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1

Modelling of hydrogen isotope inventory in mixed materials including porous deposited layers in fusion devices  

NASA Astrophysics Data System (ADS)

Hydrogen isotope inventory (HII) is a key issue for fusion devices such as ITER. Simultaneous use of Be, W and C as the wall material for different parts of plasma-facing components (PFCs) will bring in material mixing issues, which compound that of hydrogen isotope retention. To simulate the hydrogen inventory in the PFCs, we have developed a flexible standalone model called HIIPC (Hydrogen Isotope Inventory Processes Code). The particle-balance-based model for reaction-diffusion and HII in metal and porous media (mainly carbon and co-deposited layers) is presented, coupled with a heating model which can calculate the temperature distribution. Some sample results are given to illustrate the model's capabilities and show good qualitative agreement with the experiment.

Sang, Chaofeng; Bonnin, Xavier; Warrier, Manoj; Rai, Abha; Schneider, Ralf; Sun, Jizhong; Wang, Dezhen

2012-04-01

2

Physics of Dust in Magnetic Fusion Devices  

NASA Astrophysics Data System (ADS)

Significant amount of dust will be produced in the next generation magnetic fusion devices due to plasma-wall interactions. The dust inventory must be controlled as it can pose a safety hazard and degrade performance. Safety concerns are due to tritium retention, dust radioactivity, toxicity, and flammability. Performance concerns include high-Z impurities carried by dust to the fusion core that can reduce plasma temperature and may even induce sudden termination of the plasma. Questions regarding dust in magnetic fusion devices therefore may be divided into dust safety, dust production, dust motion (dynamics), characteristics of dust, dust-plasma interactions, and most important of all, can dust be controlled in ways so that it will not become a severe problem for magnetic fusion energy production? The answer is not apparent at this time, which has motivated this work. Although dust safety and dust chemistry are important, our discussions primarily focus on dust physics. We describe theoretical frameworks, mostly due to dust research under a nonfusion context, that have already been established and can be used to answer many dust-related questions. We also describe dust measurements in fusion devices, numerical methods and results, and laboratory experiments related to the physics of fusion dust. Although qualitative understanding of dust in fusion has been or can be achieved, quantitative understanding of most dust physics in magnetic fusion is still needed. In order to find an effective way to deal with dust, future research activities include better dust diagnosis and monitoring, basic dusty plasma experiments emulating fusion conditions (for example, by using a mockup facility), numerical simulations bench-marked by experimental data, and development of a new generation of wall materials for fusion, which may include wall materials with engineered nanostructures.

Wang, Zhehui; Skinner, Charles H.; Luca Delzanno, Gian; Krasheninnikov, Sergei I.; Lapenta, Gianni M.; Pigarov, Alexander Yu.; Shukla, Padma K.; Smirnov, Roman D.; Ticos, Catalin M.; West, W. Phil

2008-03-01

3

21 CFR 888.3080 - Intervertebral body fusion device.  

Code of Federal Regulations, 2013 CFR

...2013-04-01 false Intervertebral body fusion device. 888.3080 Section 888...Devices § 888.3080 Intervertebral body fusion device. (a) Identification . An intervertebral body fusion device is an implanted single...

2013-04-01

4

21 CFR 888.3080 - Intervertebral body fusion device.  

Code of Federal Regulations, 2012 CFR

...2012-04-01 false Intervertebral body fusion device. 888.3080 Section 888...Devices § 888.3080 Intervertebral body fusion device. (a) Identification . An intervertebral body fusion device is an implanted single...

2012-04-01

5

21 CFR 888.3080 - Intervertebral body fusion device.  

...2014-04-01 false Intervertebral body fusion device. 888.3080 Section 888...Devices § 888.3080 Intervertebral body fusion device. (a) Identification. An intervertebral body fusion device is an implanted single...

2014-04-01

6

21 CFR 888.3080 - Intervertebral body fusion device.  

Code of Federal Regulations, 2011 CFR

...2011-04-01 false Intervertebral body fusion device. 888.3080 Section 888...Devices § 888.3080 Intervertebral body fusion device. (a) Identification . An intervertebral body fusion device is an implanted single...

2011-04-01

7

21 CFR 888.3080 - Intervertebral body fusion device.  

Code of Federal Regulations, 2010 CFR

...2010-04-01 false Intervertebral body fusion device. 888.3080 Section 888...Devices § 888.3080 Intervertebral body fusion device. (a) Identification . An intervertebral body fusion device is an implanted single...

2010-04-01

8

Electromagnetic computations for fusion devices  

SciTech Connect

Among the difficulties in making nuclear fusion a useful energy source, two important ones are producing the magnetic fields needed to drive and confine the plasma, and controlling the eddy currents induced in electrically conducting components by changing fields. All over the world, researchers are developing electromagnetic codes and employing them to compute electromagnetic effects. Ferromagnetic components of a fusion reactor introduce field distortions. Eddy currents are induced in the vacuum vessel, blanket and other torus components of a tokamak when the plasma current disrupts. These eddy currents lead to large forces, and 3-D codes are being developed to study the currents and forces. 35 refs., 6 figs.

Turner, L.R.

1989-09-01

9

Charge exchange recombination spectroscopy on fusion devices  

SciTech Connect

For fusion, obtaining reliable measurements of basic plasma parameters like ion and electron densities and temperatures is a primary goal. For theory, measurements are needed as a function of time and space to understand plasma transport and confinement with the ultimate goal of achieving economic nuclear fusion power. Electron profile measurements and plasma spectroscopy for the plasma ions are introduced. With the advent of Neutral Beam auxiliary plasma heating, Charge Exchange Recombination Spectroscopy provides accurate and time resolved measurements of the ions in large volume fusion devices. In acknowledgement of Nicol Peacock's role in the development of these techniques, still at the forefront of plasma fusion research, this paper describes the evolution of this diagnostic method.

Duval, B. P. [Centre de Recherches en Physique des Plasmas, EPFL, Lausanne (Switzerland)

2012-05-25

10

Edge turbulence measurements in toroidal fusion devices  

Microsoft Academic Search

This paper reviews measurements of edge plasma turbulence in toroidal magnetic fusion devices with an emphasis on recent results in tokamaks. The dominant feature of edge turbulence is a high level of broadband density fluctuations with a relative amplitude deltan\\/n ~ 5 100%, accompanied by large potential and electron temperature fluctuations. The frequency range of this turbulence is ~10 kHz

S. J. Zweben; J. A. Boedo; O. Grulke; C. Hidalgo; B. La Bombard; R. J. Maqueda; P. Scarin; J. L. Terry

2007-01-01

11

Magnetic systems for fusion devices  

SciTech Connect

Mirror experiments have led the way in applying superconductivity to fusion research because of unique requirements for high and steady magnetic fields. The first significant applications were Baseball II at LLNL and IMP at ORNL. More recently, the MFTF-B yin-yang coil was successfully tested and the entire tandem configuration is nearing completion. Tokamak magnets have also enjoyed recent success with the large coil project tests at ORNL, preceded by single coil tests in Japan and Germany. In the USSR, the T-7 Tokamak has been operational for many years and the T-15 Tokamak is under construction, with the TF coils nearing completion. Also the Tore Supra is being built in France.

Henning, C.D.

1985-02-01

12

Thermovoltaic semiconductor device including a plasma filter  

DOEpatents

A thermovoltaic energy conversion device and related method for converting thermal energy into an electrical potential. An interference filter is provided on a semiconductor thermovoltaic cell to pre-filter black body radiation. The semiconductor thermovoltaic cell includes a P/N junction supported on a substrate which converts incident thermal energy below the semiconductor junction band gap into electrical potential. The semiconductor substrate is doped to provide a plasma filter which reflects back energy having a wavelength which is above the band gap and which is ineffectively filtered by the interference filter, through the P/N junction to the source of radiation thereby avoiding parasitic absorption of the unusable portion of the thermal radiation energy.

Baldasaro, Paul F. (Clifton Park, NY)

1999-01-01

13

77 FR 60720 - Certain Electronic Devices, Including Wireless Commmunication Devices, Portable Music and Data...  

Federal Register 2010, 2011, 2012, 2013

...Devices, Including Wireless Commmunication Devices, Portable Music and Data Processing Devices, and Tablet Computers; Notice...devices, including wireless communication devices, portable music and data processing devices, and tablet computers,...

2012-10-04

14

77 FR 70464 - Certain Electronic Devices, Including Wireless Communication Devices, Portable Music and Data...  

Federal Register 2010, 2011, 2012, 2013

...Devices, Including Wireless Communication Devices, Portable Music and Data Processing Devices, and Tablet Computers; Notice...devices, including wireless communication devices, portable music and data processing devices, and tablet computers, by...

2012-11-26

15

78 FR 16865 - Certain Electronic Devices, Including Wireless Communication Devices, Portable Music and Data...  

Federal Register 2010, 2011, 2012, 2013

...Devices, Including Wireless Communication Devices, Portable Music and Data Processing Devices, and Tablet Computers; Investigations...devices, including wireless communication devices, portable music and data processing devices, and tablet computers, by...

