventions that concerning students’ goal and developing programs to enhance students’ social value of goal is necessary. PMID:26838564

  10. Career goals in the high risk adolescent.

    PubMed

    Fleming, Charlene; Woods, Charles; Barkin, Shari L

    2006-10-01

    Possessing a career goal might serve as a protective factor for an adolescent's healthy development. This could be especially important in adolescents who engage in high risk behaviors. The relationship between high risk adolescents' future career goals and selected predictor variables were examined. Almost half (49%) the students indicated a career goal. Students who reported a job were 5.1-fold more likely to have listed a future career goal. Females, those aged 18 years, and those whose mothers were employed were twice as likely to have a career goal. Considerations for fostering career goals for high risk students are warranted. PMID:16968962

  11. Research Program of a Super Fast Reactor

    SciTech Connect

    Oka, Yoshiaki; Ishiwatari, Yuki; Liu, Jie; Terai, Takayuki; Nagasaki, Shinya; Muroya, Yusa; Abe, Hiroaki; Akiba, Masato; Akimoto, Hajime; Okumura, Keisuke; Akasaka, Naoaki; GOTO, Shoji

    2006-07-01

    Research program of a supercritical-pressure light water cooled fast reactor (Super Fast Reactor) is funded by MEXT (Ministry of Education, Culture, Sports, Science and Technology) in December 2005 as one of the research programs of Japanese NERI (Nuclear Energy Research Initiative). It consists of three programs. (1) development of Super Fast Reactor concept; (2) thermal-hydraulic experiments; (3) material developments. The purpose of the concept development is to pursue the advantage of high power density of fast reactor over thermal reactors to achieve economic competitiveness of fast reactor for its deployment without waiting for exhausting uranium resources. Design goal is not breeding, but maximizing reactor power by using plutonium from spent LWR fuel. MOX will be the fuel of the Super Fast Reactor. Thermal-hydraulic experiments will be conducted with HCFC22 (Hydro chlorofluorocarbons) heat transfer loop of Kyushu University and supercritical water loop at JAEA. Heat transfer data including effect of grid spacers will be taken. The critical flow and condensation of supercritical fluid will be studied. The materials research includes the development and testing of austenitic stainless steel cladding from the experience of PNC1520 for LMFBR. Material for thermal insulation will be tested. SCWR (Supercritical-Water Cooled Reactor) of GIF (Generation-4 International Forum) includes both thermal and fast reactors. The research of the Super Fast Reactor will enhance SCWR research and the data base. The research period will be until March 2010. (authors)

  12. The actual goals of geoethics

    NASA Astrophysics Data System (ADS)

    Nemec, Vaclav

    2014-05-01

    The most actual goals of geoethics have been formulated as results of the International Conference on Geoethics (October 2013) held at the geoethics birth-place Pribram (Czech Republic): In the sphere of education and public enlightenment an appropriate needed minimum know how of Earth sciences should be intensively promoted together with cultivating ethical way of thinking and acting for the sustainable well-being of the society. The actual activities of the Intergovernmental Panel of Climate Changes are not sustainable with the existing knowledge of the Earth sciences (as presented in the results of the 33rd and 34th International Geological Congresses). This knowledge should be incorporated into any further work of the IPCC. In the sphere of legislation in a large international co-operation following steps are needed: - to re-formulate the term of a "false alarm" and its legal consequences, - to demand very consequently the needed evaluation of existing risks, - to solve problems of rights of individuals and minorities in cases of the optimum use of mineral resources and of the optimum protection of the local population against emergency dangers and disasters; common good (well-being) must be considered as the priority when solving ethical dilemmas. The precaution principle should be applied in any decision making process. Earth scientists presenting their expert opinions are not exempted from civil, administrative or even criminal liabilities. Details must be established by national law and jurisprudence. The well known case of the L'Aquila earthquake (2009) should serve as a serious warning because of the proven misuse of geoethics for protecting top Italian seismologists responsible and sentenced for their inadequate superficial behaviour causing lot of human victims. Another recent scandal with the Himalayan fossil fraud will be also documented. A support is needed for any effort to analyze and to disclose the problems of the deformation of the contemporary

  13. Research reactors - an overview

    SciTech Connect

    West, C.D.

    1997-03-01

    A broad overview of different types of research and type reactors is provided in this paper. Reactor designs and operating conditions are briefly described for four reactors. The reactor types described include swimming pool reactors, the High Flux Isotope Reactor, the Mark I TRIGA reactor, and the Advanced Neutron Source reactor. Emphasis in the descriptions is placed on safety-related features of the reactors. 7 refs., 7 figs., 2 tabs.

  14. Deterministic seismic design and evaluation criteria to meet probabilistic performance goals

    SciTech Connect

    Short, S.A. ); Murray, R.C.; Nelson, T.A. ); Hill, J.R. . Office of Safety Appraisals)

    1990-12-01

    For DOE facilities across the United States, seismic design and evaluation criteria are based on probabilistic performance goals. In addition, other programs such as Advanced Light Water Reactors, New Production Reactors, and IPEEE for commercial nuclear power plants utilize design and evaluation criteria based on probabilistic performance goals. The use of probabilistic performance goals is a departure from design practice for commercial nuclear power plants which have traditionally been designed utilizing a deterministic specification of earthquake loading combined with deterministic response evaluation methods and permissible behavior limits. Approaches which utilize probabilistic seismic hazard curves for specification of earthquake loading and deterministic response evaluation methods and permissible behavior limits are discussed in this paper. Through the use of such design/evaluation approaches, it may be demonstrated that there is high likelihood that probabilistic performance goals can be achieved. 12 refs., 2 figs., 9 tabs.

  15. NEUTRONIC REACTOR

    DOEpatents

    Ohlinger, L.A.; Wigner, E.P.; Weinberg, A.M.; Young, G.J.

    1958-09-01

    This patent relates to neutronic reactors of the heterogeneous water cooled type, and in particular to a fuel element charging and discharging means therefor. In the embodiment illustrated the reactor contains horizontal, parallel coolant tubes in which the fuel elements are disposed. A loading cart containing a magnzine for holding a plurality of fuel elements operates along the face of the reactor at the inlet ends of the coolant tubes. The loading cart is equipped with a ram device for feeding fuel elements from the magazine through the inlot ends of the coolant tubes. Operating along the face adjacent the discharge ends of the tubes there is provided another cart means adapted to receive irradiated fuel elements as they are forced out of the discharge ends of the coolant tubes by the incoming new fuel elements. This cart is equipped with a tank coataining a coolant, such as water, into which the fuel elements fall, and a hydraulically operated plunger to hold the end of the fuel element being discharged. This inveation provides an apparatus whereby the fuel elements may be loaded into the reactor, irradiated therein, and unloaded from the reactor without stopping the fiow of the coolant and without danger to the operating personnel.

  16. Program Goals and Subject Matter Taxonomies for Course Goals, K-12. Fourth Edition.

    ERIC Educational Resources Information Center

    Tri-County Goal Development Project, Portland, OR.

    This collection of program goals and subject matter taxonomies was produced by the Tri-County (Oregon) Goal Development Project in response to requests that the project make available in one volume those sections of the course goal collections that are most useful for broad-based planning and decision-making. Program goals and course goals differ…

  17. Goals of Universal Basic and Secondary Education

    ERIC Educational Resources Information Center

    Cohen, Joel E.

    2006-01-01

    This essay discusses educational goals for universal basic and secondary education. It suggests some of the difficulties that may explain the great diversity of educational goals. The purposes of this essay are to (1) stimulate attention to educational goals on the part of individuals, families, educational professionals, community leaders in…

  18. Applications of Goal Programming to Education.

    ERIC Educational Resources Information Center

    Van Dusseldorp, Ralph A.; And Others

    This paper discusses goal programming, a computer-based operations research technique that is basically a modification and extension of linear programming. The authors first discuss the similarities and differences between goal programming and linear programming, then describe the limitations of goal programming and its possible applications for…

  19. ORGANIZATIONAL GOALS--A SYSTEMS APPROACH.

    ERIC Educational Resources Information Center

    OHM, ROBERT E.

    CONTEMPORARY SYSTEMS THEORISTS HAVE PROVIDED A HELPFUL VIEW OF THE WAY GOAL-STRUCTURE MAY SHAPE ADMINISTRATIVE BEHAVIOR IN EDUCATIONAL ORGANIZATIONS. THE "TRADITIONALIST" VIEW ASSIGNED ORGANIZATIONAL GOALS THE FUNCTIONS OF FORECASTING AND PLANNING. THE "EMERGING MODEL" VIEWED GOALS AS UNDEFINED ELEMENTS REQUIRING LITTLE SYSTEMATIC TREATMENT IN A…

  20. The Common Goals of Michigan Education, Tentative.

    ERIC Educational Resources Information Center

    Michigan State Dept. of Education, Lansing.

    The common goals of Michigan education are grouped into four areas. The goals in the first area, citizenship and morality, deal with morality, citizenship and social responsibility, and rights and responsibilities of students. The goals in the second area, democracy and equal opportunity, deal with equality of educational opportunity, education of…

  1. The Language Factor in Development Goals

    ERIC Educational Resources Information Center

    Bamgbose, Ayo

    2014-01-01

    Although development goals are usually set as targets that must be achieved in a development process, experience with development goals in Africa has tended to underscore underperformance either in terms of a shortfall in the targets attained or in terms of inadequate pursuit of specific goals. To illustrate this syndrome, the African Union's…

  2. 33 CFR 385.38 - Interim goals.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... section. (c) Principles for developing interim goals. (1) RECOVER, using best available science and... available science. These goals may be modified, based on best available science and the adaptive assessment...) Improvement in native plant and animal abundance. (3) In developing the interim goals based upon water...

  3. 33 CFR 385.38 - Interim goals.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... section. (c) Principles for developing interim goals. (1) RECOVER, using best available science and... available science. These goals may be modified, based on best available science and the adaptive assessment...) Improvement in native plant and animal abundance. (3) In developing the interim goals based upon water...