2013-03-19

16

A Cognitive Vision System for Nuclear Fusion Device Monitoring  

E-print Network

A Cognitive Vision System for Nuclear Fusion Device Monitoring Vincent Martin1 , Victor Moncada1 to produce controlled thermonuclear fusion power by magnetic confinement of a plasma (fully ionized gas optimizations. The framework is generic and can be easily adapted to different fusion device environ- ments

Paris-Sud XI, Université de

17

Neutral particle kinetics in fusion devices  

SciTech Connect

The theory of neutral particle kinetics treats the transport of mass, momentum, and energy in a plasma due to neutral particles which themselves are unaffected by magnetic fields. This transport affects the global power and particle balances in fusion devices, as well as profile control and plasma confinement quality, particle and energy fluxes onto device components, performance of pumping systems, and the design of diagnostics and the interpretation of their measurements. This paper reviews the development of analytic, numerical, and Monte Carlo methods of solving the time-independent Boltzmann equation describing neutral kinetics. These models for neutral particle behavior typically use adaptations of techniques developed originally for computing neutron transport, due to the analogy between the two phenomena, where charge-exchange corresponds to scattering and ionization to absorption. Progress in the field depends on developing multidimensional analytic methods, and obtaining experimental data for the physical processes of wall reflection, the neutral/plasma interaction, and for processes in fusion devices which are directly related to neutral transport, such as H/sub ..cap alpha../ emission rates, plenum pressures, and charge-exchange emission spectra.

Tendler, M.; Heifetz, D.

1986-05-01

18

Conference Report on the 2nd International Symposium on Lithium Applications for Fusion Devices  

Microsoft Academic Search

The 2nd International Symposium on Lithium Applications for Fusion Devices (ISLA-2011) was held on 27–29 April 2011 at the Princeton Plasma Physics Laboratory (PPPL) with broad participation from the community working on aspects of lithium research for fusion energy development. This community is expanding rapidly in many areas including experiments in magnetic confinement devices and a variety of lithium test

M. Ono; M. G. Bell; Y. Hirooka; R. Kaita; H. W. Kugel; G. Mazzitelli; J. E. Menard; S. V. Mirnov; M. Shimada; C. H. Skinner; F. L. Tabares

2012-01-01

19

Eddy current analysis in fusion devices  

SciTech Connect

In magnetic fusion devices, particularly tokamaks and reversed field pinch (RFP) experiments, time-varying magnetic fields are in intimate contact with electrically conducting components of the device. Induced currents, fields, forces, and torques result. This note reviews the analysis of eddy current effects in the following systems: Interaction of a tokamak plasma with the eddy currents in the first wall, blanket, and shield (FWBS) systems; Eddy currents in a complex but two-dimensional vacuum vessel, as in TFTR, JET, and JT-60; Eddy currents in the FWBS system of a tokamak reactor, such as NET, FER, or ITER; and Eddy currents in a RFP shell. The cited studies are chosen to be illustrative, rather than exhaustive. 42 refs.

Turner, L.R.

1988-06-01

20

Tritium and workers in fusion devices-lessons learnt.  

PubMed

Fusion machines from all over the world have contributed to the knowledge accumulated in fusion science. This knowledge has been applied to design new experimental fusion machines and in particular ITER. Only two fusion devices based on magnetic confinement have used deuterium and tritium fuels to-date-the Tokamak Fusion Test Reactor, TFTR, in Princeton, USA, and JET, the European tokamak. These machines have demonstrated that the fusion reaction is achievable with these fuels, and have provided valuable lessons on radioprotection-related issues as concerns tritium and workers. Dedicated tritium installations for fusion research and development have also contributed to this knowledge base. PMID:19690360

Rodriguez-Rodrigo, Lina; Elbez-Uzan, Joelle; Alejaldre, Carlos

2009-09-01

21

Overview of gas balance in plasma fusion devices  

Microsoft Academic Search

Particle retention is a major constraint for future fusion devices like ITER in which the amount of tritium will be strictly limited for safety reasons. In the EU Task Force on plasma wall interaction, efforts are underway to investigate the gas balance, the particle retention and removal in fusion devices. Gas balance in JET, ASDEX Upgrade, TEXTOR and Tore Supra

22

Linear optimal control of tokamak fusion devices  

SciTech Connect

The control of plasma position, shape and current in a tokamak fusion reactor is examined using linear optimal control. These advanced tokamaks are characterized by non up-down symmetric coils and structure, thick structure surrounding the plasma, eddy currents, shaped plasmas, superconducting coils, vertically unstable plasmas, and hybrid function coils providing ohmic heating, vertical field, radial field, and shaping field. Models of the electromagnetic environment in a tokamak are derived and used to construct control gains that are tested in nonlinear simulations with initial perturbations. The issues of applying linear optimal control to advanced tokamaks are addressed, including complex equilibrium control, choice of cost functional weights, the coil voltage limit, discrete control, and order reduction. Results indicate that the linear optimal control is a feasible technique for controlling advanced tokamaks where the more common classical control will be severely strained or will not work. 28 refs., 13 figs.

Kessel, C.E.; Firestone, M.A.; Conn, R.W.

1989-05-01

23

Measuring time of flight of fusion products in an inertial electrostatic confinement fusion device for spatial profiling of fusion reactions  

SciTech Connect

A new diagnostic has been developed that uses the time of flight (TOF) of the products from a nuclear fusion reaction to determine the location where the fusion reaction occurred. The TOF diagnostic uses charged particle detectors on opposing sides of the inertial electrostatic confinement (IEC) device that are coupled to high resolution timing electronics to measure the spatial profile of fusion reactions occurring between the two charged particle detectors. This diagnostic was constructed and tested by the University of Wisconsin-Madison Inertial Electrostatic Confinement Fusion Group in the IEC device, HOMER, which accelerates deuterium ions to fusion relevant energies in a high voltage ({approx}100 kV), spherically symmetric, electrostatic potential well [J. F. Santarius, G. L. Kulcinski, R. P. Ashley, D. R. Boris, B. B. Cipiti, S. K. Murali, G. R. Piefer, R. F. Radel, T. E. Radel, and A. L. Wehmeyer, Fusion Sci. Technol. 47, 1238 (2005)]. The TOF diagnostic detects the products of D(d,p)T reactions and determines where along a chord through the device the fusion event occurred. The diagnostic is also capable of using charged particle spectroscopy to determine the Doppler shift imparted to the fusion products by the center of mass energy of the fusion reactants. The TOF diagnostic is thus able to collect spatial profiles of the fusion reaction density along a chord through the device, coupled with the center of mass energy of the reactions occurring at each location. This provides levels of diagnostic detail never before achieved on an IEC device.

Donovan, D. C. [Sandia National Laboratories, 7011 East Avenue, Livermore, California 94550 (United States); Boris, D. R. [Naval Research Laboratory, 4555 Overlook Avenue, South West, Washington, DC 20375 (United States); Kulcinski, G. L.; Santarius, J. F. [Fusion Technology Institute, University of Wisconsin-Madison, 1500 Engineering Drive, Madison, Wisconsin 53706 (United States); Piefer, G. R. [Phoenix Nuclear Labs, 2555 Industrial Drive, Madison, Wisconsin 53713 (United States)

2013-03-15

24

Measuring time of flight of fusion products in an inertial electrostatic confinement fusion device for spatial profiling of fusion reactions  

NASA Astrophysics Data System (ADS)

A new diagnostic has been developed that uses the time of flight (TOF) of the products from a nuclear fusion reaction to determine the location where the fusion reaction occurred. The TOF diagnostic uses charged particle detectors on opposing sides of the inertial electrostatic confinement (IEC) device that are coupled to high resolution timing electronics to measure the spatial profile of fusion reactions occurring between the two charged particle detectors. This diagnostic was constructed and tested by the University of Wisconsin-Madison Inertial Electrostatic Confinement Fusion Group in the IEC device, HOMER, which accelerates deuterium ions to fusion relevant energies in a high voltage (˜100 kV), spherically symmetric, electrostatic potential well [J. F. Santarius, G. L. Kulcinski, R. P. Ashley, D. R. Boris, B. B. Cipiti, S. K. Murali, G. R. Piefer, R. F. Radel, T. E. Radel, and A. L. Wehmeyer, Fusion Sci. Technol. 47, 1238 (2005)]. The TOF diagnostic detects the products of D(d,p)T reactions and determines where along a chord through the device the fusion event occurred. The diagnostic is also capable of using charged particle spectroscopy to determine the Doppler shift imparted to the fusion products by the center of mass energy of the fusion reactants. The TOF diagnostic is thus able to collect spatial profiles of the fusion reaction density along a chord through the device, coupled with the center of mass energy of the reactions occurring at each location. This provides levels of diagnostic detail never before achieved on an IEC device.

Donovan, D. C.; Boris, D. R.; Kulcinski, G. L.; Santarius, J. F.; Piefer, G. R.

2013-03-01

25

D-3He fusion in an inertial electrostatic confinement device  

Microsoft Academic Search

Advanced fusion fuels, D and 3He, have been successfully fused in an inertial electrostatic confinement device at the University of Wisconsin. It is thought that this is the first known fusion of helium-3 with deuterium on a steady state basis. The detection of 14.7 MeV protons has confirmed the reaction of D-3He fusion, and has produced a continuous, charged particle

R. P. Ashley; G. L. Kulcinski; J. F. Santarius; S. Krupakar Murali; G. Piefer

1999-01-01

26

Wafer Fusion for Integration of Semiconductor Materials and Devices  

SciTech Connect

We have developed a wafer fusion technology to achieve integration of semiconductor materials and heterostructures with widely disparate lattice parameters, electronic properties, and/or optical properties for novel devices not now possible on any one substrate. Using our simple fusion process which uses low temperature (400-600 C) anneals in inert N{sub 2} gas, we have extended the scope of this technology to examine hybrid integration of dissimilar device technologies. As a specific example, we demonstrate wafer bonding vertical cavity surface emitting lasers (VCSELs) to transparent AlGaAs and GaP substrates to fabricate bottom-emitting short wavelength VCSELs. As a baseline fabrication technology applicable to many semiconductor systems, wafer fusion will revolutionize the way we think about possible semiconductor devices, and enable novel device configurations not possible by epitaxial growth.

Choquette, K.D.; Geib, K.M.; Hou, H.Q.; Allerman, A.A.; Kravitz, S.; Follstaedt, D.M.; Hindi, J.J.

1999-05-01

27

Measuring time of flight of fusion products in an inertial electrostatic confinement fusion device for spatial profiling of fusion reactions.  

PubMed

A new diagnostic has been developed that uses the time of flight (TOF) of the products from a nuclear fusion reaction to determine the location where the fusion reaction occurred. The TOF diagnostic uses charged particle detectors on opposing sides of the inertial electrostatic confinement (IEC) device that are coupled to high resolution timing electronics to measure the spatial profile of fusion reactions occurring between the two charged particle detectors. This diagnostic was constructed and tested by the University of Wisconsin-Madison Inertial Electrostatic Confinement Fusion Group in the IEC device, HOMER, which accelerates deuterium ions to fusion relevant energies in a high voltage (?100 kV), spherically symmetric, electrostatic potential well [J. F. Santarius, G. L. Kulcinski, R. P. Ashley, D. R. Boris, B. B. Cipiti, S. K. Murali, G. R. Piefer, R. F. Radel, T. E. Radel, and A. L. Wehmeyer, Fusion Sci. Technol. 47, 1238 (2005)]. The TOF diagnostic detects the products of D(d,p)T reactions and determines where along a chord through the device the fusion event occurred. The diagnostic is also capable of using charged particle spectroscopy to determine the Doppler shift imparted to the fusion products by the center of mass energy of the fusion reactants. The TOF diagnostic is thus able to collect spatial profiles of the fusion reaction density along a chord through the device, coupled with the center of mass energy of the reactions occurring at each location. This provides levels of diagnostic detail never before achieved on an IEC device. PMID:23556815

Donovan, D C; Boris, D R; Kulcinski, G L; Santarius, J F; Piefer, G R

2013-03-01

28

Super-X divertors and high power density fusion devices  

SciTech Connect

The Super-X Divertor (SXD), a robust axisymmetric redesign of the divertor magnetic geometry that can allow a fivefold increase in the core power density of toroidal fusion devices, is presented. With small changes in poloidal coils and currents for standard divertors, the SXD allows the largest divertor plate radius inside toroidal field coils. This increases the plasma-wetted area by 2-3 times over all flux-expansion-only methods (e.g., plate near main X point, plate tilting, X divertor, and snowflake), decreases parallel heat flux and hence plasma temperature at plate, and increases connection length by 2-5 times. Examples of high-power-density fusion devices enabled by SXD are discussed; the most promising near-term device is a 100 MW modular compact fusion neutron source 'battery' small enough to fit inside a conventional fission blanket.

Valanju, P. M.; Kotschenreuther, M.; Mahajan, S. M. [Institute for Fusion Studies, University of Texas at Austin, Austin, Texas 78712-1060 (United States); Canik, J. [Oak Ridge National Laboratory, Oak Ridge, Tennessee 37830 (United States)

2009-05-15

29

Super-X Divertors and High Power Density Fusion Devices  

SciTech Connect

The Super-X Divertor (SXD), a robust axisymmetric redesign of the divertor magnetic geometry that can allow a fivefold increase in the core power density of toroidal fusion devices, is presented. With small changes in poloidal coils and currents for standard divertors, the SXD allows the largest divertor plate radius inside toroidal field coils. This increases the plasma-wetted area by 2-3 times over all flux-expansion-only methods (e.g., plate near main X point, plate tilting, X divertor, and snowflake), decreases parallel heat flux and hence plasma temperature at plate, and increases connection length by 2-5 times. Examples of high-power-density fusion devices enabled by SXD are discussed; the most promising near-term device is a 100 MW modular compact fusion neutron source "battery" small enough to fit inside a conventional fission blanket.

Valanju, P. [University of Texas, Austin; Kotschenreuther, M. [University of Texas, Austin; Mahajan, S. [University of Texas, Austin; Canik, John [ORNL

2009-01-01

30

Variable control of neutron albedo in toroidal fusion devices  

DOEpatents

An arrangement is provided for controlling neutron albedo in toroidal fusion devices having inboard and outboard vacuum vessel walls for containment of the neutrons of a fusion plasma. Neutron albedo material is disposed immediately adjacent the inboard wall, and is movable, preferably in vertical directions, so as to be brought into and out of neutron modifying communication with the fusion neutrons. Neutron albedo material preferably comprises a liquid form, but may also take pebble, stringer and curtain-like forms. A neutron flux valve, rotatable about a vertical axis is also disclosed.

Jassby, Daniel L. (Princeton, NJ); Micklich, Bradley J. (Princeton, NJ)

1986-01-01

31

Skyshine study for next generation of fusion devices  

SciTech Connect

A shielding analysis for next generation of fusion devices (ETR/INTOR) was performed to study the dose equivalent outside the reactor building during operation including the contribution from neutrons and photons scattered back by collisions with air nuclei (skyshine component). Two different three-dimensional geometrical models for a tokamak fusion reactor based on INTOR design parameters were developed for this study. In the first geometrical model, the reactor geometry and the spatial distribution of the deuterium-tritium neutron source were simplified for a parametric survey. The second geometrical model employed an explicit representation of the toroidal geometry of the reactor chamber and the spatial distribution of the neutron source. The MCNP general Monte Carlo code for neutron and photon transport was used to perform all the calculations. The energy distribution of the neutron source was used explicitly in the calculations with ENDF/B-V data. The dose equivalent results were analyzed as a function of the concrete roof thickness of the reactor building and the location outside the reactor building.

Gohar, Y.; Yang, S.

1987-02-01

32

Frontier of Fusion Research: Path to the Steady State Fusion Reactor by Large Helical Device  

NASA Astrophysics Data System (ADS)

The ITER, the International Thermonuclear Experimental Reactor, which will be built in Cadarache in France, has finally started this year, 2006. Since the thermal energy produced by fusion reactions divided by the external heating power, i.e., the Q value, will be larger than 10, this is a big step of the fusion research for half a century trying to tame the nuclear fusion for the 6.5 Billion people on the Earth. The source of the Sun's power is lasting steadily and safely for 8 Billion years. As a potentially safe environmentally friendly and economically competitive energy source, fusion should provide a sustainable future energy supply for all mankind for ten thousands of years. At the frontier of fusion research important milestones are recently marked on a long road toward a true prototype fusion reactor. In its own merits, research into harnessing turbulent burning plasmas and thereby controlling fusion reaction, is one of the grand challenges of complex systems science. After a brief overview of a status of world fusion projects, a focus is given on fusion research at the National Institute for Fusion Science (NIFS) in Japan, which is playing a role of the Inter University Institute, the coordinating Center of Excellence for academic fusion research and by the Large Helical Device (LHD), the world's largest superconducting heliotron device, as a National Users' facility. The current status of LHD project is presented focusing on the experimental program and the recent achievements in basic parameters and in steady state operations. Since, its start in a year 1998, a remarkable progress has presently resulted in the temperature of 140 Million degree, the highest density of 500 Thousand Billion/cc with the internal density barrier (IDB) and the highest steady average beta of 4.5% in helical plasma devices and the largest total input energy of 1.6 GJ, in all magnetic confinement fusion devices. Finally, a perspective is given of the ITER Broad Approach program as an integrated part of ITER and Development of Fusion Energy project Agreement. Moreover, the relationship with the NIFS' new parent organization the National Institutes of Natural Sciences and with foreign research institutions is briefly explained.

Motojima, Osamu

2006-12-01

33

Computerized device for critical flicker fusion frequency determination  

NASA Astrophysics Data System (ADS)

The critical fusion flicker frequency of the human visual system is the threshold sensitivity for a sine wave-modulated patch of monochromatic flickering light measured as a function of its temporal frequency and average luminance level. The critical flicker fusion frequency changes in different ocular and non-ocular conditions, for example: high-myopia, AMR, glaucoma, schizophrenia, after alcohol intake, fatigue. A computerized test for critical flicker fusion frequency determination was developed. Visual stimuli are two monochromatic LED light sources that are connected to a microcircuit driven by a computer program. The control of the device is realized through the parallel port of the PC. During the test a patient has to choose which one of two light sources is flickering. The critical cliker fusion frequency is determined by a psychophysical procedure, where the stimulus frequency that showed detection probability 75% is considered as threshold.