  4. Multiple Goal Orientations and Foreign Language Anxiety

    ERIC Educational Resources Information Center

    Koul, Ravinder; Roy, Laura; Kaewkuekool, Sittichai; Ploisawaschai, Suthee

    2009-01-01

    This investigation examines Thai college students' motivational goals for learning the English language. Thai student volunteers (N = 1387) from two types of educational institutions participated in this survey study which combined measures of goal orientations based on two different goal constructs and motivation models. Results of two-step…

  5. Examining the Stability of Achievement Goal Orientation

    ERIC Educational Resources Information Center

    Muis, Krista R.; Edwards, Ordene

    2009-01-01

    We examined stability and change in students' achievement goal orientations over varying tasks. Two naturalistic longitudinal studies were conducted in undergraduate courses. Students completed self-reports designed to measure their achievement goals. Achievement goals were measured four times: prior to two assignments and two exams. Four…

  6. Parental Goals and Talk with Toddlers

    ERIC Educational Resources Information Center

    Rowe, Meredith L.; Casillas, Allison

    2011-01-01

    Myriad studies support a relation between parental beliefs and behaviours. This study adds to the literature by focusing on the specific relationship between parental goals and their communication with toddlers. Do parents with different goals talk about different topics with their children? Parents' goals for their 30-month olds were gathered…

  7. Antineutrino Monitoring for Heavy Water Reactors

    NASA Astrophysics Data System (ADS)

    Christensen, Eric; Huber, Patrick; Jaffke, Patrick; Shea, Thomas E.

    2014-07-01

    In this Letter we discuss the potential application of antineutrino monitoring to the Iranian heavy water reactor at Arak, the IR-40, as a nonproliferation measure. An above ground detector positioned right outside the IR-40 reactor building could meet IAEA verification goals for reactor plutonium inventories. While detectors with the needed spectral sensitivity have been demonstrated below ground, additional research and development is needed to demonstrate an above-ground detector with this same level of sensitivity. In addition to monitoring the reactor during operation, observing antineutrino emissions from long-lived fission products could also allow monitoring the reactor when it is shut down, provided very low detector backgrounds can be achieved. Antineutrino monitoring could also be used to distinguish different levels of fuel enrichment. Most importantly, these capabilities would not require a complete reactor operational history and could provide a means to reestablish continuity of knowledge in safeguards conclusions should this become necessary.

  8. POWER REACTOR

    DOEpatents

    Zinn, W.H.

    1958-07-01

    A fast nuclear reactor system ls described for producing power and radioactive isotopes. The reactor core is of the heterogeneous, fluid sealed type comprised of vertically arranged elongated tubular fuel elements having vertical coolant passages. The active portion is surrounded by a neutron reflector and a shield. The system includes pumps and heat exchangers for the primary and secondary coolant circuits. The core, primary coolant pump and primary heat exchanger are disposed within an irapenforate tank which is filled with the primary coolant, in this case a liquid metal such as Na or NaK, to completely submerge these elements. The tank is completely surrounded by a thick walled concrete shield. This reactor system utilizes enriched uranium or plutonium as the fissionable material, uranium or thorium as a diluent and thorium or uranium containing less than 0 7% of the U/sup 235/ isotope as a fertile material.

  9. NEUTRONIC REACTORS

    DOEpatents

    Wigner, E.P.; Young, G.J.

    1958-10-14

    A method is presented for loading and unloading rod type fuel elements of a neutronic reactor of the heterogeneous, solld moderator, liquid cooled type. In the embodiment illustrated, the fuel rods are disposed in vertical coolant channels in the reactor core. The fuel rods are loaded and unloaded through the upper openings of the channels which are immersed in the coolant liquid, such as water. Unloading is accomplished by means of a coffer dam assembly having an outer sleeve which is placed in sealing relation around the upper opening. A radiation shield sleeve is disposed in and reciprocable through the coffer dam sleeve. A fuel rod engaging member operates through the axial bore in the radiation shield sleeve to withdraw the fuel rod from its position in the reactor coolant channel into the shield, the shield snd rod then being removed. Loading is accomplished in the reverse procedure.

  10. Catalytic reactor

    DOEpatents

    Aaron, Timothy Mark; Shah, Minish Mahendra; Jibb, Richard John

    2009-03-10

    A catalytic reactor is provided with one or more reaction zones each formed of set(s) of reaction tubes containing a catalyst to promote chemical reaction within a feed stream. The reaction tubes are of helical configuration and are arranged in a substantially coaxial relationship to form a coil-like structure. Heat exchangers and steam generators can be formed by similar tube arrangements. In such manner, the reaction zone(s) and hence, the reactor is compact and the pressure drop through components is minimized. The resultant compact form has improved heat transfer characteristics and is far easier to thermally insulate than prior art compact reactor designs. Various chemical reactions are contemplated within such coil-like structures such that as steam methane reforming followed by water-gas shift. The coil-like structures can be housed within annular chambers of a cylindrical housing that also provide flow paths for various heat exchange fluids to heat and cool components.