Racene, Diana

2003-08-01

34

FED-R: a fusion engineering device utilizing resistive magnets  

SciTech Connect

The principal purpose of the FED-R tokamak facility is to provide a substantial quasi-steady flux of fusion neutrons irradiating a large test area in order to carry out thermal, neutronic, and radiation effects testing of experimental blanket assemblies having a variety of configurations, compositions, and purposes. The design of the FED-R device also suggests potential for an upgrade that could be employed as a full-scale demonstration reactor for some specific fusion-neutron application when required.

Jassby, D.L.; Kalsi, S.S. (eds.)

1983-04-01

35

On Lithium Wall and Performance of Magnetic Fusion Device S. I. Krasheninnikov1  

E-print Network

On Lithium Wall and Performance of Magnetic Fusion Device S. I. Krasheninnikov1 , L. E. Zakharov2 It is shown that lithium walls resulting in zero recycling conditions at the edge of magnetic fusion device strong impact of fully absorbing lithium walls on the performance of magnetic fusion devices have been

Krstic, Miroslav

36

Super-X divertors and high power density fusion devices  

Microsoft Academic Search

The Super-X Divertor (SXD), a robust axisymmetric redesign of the divertor magnetic geometry that can allow a fivefold increase in the core power density of toroidal fusion devices, is presented. With small changes in poloidal coils and currents for standard divertors, the SXD allows the largest divertor plate radius inside toroidal field coils. This increases the plasma-wetted area by 2-3

P. M. Valanju; M. Kotschenreuther; S. M. Mahajan; John Canik

2009-01-01

37

Impurity studies in fusion devices using laser-fluorescence-spectroscopy  

SciTech Connect

Resonance fluorescence excitation of neutral atoms using tunable radiation from dye lasers offers a number of unique advantages for impurity studies in fusion devices. Using this technique, it is possible to perform local, time-resolved measurements of the densities and velocity distributions of metallic impurities in fusion devices without disturbing the plasma. Velocities are measured by monitoring the fluorescence intensity while tuning narrow bandwidth laser radiation through the Doppler - broadened absorbtion spectrum of the transition. The knowledge of the velocity distribution of neutral impurities is particularly useful for the determination of impurity introduction mechanisms. The laser fluorescence technique will be described in terms of its application to metallic impurities in fusion devices and related laboratory experiments. Particular attention will be given to recent results from the ISX-B tokamak using pulsed dye lasers where detection sensitivities for neutral Fe of 10/sup 6/ atoms/cm/sup 3/ with a velocity resolution of 600 m/sec (0.1 eV) have been achieved. Techniques for exciting plasma particles (H,D) will also be discussed.

Husinsky, W.R.

1980-08-01

38

Pressure Sensitivity Studies of an Electrostatic Fusion Neutron Device Using a Particle-in-Cell Model  

SciTech Connect

The background deuterium neutral gas pressure is a major operational parameter affecting the physics of the ionized gas discharge in the inertial electrostatic confinement (IEC) axial-cylindrical fusion neutron generator device (C-Device). There is uncertainty in its actual value in previous experiments. The cylindrical hollow IEC modeling program (CHIMP) computer code is a particle-in-cell, Monte Carlo-collision (PIC-MCC) model that includes ionization and secondary electron emission processes and is used to give preliminary results for the ionized gas physics behavior and neutron generation in the C-Device for a range of pressure calibration factors.

Bromley, Blair P. [Brookhaven National Laboratory (United States)

2002-01-15

39

Electra-optical device including a nitrogen containing electrolyte  

DOEpatents

Described is a thin-film battery, especially a thin-film microbattery, and a method for making same having application as a backup or primary integrated power source for electronic devices. The battery includes a novel electrolyte which is electrochemically stable and does not react with the lithium anode and a novel vanadium oxide cathode. Configured as a microbattery, the battery can be fabricated directly onto a semiconductor chip, onto the semiconductor die or onto any portion of the chip carrier. The battery can be fabricated to any specified size or shape to meet the requirements of a particular application. The battery is fabricated of solid state materials and is capable of operation between {minus}15 C and 150 C.

Bates, J.B.; Dudney, N.J.; Gruzalski, G.R.; Luck, C.F.

1995-10-03

40

Electra-optical device including a nitrogen containing electrolyte  

DOEpatents

Described is a thin-film battery, especially a thin-film microbattery, and a method for making same having application as a backup or primary integrated power source for electronic devices. The battery includes a novel electrolyte which is electrochemically stable and does not react with the lithium anode and a novel vanadium oxide cathode Configured as a microbattery, the battery can be fabricated directly onto a semiconductor chip, onto the semiconductor die or onto any portion of the chip carrier. The battery can be fabricated to any specified size or shape to meet the requirements of a particular application. The battery is fabricated of solid state materials and is capable of operation between -15.degree. C. and 150.degree. C.

Bates, John B. (Oak Ridge, TN); Dudney, Nancy J. (Knoxville, TN); Gruzalski, Greg R. (Oak Ridge, TN); Luck, Christopher F. (Knoxville, TN)

1995-01-01

41

76 FR 45860 - In the Matter of Certain Electronic Devices, Including Wireless Communication Devices, Portable...  

Federal Register 2010, 2011, 2012, 2013

...Wireless Communication Devices, Portable Music and Data Processing Devices, and Tablet...wireless communication devices, portable music and data processing devices, and tablet...wireless communication devices, portable music and data processing devices, and...

2011-08-01

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78 FR 34669 - Certain Electronic Devices, Including Wireless Communication Devices, Portable Music and Data...  

Federal Register 2010, 2011, 2012, 2013

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2013-06-10

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75 FR 74080 - In the Matter of Certain Liquid Crystal Display Devices, Including Monitors, Televisions, and...  

Federal Register 2010, 2011, 2012, 2013

...337-TA-749 In the Matter of Certain Liquid Crystal Display Devices, Including Monitors...States after importation of certain liquid crystal display devices, including monitors...States after importation of certain liquid crystal display devices, including...

2010-11-30

44

75 FR 63856 - In the Matter of Certain Liquid Crystal Display Devices, Including Monitors, Televisions, and...  

Federal Register 2010, 2011, 2012, 2013

...337-TA-741] In the Matter of Certain Liquid Crystal Display Devices, Including Monitors...States after importation of certain liquid crystal display devices, including monitors...States after importation of certain liquid crystal display devices, including...

2010-10-18

45

78 FR 47410 - Certain Wireless Devices, Including Mobile Phones and Tablets Institution of Investigation  

Federal Register 2010, 2011, 2012, 2013

...Certain Wireless Devices, Including Mobile Phones and Tablets Institution of Investigation...certain wireless devices, including mobile phones and tablets by reason of infringement...certain wireless devices, including mobile phones and tablets by reason of...

2013-08-05

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78 FR 40171 - Certain Wireless Devices, Including Mobile Phones and Tablets; Notice Of Receipt of Complaint...  

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...Certain Wireless Devices, Including Mobile Phones and Tablets; Notice Of Receipt...Certain Wireless Devices, Including Mobile Phones and Tablets, DN 2964; the Commission...certain wireless devices, including mobile phones and tablets. The complaint...

2013-07-03

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75 FR 4583 - In the Matter of: Certain Electronic Devices, Including Mobile Phones, Portable Music Players...  

Federal Register 2010, 2011, 2012, 2013

...Devices, Including Mobile Phones, Portable Music Players, and Computers; Notice of Investigation...devices, including mobile phones, portable music players, and computers, by reason of...devices, including mobile phones, portable music players, or computers that infringe...

2010-01-28

48

Inertial electrostatic confinement fusion device with an ion source using a magnetron discharge  

Microsoft Academic Search

An inertial electrostatic confinement (IEC) fusion device is studied for a compact fusion neutron\\/proton source using a built-in magnetron ion source. The addition of an ion source to the IEC fusion device enhances fusion reactions by allowing a lower operating gas pressure and by providing a beam-like ion energy distribution. Under lower gas pressures, charge exchange collisions are reduced, resulting

T. Takamatsu; K. Masuda; T. Kyunai; H. Toku; K. Yoshikawa

2006-01-01

49

Some considerations of cold fusion including the calculation of fusion rates in molecules of hydrogen isotopes  

SciTech Connect

We calculate the fusion reaction rates in molecules of hydrogen isotopes. The rates are calculated analytically (for the first time) as an asymptotic expansion in the ratio of the electron mass to the reduced mass of the nucleii. The fusion rates of the P-D, D-D, and D-T reactions are given for a variable electron mass by a simple analytic formula. However, we do not know any mechanism by which a sufficiently localized electron in solid can have an effective mass' large enough to explain the result of Fleischman and Pons (FP). This calculation indicates that P-D rates should exceed D-D rates for D-D fusion rates less than approximately 10{sup {minus}23} per molecule per second. The D-D fusion rate is enhanced by a factor of 10{sup 5} at 10,000{degree}K if the excited vibrational states are populated with a Boltzmann distribution and the rotational excitations suppressed. The suggestion that experimental results could be explained by bombardment of cold deuterons by kilovolt deuterons is shown to be an unlikely from an energetic point of view. 12 refs., 3 figs., 1 tab.

Cowley, S.C.; Kulsrud, R.M.

1989-11-01

50

Effects of Electrode Shape on Performance Characteristics of a Cylindrical Inertial Electrostatic Confinement Fusion Device  

Microsoft Academic Search

The effects of beam convergence on the fusion reaction rate in the cylindrical inertial electrostatic confinement fusion device are investigated using a two-dimensional simulation code and experiments. It is found from the simulation that the fusion reaction rate increases significantly with an increase of beam convergence; therefore, there is an increase of ion densities at the center region. In the

Yasushi Yamamoto; Ryousaku Kusaba; Takayuki Shirouzu; Nobuyuki Inoue

2001-01-01

51

Numerical modelling of electromagnetic loads on fusion device structures  

NASA Astrophysics Data System (ADS)

In magnetic confinement fusion devices, during abnormal operations (disruptions) the plasma begins to move rapidly towards the vessel wall in a vertical displacement event (VDE), producing plasma current asymmetries, vessel eddy currents and open field line halo currents, each of which can exert potentially damaging forces upon the vessel and in-vessel components. This paper presents a methodology to estimate electromagnetic loads, on three-dimensional conductive structures surrounding the plasma, which arise from the interaction of halo-currents associated to VDEs with a magnetic field of the order of some Tesla needed for plasma confinement. Lorentz forces, calculated by complementary formulations, are used as constraining loads in a linear static structural analysis carried out on a detailed model of the mechanical structures of a representative machine.

Bettini, Paolo; Furno Palumbo, Maurizio; Specogna, Ruben

2014-03-01

52

LN sub 2 cyclic cooling considerations of fusion ignition devices  

SciTech Connect

Three preconceptual design studies have been under way in the United States for compact fusion ignition devices, all of which utilize copper magnets for toroidal field (TF) and poloidal field coils. The proposal is to operate the magnets at liquid nitrogen temperature to minimize the power requirements for the magnets. During each operating pulse, the temperature of he magnet systems is allowed to increase; no active cooling is provided during the pulse. One of the design requirements calls for cooldown between full-power pulses in some reasonable time to proved the capability for some reasonable number of operating pulses per day. A number of devices such as Alcator-A and -C have operated around liquid nitrogen temperature, but these machines have much shorter pulses and produce no neutrons. Therefore, the temperature rise during each pulse is modest, and the cooldown is less of a problem than for an ignited device with burn times of several seconds. The purpose of this study is to develop a simple model to calculate the cooldown rate of a magnet with various cooling surface configurations. The results will be useful in developing a configuration to provide the desired cooling time between pulses, which should be {approximately}1 h or less. This analysis was applied to the inner leg of the TF coil of Ignitor, one of the ignition devices under study. The inner leg is analyzed mainly because it carries higher current densities than the outer leg and the cooling surface area is more restricted. Four cooling configuration options were studies. Here the result are reported of the most practical option in which the cooling channel is inside the TF coil. 3 refs., 1 fig., 1 tab.

Dabiri, A.E. (Oak Ridge National Lab., TN (USA))

1986-01-01

53

Experimental Study of the Iranian Inertial Electrostatic Confinement Fusion Device as a Continuous Neutron Generator  

Microsoft Academic Search

Among many facilities in the field of nuclear fusion devices, inertial electrostatic confinement (IECF) device has the specific\\u000a character of tendency to generate fusion products continuously. Besides the distinctive characteristics, it has become an\\u000a outstanding focus of interest for many scientists because of several applications such as the ability of performing hydrogen\\u000a boron fusion. This paper summarizes primary results of

V. Damideh; A. Sadighzadeh; A. Koohi; A. Aslezaeem; A. Heidarnia; N. Abdollahi; F. Abbasi Davani; R. Damideh

54

78 FR 34132 - Certain Portable Electronic Communications Devices, Including Mobile Phones and Components...  

Federal Register 2010, 2011, 2012, 2013

...Portable Electronic Communications Devices, Including Mobile Phones and Components Thereof; Correction to Notice of Receipt...Portable Electronic Communications Devices, Including Mobile Phones and Components Thereof, DN 2958; the Commission...

2013-06-06

55

Development progresses of radio frequency ion source for neutral beam injector in fusion devices.  

PubMed

A large-area RF (radio frequency)-driven ion source is being developed in Germany for the heating and current drive of an ITER device. Negative hydrogen ion sources are the major components of neutral beam injection systems in future large-scale fusion experiments such as ITER and DEMO. RF ion sources for the production of positive hydrogen (deuterium) ions have been successfully developed for the neutral beam heating systems at IPP (Max-Planck-Institute for Plasma Physics) in Germany. The first long-pulse ion source has been developed successfully with a magnetic bucket plasma generator including a filament heating structure for the first NBI system of the KSTAR tokamak. There is a development plan for an RF ion source at KAERI to extract the positive ions, which can be applied for the KSTAR NBI system and to extract the negative ions for future fusion devices such as the Fusion Neutron Source and Korea-DEMO. The characteristics of RF-driven plasmas and the uniformity of the plasma parameters in the test-RF ion source were investigated initially using an electrostatic probe. PMID:24593580

Chang, D H; Jeong, S H; Kim, T S; Park, M; Lee, K W; In, S R

2014-02-01

56

CONFERENCE REPORT: Summary of the 16th IAEA Technical Meeting on 'Research using Small Fusion Devices'  

NASA Astrophysics Data System (ADS)

Common research topics that are being studied in small, medium and large devices such as H-mode like or improved confinement, turbulence and transport are reported. These included modelling and diagnostic developments for edge and core, to characterize plasma density, temperature, electric potential, plasma flows, turbulence scale, etc. Innovative diagnostic methods were designed and implemented which could be used to develop experiments in small devices (in some cases not possible in large devices due to higher power deposition) to allow a better understanding of plasma edge and core properties. Reports are given addressing research in linear devices that can be used to study particular plasma physics topics relevant for other magnetic confinement devices such as the radial transport and the modelling of self-organized plasma jets involved in spheromak-like plasma formation. Some aspects of the work presented are of interest to the astrophysics community since they are believed to shed light on the basis of the physics of stellar jets. On the dense magnetized plasmas (DMP) topic, the present status of research, operation of new devices, plasma dynamics modelling and diagnostic developments is reported. The main devices presented belong to the class of Z-pinches, mostly plasma foci, and several papers were presented under this topic. The physics of DMP is important both for the main-stream fusion investigations as well as for providing the basis for elaboration of new concepts. New high-current technology introduced in the DMP devices design and construction make these devices nowadays more reliably fitted to various applications and give the possibility to widen the energy range used by them in both directions—to the multi-MJ level facilities and down to miniature plasma focus devices with energy of just a few J.

Gribkov, V.; Van Oost, G.; Malaquias, A.; Herrera, J.

2006-10-01

57

Effects of the Cathode Grid Wires on Fusion Proton Measurements in Inertial-Electrostatic Confinement Devices  

Microsoft Academic Search

Gridded inertial-electrostatic confinement (IEC) de- vices interest fusion researchers owing to their ability to burn advanced fusion fuels and have many near-term applications. In these devices, a high voltage (10-180 kV) accelerates ions radially between nearly transparent electrodes in spherical or cylindrical geometry. In this paper, we report experiments that study fusion reactions within the microchannels formed between the wires

S. Krupakar Murali; John F. Santarius; Gerald L. Kulcinski

2011-01-01

58

Effects of Electrode Shape on Performance Characteristics of a Cylindrical Inertial Electrostatic Confinement Fusion Device  

SciTech Connect

The effects of beam convergence on the fusion reaction rate in the cylindrical inertial electrostatic confinement fusion device are investigated using a two-dimensional simulation code and experiments. It is found from the simulation that the fusion reaction rate increases significantly with an increase of beam convergence; therefore, there is an increase of ion densities at the center region. In the experiments designed to confirm these results using different electrode shapes, the effects of the anode shape are clearly observed.

Yamamoto, Yasushi; Kusaba, Ryousaku; Shirouzu, Takayuki; Inoue, Nobuyuki [Kyoto University (Japan)

2001-05-15

59

Three-Dimensional Modeling of Complex Fusion Devices Using CAD-MCNPX Interface Mengkuo Wang  

E-print Network

Three-Dimensional Modeling of Complex Fusion Devices Using CAD-MCNPX Interface Mengkuo Wang 1 , Timothy J. Tautges 2 , Douglass L. Henderson 3 , Laila El-Guebaly 4 , Xueren Wang 5 1 University, wang@fusion.ucsd.edu MCNPX's [1] geometric modeling capabilities are limited to Boolean combinations

California at San Diego, University of

60

An internal view of the vacuum chamber containing the fusion device, showing two  

E-print Network

are not looking at this as an energy source right now," Danon says. Rather, the most immediate application mayAn internal view of the vacuum chamber containing the fusion device, showing two pyroelectric thought, according to Danon. "Nuclear fusion has been explored as a potential source of power, but we

Danon, Yaron

61

Multilayer mirror based monitors for impurity controls in large fusion reactor type devices  

SciTech Connect

Multilayer Mirror (MLM) based monitors are compact, high throughput diagnostics capable of extracting XUV emissions (the wavelength range including the soft-x-ray and the extreme ultraviolet, 10 {angstrom} to 304 {angstrom}) of impurities from the harsh environment of large fusion reactor type devices. For several years the Plasma Spectroscopy Group at Johns Hopkins University has investigated the application of MLM based XUV spectroscopic diagnostics for magnetically confined fusion plasmas. MLM based monitors have been constructed for and extensively used on DIII-D, Alcator C-mod, TEXT, Phaedrus-T, and CDX-U tokamaks to study the impurity behavior of elements ranging from He to Mo. On ITER MLM based devices would be used to monitor the spectral line emissions from Li I-like to F I-like charge states of Fe, Cr, and Ni, as well as extractors for the bands of emissions from high Z elements such as Mo or W for impurity controls of the fusion plasma. In addition to monitoring the impurity emissions from the main plasma, MLM based devices can also be adapted for radiation measurements of low Z elements in the divertor. The concepts and designs of these MLM based monitors for impurity controls in ITER will be presented. The results of neutron irradiation experiments of the MLMs performed in the Los Alamos Spallation Radiation Effects Facility (LASREF) at the Los Alamos National Laboratory will also be discussed. These preliminary neutron exposure studies show that the dispersive and reflective qualities of the MLMs were not affected in a significant manner.

Regan, S.P.; May, M.J.; Soukhanovskii, V.; Finkenthal, M.; Moos, H.W. [Johns Hopkins Univ., Baltimore, MD (United States). Dept. of Physics and Astronomy

1995-12-31

62

Instrumented posterior lumbar interbody fusion (PLIF) with interbody fusion device (Cage) in degenerative disc disease (DDD): 3 years outcome.  

PubMed

This prospective interventional study carried out at Bangabandhu Sheikh Mujib Medical University and a private hospital in Dhaka, Bangladesh during the period from October 2003 to September 2011. Surgical treatment of degenerative disc disease (DDD) should aim to re-expand the interbody space and stabilize until fusion is complete. The present study conducted to find out the efficacy of using interbody fusion device (Cage) to achieve interbody space re-expansion and fusion in surgical management of DDD. We have performed the interventional study on 53 patients, 42 female and 11 male, with age between 40 to 67 years. All the patients were followed up for 36 to 60 months (average 48 months). Forty seven patients were with spondylolisthesis and 06 with desiccated disc. All subjects were evaluated with regard to immediate and long term complications, radiological fusion and interbody space re-expansion and maintenance. The clinical outcome (pain and disability) was scored by standard pre and postoperative questionnaires. Intrusion, extrusion and migration of the interbody fusion cage were also assessed. Forty seven patients were considered to have satisfactory outcome in at least 36 months follow up. Pseudoarthrosis developed in 04 cases and 06 patients developed complications. In this series posterior lumbar interbody fusion (PLIF) with interbody cage and instrumentation in DDD showed significant fusion rate and maintenance of interbody space. Satisfactory outcome observed in 88.68% cases. PMID:24292314

Ahsan, M K; Hossain, M A; Sakeb, N; Khan, S I; Zaman, N

2013-10-01

63

77 FR 45375 - Certain Liquid Crystal Display Devices, Including Monitors, Televisions, Modules, and Components...  

Federal Register 2010, 2011, 2012, 2013

...INTERNATIONAL TRADE COMMISSION [Investigation Nos. 337-TA-741/749] Certain Liquid Crystal Display Devices, Including Monitors, Televisions, Modules, and Components Thereof; Commission Determination Not To...

2012-07-31

64

77 FR 37067 - Certain Liquid Crystal Display Devices, Including Monitors, Televisions, Modules, and Components...  

Federal Register 2010, 2011, 2012, 2013

...INTERNATIONAL TRADE COMMISSION [Investigation No. 337-TA-741/749] Certain Liquid Crystal Display Devices, Including Monitors, Televisions, Modules, and Components Thereof; Final Determination of No...

2012-06-20

65

47 CFR 15.115 - TV interface devices, including cable system terminal devices.  

Code of Federal Regulations, 2010 CFR

...pamphlet, if a manual is not provided, the types of wires or coaxial cables necessary to ensure that the unit complies with...27. For all other TV interface devices, the wires or coaxial cables used to couple the output signals to the TV...

2010-10-01

66

47 CFR 15.115 - TV interface devices, including cable system terminal devices.  

Code of Federal Regulations, 2013 CFR

...pamphlet, if a manual is not provided, the types of wires or coaxial cables necessary to ensure that the unit complies with...27. For all other TV interface devices, the wires or coaxial cables used to couple the output signals to the TV...

2013-10-01

67

47 CFR 15.115 - TV interface devices, including cable system terminal devices.  

Code of Federal Regulations, 2012 CFR

...pamphlet, if a manual is not provided, the types of wires or coaxial cables necessary to ensure that the unit complies with...27. For all other TV interface devices, the wires or coaxial cables used to couple the output signals to the TV...

2012-10-01

68

47 CFR 15.115 - TV interface devices, including cable system terminal devices.  

Code of Federal Regulations, 2011 CFR

...pamphlet, if a manual is not provided, the types of wires or coaxial cables necessary to ensure that the unit complies with...27. For all other TV interface devices, the wires or coaxial cables used to couple the output signals to the TV...

2011-10-01

69

Photo-fusion reactions in a new compact device for ELI  

NASA Astrophysics Data System (ADS)

In the last few years significant progress on technological, experimental and numerical studies on fusion process in high density and high temperature plasmas produced by a high intensity laser pulse interaction with clusters in a high external applied magnetic field, enable us to propose a compact photo-fusion magnetic device for high neutron production. For the purpose of the project a pulsed magnetic field driver with values up to 110 Tesla has been developed which allows increasing the trapping time of the high density plasma in the device and improving the neutron yield. Numerical simulations show that the proposed device is capable of producing up to 109-1010 neutrons per laser shot with an external magnetic field of 150 Tesla. The proposed device can be used for experiments and numerical code validation concerning different conventional and (or) exotic fusion fuels.

Moustaizis, S. D.; Auvray, P.; Hora, H.; Lalousis, P.; Larour, J.; Mourou, G.

2012-07-01

70

Photo-fusion reactions in a new compact device for ELI  

SciTech Connect

In the last few years significant progress on technological, experimental and numerical studies on fusion process in high density and high temperature plasmas produced by a high intensity laser pulse interaction with clusters in a high external applied magnetic field, enable us to propose a compact photo-fusion magnetic device for high neutron production. For the purpose of the project a pulsed magnetic field driver with values up to 110 Tesla has been developed which allows increasing the trapping time of the high density plasma in the device and improving the neutron yield. Numerical simulations show that the proposed device is capable of producing up to 10{sup 9}-10{sup 10} neutrons per laser shot with an external magnetic field of 150 Tesla. The proposed device can be used for experiments and numerical code validation concerning different conventional and (or) exotic fusion fuels.

Moustaizis, S. D.; Auvray, P.; Hora, H.; Lalousis, P.; Larour, J.; Mourou, G. [Technical University of Crete, Science Department, 73100 Chania, Crete (Greece); LPP-Laboratoire de Physique des Plasmas, Ecole Polytechnique, Palaiseau (France); Department of Theoret. Physics, Univ. New South Wales, Sydney 2052 (Australia); Institute of Electronic Structure and Laser, FORTH, Heraklion (Greece); LPP-Laboratoire de Physique des Plasmas, Ecole Polytechnique, Palaiseau (France); LOA Laboratoire d'Optique Appliquee, ENSTA, Palaiseau Cedex (France)

2012-07-09

71

Optical relay design for an IR imaging diagnostic system in TJ-II fusion device  

NASA Astrophysics Data System (ADS)

The surroundings of a nuclear fusion reactor experiments the presence of magnetic fields, which affects the performance of any diagnostic optical system located nearby. It is therefore necessary to determine with precision the optimum location for the diagnostic and to design magnetically robust optical imaging systems. The purpose of the present optical diagnostic is to measure the temperature dispersion in the vicinity of the NBI (neutral beam injectors) that heat the confined plasma inside the fusion device. The measure is made by processing the information contained in the images of the objects inside the chamber in the 7 to 16 um far infrared wavelength range, through a F2Ba vacuum viewport window. Our main concern is to design the optical relay from this viewport to the IR sensor, a FPA uncooled microbolometer 320x240px, for different axial distances, with a field of view of 24°x18° and 1.3 mrad of IFOV spatial resolution. The proposed optical relay system includes the use of a reflexive relay (aspheric concave mirrors) and a refractive and imaging camera. The system has being corrected for primary aberrations and optimized to allow a future second optical system working in visible range after the mirrors, by including a dichroic beamsplitter.

Ruiz de Galarreta, Carlota; Manzanares Ituarte, Ana; de la Cal Heusch, Eduardo; Liniers, Macarena; Wolfers, Gilles

2012-12-01

72

76 FR 42730 - In the Matter of Certain Univeral Serial Bus (“USB”) Portable Storage Devices, Including USB...  

Federal Register 2010, 2011, 2012, 2013

...Univeral Serial Bus (``USB'') Portable Storage Devices, Including USB Flash Drives and...universal serial bus (``USB'') portable storage devices, including USB flash drives and...universal serial bus (``USB'') portable storage devices, including USB flash drives...

2011-07-19

73

Performance characteristics of an inertial-electrostatic confinement fusion device with magnetron discharge  

Microsoft Academic Search

A magnetron discharge as a built-in ion source for an inertial-electrostatic confinement fusion (IECF) device was experimentally studied aiming at a drastic improvement of fusion reaction rate. With this discharge in the vicinity of the grounded vacuum chamber, produced ions are expected to have almost full energy corresponding to the voltage applied to the central transparent cathode. Also, the magnetron-glow

Kai Masuda; Kiyoshi Yoshikawa; Toshiyuki Mizutani; Teruhisa Takamatsu; Masaki Imoto; Kazunobu Nagasaki; Hisayuki Toku

2003-01-01

74

Simulation of RF-fields in a fusion device  

SciTech Connect

In this paper the problem of scattering off a fusion plasma is approached from the point of view of integral equations. Using the volume equivalence principle an integral equation is derived which describes the electromagnetic fields in a plasma. The equation is discretized with MoM using conforming basis functions. This reduces the problem to solving a dense matrix equation. This can be done iteratively. Each iteration can be sped up using FFTs.

De Witte, Dieter; Bogaert, Ignace; De Zutter, Daniel [Department of Information Technology (INTEC), Ghent University (Belgium); Van Oost, Guido [Department of Applied Physics, Ghent University (Belgium); Van Eester, Dirk [Royal Military Academy, Brussels (Belgium)

2009-11-26

75

Fusion Nuclear Schience Facility-AT: A Material And Component Testing Device  

SciTech Connect

A Fusion Nuclear Science Facility (FNSF) is a necessary complement to ITER, especially in the area of materials and components testing, needed for DEMO design development. FNSF-AT, which takes advantage of advanced tokamak (AT) physics should have neutron wall loading of 1-2 MW/m2, continuous operation for periods of up to two weeks, a duty factor goal of 0.3 per year and an accumulated fluence of 3-6 MW-yr/m2 (~30-60 dpa) in ten years to enable the qualification of structural, blanket and functional materials, components and corresponding ancillary equipment necessary for the design and licensing of a DEMO. Base blankets with a ferritic steel structure and selected tritium blanket materials will be tested and used for the demonstration of tritium sufficiency. Additional test ports at the outboard mid-plane will be reserved for test blankets with advanced designs or exotic materials, and electricity production for integrated high fluence testing in a DT fusion spectrum. FNSF-AT will be designed using conservative implementations of all elements of AT physics to produce 150-300 MW fusion power with modest energy gain (Q<7) in a modest sized normal conducting coil device. It will demonstrate and help to select the DEMO plasma facing, structural, tritium breeding, functional materials and ancillary equipment including diagnostics. It will also demonstrate the necessary tritium fuel cycle, design and cooling of the first wall chamber and divertor components. It will contribute to the knowledge on material qualification, licensing, operational safety and remote maintenance necessary for DEMO design

Wong, C. P.; Chan, V. S.; Garofalo, A. M.; Stambaugh, Ron; Sawan, M.; Kurtz, Richard J.; Merrill, Brad

2012-07-01

76

77 FR 3793 - Certain Liquid Crystal Display Devices, Including Monitors, Televisions, and Modules, and...  

Federal Register 2010, 2011, 2012, 2013

...INTERNATIONAL TRADE COMMISSION [Investigations No. 337-TA-741 and 337-TA-749] Certain Liquid Crystal Display Devices, Including Monitors, Televisions, and Modules, and Components Thereof; Request for Statements on the...

2012-01-25

77

78 FR 63492 - Certain Electronic Devices, Including Mobile Phones and Tablet Computers, and Components Thereof...  

Federal Register 2010, 2011, 2012, 2013

...INTERNATIONAL TRADE COMMISSION [Investigation No. 337-TA-847] Certain Electronic Devices, Including Mobile Phones and Tablet Computers, and Components Thereof; Notice of Request for Statements on the Public Interest AGENCY:...

2013-10-24

78

76 FR 41522 - In the Matter of Certain Electronic Devices, Including Mobile Phones, Mobile Tablets, Portable...  

Federal Register 2010, 2011, 2012, 2013

...Devices, Including Mobile Phones, Mobile Tablets, Portable Music Players, and Computers, and Components Thereof; Notice of...importation of certain mobile phones, mobile tablets, portable music players, and computers. 76 FR 24051 (Apr. 29,...

2011-07-14

79

Microfluidic device for high-yield pairing and fusion of stem cells with somatic cells  

NASA Astrophysics Data System (ADS)

Electro cell fusion has significant potential as a biotechnology tool with applications ranging from antibody production to cellular reprogramming. However due to low fusion efficiency of the conventional electro fusion methodology the true potential of the technique has not been reached. In this paper, we report a new method which takes cell fusion efficiency two orders magnitude higher than the conventional electro fusion method. The new method, based on one-toone pairing, fusion and selection of fused cells was developed using a microfabricated device. The device was composed of two microfluidic channels, a micro slit array and a petri dish integrated with electrodes. The electrodes positioned in each channel were used to generate electric field lines concentrating in the micro slits. Cells were introduced into channels and brought in to contact through the micro slit array using dielectrophoresis. The cells in contact were fused by applying a DC pulse to electrodes. As the electric field lines were concentrated at the micro slits the membrane potential was induced only at the vicinity of the micro slits, namely only at the cell-cell contact point. This mechanism assured the minimum damage to cells in the fusion as well as the ability to control the strength and location of induced membrane potential. We introduced mouse embryonic stem cells and mouse embryonic fibroblasts to the microfluidic channels and demonstrated high-yield fusion (> 80%). Post-fusion study showed the method can generate viable hybrids of stem cells and embryonic fibroblasts. Multinucleated hybrid cells adhering on the chip surface were routinely obtained by using this method and on-chip culturing.

Gel, Murat; Hirano, Kunio; Oana, Hidehiro; Kotera, Hidetoshi; Tada, Takashi; Washizu, Masao

2011-12-01

80

Study of fusion regimes in an inertial electrostatic confinement device using the new eclipse disk diagnostic  

Microsoft Academic Search

New diagnostics are required to understand the physics operation of an inertial electrostatic confinement (IEC) device. In an attempt to understand the fusion source regimes within the IEC device, a new diagnostic called the eclipse disk has been introduced. This diagnostic was used to exploit the byproduct protons' energy difference between the deuterium-deuterium (D-D) and deuterium-an isotope of helium with

S. Krupakar Murali; B. B. Cipiti; J. F. Santarius; G. L. Kulcinski

2006-01-01

81

Dust in fusion devices---a multi-faceted problem connecting high- and low-temperature plasma physics  

Microsoft Academic Search

Small particles with sizes between a few nanometers and a few 10 µm (dust) are formed in fusion devices by plasma surface interaction processes. Though it is not a major problem today, dust is considered a problem that could arise in future long pulse fusion devices. This is primarily due to its radioactivity and due to its very high chemical

J. Winter

2004-01-01

82

Experimental Evaluation of Torsional Fatigue Strength of Welded Bellows and Application to Design of Fusion Device  

Microsoft Academic Search

Torsional fatigue strength of the welded bellows was evaluated experimentally, aiming the application to a port of a fusion device.The welded bellows revealed elastic torsional buckling and spiral distorsion even under a small angle of torsion. Twisting load never leads the welded bellows to fracture easily so far as the angle of torsion is not excessively large, and the welded

Hideyuki TAKATSU; Masahiro YAMAMOTO; Masatsugu SHIMIZU; Kazuo SUZUKI; Tadashi SONOBE; Yuzo HAYASHI; Gen-ichiro MIZUNO

1984-01-01

83

The Potential Profile and its Influence on the Neutron Yield of Inertial Electrostatic Confinement Fusion Device  

Microsoft Academic Search

We have simulated an IECF (inertial electrostatic confinement fusion) device by developing and using a particle code. Because a virtual anode is built up at large current region, which decelerates ions and reduces neutron yield, suppression of this virtual anode by supply of electrons from an additional electrode inside the cathode has been tried in the simulations. The simulation results

K. Noborio; Y. Yamamoto; Y. Ueno; S. Konishi

2005-01-01

84

Effects of Grid Cathode Structure on a Low-Input-Power Inertial Electrostatic Confinement Fusion Device  

Microsoft Academic Search

The effects of grid cathode structure on a low-input-power inertial electrostatic confinement fusion (IECF) device were studied to achieve a high neutron production rate (NPR). An increase in geometric transparency of the grid cathode by decreasing the number of wire rings is known to mean that the recirculation ion current is increased. We expected that this increase would contribute to

Yasuyuki TANIUCHI; Yoshihito MATSUMURA; Katsuyoshi TAIRA; Michiaki UTSUMI; Masami CHIBA; Toshiaki SHIRAKAWA; Masatoshi FUJII

2010-01-01

85

High heat flux experiments of plasma facing components for next fusion devices  

Microsoft Academic Search

To develop plasma facing components (PFC) for the next fusion devices, JAERI has been carrying out high heat flux and high particle flux experiments on the divertor modules and candidate materials in JAERI Electron Beam Irradiation System (JEBIS). (1) To investigate the feasibility and the advantage of a saddle type divertor modules, which has unidirectional (1-D) carbon fiber reinforced carbon

K. Nakamura; M. Akiba; S. Suzuki; K. Satoh; K. Yokoyama; M. Dairaku; M. Araki; Y. Ohara; T. Inoue; Y. Okumura; I. Smid

1993-01-01

86

Anterior Lumbar Interbody Fusion: Two-Year Results with a Modular Interbody Device  

PubMed Central

Study Design Retrospective case series. Purpose To present radiographic outcomes following anterior lumbar interbody fusion (ALIF) utilizing a modular interbody device. Overview of Literature Though multiple anterior lumbar interbody techniques have proven successful in promoting bony fusion, postoperative subsidence remains a frequently reported phenomenon. Methods Forty-three consecutive patients underwent ALIF with (n=30) or without (n=11) supplemental instrumentation. Two patients underwent ALIF to treat failed posterior instrumented fusion. The primary outcome measure was presence of fusion as assessed by computed tomography. Secondary outcome measures were lordosis, intervertebral lordotic angle (ILA), disc height, subsidence, Bridwell fusion grade, technical complications and pain score. Interobserver reliability of radiographic outcome measures was calculated. Results Forty-three patients underwent ALIF of 73 motion segments. ILA and disc height increased over baseline, and this persisted through final follow-up (p<0.01). Solid anterior interbody fusion was present in 71 of 73 motion segments (97%). The amount of new bone formation in the interbody space increased over serial imaging. Subsidence >4 mm occurred in 12% of patients. There were eight surgical complications (19%): one major (reoperation for nonunion/progressive subsidence) and seven minor (five subsidence, two malposition). Conclusions The use of a modular interbody device for ALIF resulted in a high rate of radiographic fusion and a low rate of subsidence. The large endplate and modular design of the device may contribute to a low rate of subsidence as well as maintenance of ILA and lordosis. Previously reported quantitative radiographic outcome measures were found to be more reliable than qualitative or categorical measures. PMID:25346811

Yeoman, Chevas; Chung, Woosik M.; Chappuis, James L; Freedman, Brett

2014-01-01

87

Plasma assessments for the fusion engineering device (FED)  

SciTech Connect

An initial range of plasma assumptions and scenarios has been examined for the US tokamak FED concept. The results suggest that the current FED baseline parameters of R = 4.8 m, B/sub t/ = 3.6 T, a = 1.3 m, b = 2.1 m (D-shape), and I/sub p/ = 4.8 to 5.4 MA are appropriate for achieving its nominal goals of P(fusion) approx. = 180 MW and a plasma Q greater than or equal to to 5 for a pulse length greater than 100 s. However, large uncertainty still exists in the areas of current startup, ion-cyclotron wave launching, influence of plasma shape on achievable beta, impurity control, plasma edge transport, and plasma disruption. Various options and remedies have been suggested to alleviate the impact of the uncertainty on the FED design concept. They appear promising because they can be studied experimentally and are not expected to lead to fundamental design modifications of FED.

Peng, Y.K.M.; Rutherford, P.H.; Lyon, J.F.

1981-01-01

88

Studies of Negative Ion Generation in an Inertial Electrostatic Confinement Fusion Device  

Microsoft Academic Search

The discovery of negative ion generation in Inertial Electrostatic Confinement (IEC) devices [1] has prompted a campaign to extend understanding of negative ion phenomena in IEC devices. Theoretical studies include modeling negative ion physics in IEC devices by adding negative ion generation and propagation to a 1-D computational model of ion and fast neutral currents in IEC devices [2], to

Eric Alderson; John Santarius; Gil Emmert; David Donovan; Gerald Kulcinski

2010-01-01

89

Photovoltaic Device Including A Boron Doping Profile In An I-Type Layer  

DOEpatents

A photovoltaic cell for use in a single junction or multijunction photovoltaic device, which includes a p-type layer of a semiconductor compound including silicon, an i-type layer of an amorphous semiconductor compound including silicon, and an n-type layer of a semiconductor compound including silicon formed on the i-type layer. The i-type layer including an undoped first sublayer formed on the p-type layer, and a boron-doped second sublayer formed on the first sublayer.

Yang, Liyou (Lawrenceville, NJ)

1993-10-26

90

Optimization of compact stellarator configuration as fusion devices  

SciTech Connect

Optimization of the stellarator configuration requires tradeoffs among a large number of physics parameters and engineering constraints. An integrated study of compact stellarator power plants, ARIES-CS, aims at examining these tradeoffs and defining key R and D areas. Configurations with a plasma aspect ratio of A{<=}6 and excellent quasiaxisymmetry (QA) in both two and three field period versions were developed while reducing {alpha}-particle losses to <10%. Stability to linear ideal MHD modes was attained, but at the expense of reduced QA (and increased {alpha}-particle losses) and increased complexity of the plasma shape. Recent experimental results indicate, however, that linear MHD stability limits may not be applicable to stellarators. By utilizing a highly efficient shield-only region in strategic areas, the minimum standoff was reduced by {approx}30%. This allows a comparable reduction in the machine size. The device configuration, assembly, and maintenance procedures appear to impose severe constraints: three distinct approaches were developed, each applicable to a certain blanket concept and/or stellarator configuration. Modular coils are designed to examine the geometric complexity and to understand the constraints imposed by the maximum allowable field, desirable coil-plasma separation, coil-coil spacing, and other coil parameters. A cost-optimization system code has also been developed and will be utilized to assess the tradeoff among physics and engineering constraints in a self-consistent manner in the final phase of the ARIES-CS study.

Najmabadi, Farrokh; Rene Raffray, A.; Ku, Long-Poe; Lyon, James F. [University of California San Diego, La Jolla, California 92093-0438 (United States); Princeton Plasma Physics Laboratory, P.O. Box 451, Princeton, New Jersey 08543 (United States); Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, Tennessee 37831 (United States)

2006-05-15

91

77 FR 64827 - Certain Lighting Control Devices Including Dimmer Switches and Parts Thereof (IV); Final...  

Federal Register 2010, 2011, 2012, 2013

Notice is hereby given that the U.S. International Trade Commission has terminated the above-captioned investigation with a finding of violation of section 337, and has issued a general exclusion order directed against infringing lighting control devices including dimmer switches and parts thereof, and cease and desist orders directed against respondents American Top Electric Corp. (``American......

2012-10-23

92

76 FR 31983 - In the Matter of Certain Electronic Devices, Including Mobile Phones, Portable Music Players, and...  

Federal Register 2010, 2011, 2012, 2013

...Certain Electronic Devices, Including Mobile Phones, Portable Music Players, and Computers; Notice of Commission Determination...certain electronic devices, including mobile phones, portable music players, and computers by reason of infringement of...

2011-06-02

93

Deuterium Uptake in Magnetic-Fusion Devices with Lithium-Conditioned Carbon Walls  

SciTech Connect

Lithium wall conditioning has lowered hydrogenic recycling and dramatically improved plasma performance in many magnetic-fusion devices. In this Letter, we report quantum-classical atomistic simulations and laboratory experiments that elucidate the roles of lithium and oxygen in the uptake of hydrogen in amorphous carbon. Surprisingly, we show that lithium creates a high oxygen concentration on a carbon surface when bombarded by deuterium. Furthermore, surface oxygen, rather than lithium, plays the key role in trapping hydrogen.

Krstic, Predrag S. [University of Tennessee (UTK) and Oak Ridge National Laboratory (ORNL); Allain, J. P. [Purdue University; Taylor, C. N. [Purdue University; Dadras, J. [UTK/Univ. California, Los Angeles; Maeda, S. [Kyoto University, Fukui Institute for Fundamental Chemistry, Japan; Morokuma, K. [Kyoto University, Fukui Institute for Fundamental Chemistry, Japan; Jakowski, J. [National Inst. Computational Sciences, UTK; Allouche, A. [PIM/CNRS/Aix-Marseille University, Marseille, France; Baylor, Larry R [ORNL; Skinner, C. H. [Princeton Plasma Physics Laboratory (PPPL)

2013-01-01

94

Edge-plasma models and characteristics for magnetic fusion energy devices  

Microsoft Academic Search

A description is given of the models and resulting characteristics of the plasma adjacent to material surfaces that comprise the divertor and first wall of magnetic fusion energy devices under normal operation conditions. This thin edge-plasma region begins a short distance inside of the so-called separatrix, which divides the core domain of confined magnetic field lines from the scrape-off layer

T. D. Rognlien; M. E. Rensink

2002-01-01

95

Characterization of charcoals for helium cryopumping in fusion devices  

SciTech Connect

The capability of charcoal as a sorbent for helium at cryogenic temperatures depends upon charcoal characteristics that are not well understood. Previous work by the authors has indicated that the charcoals' pumping capability for helium depends as much on their source as on their particle size distributions. To develop a correlation between the physical characteristics of charcoal and helium pumping performance, different charcoals based on wood, coal, coconut, and a petroleum by-product were obtained from commercial sources. They were bonded to an aluminum substrate, and cooled to liquid-helium temperatures in a vacuum chamber. The helium pumping speed at constant throughput versus quantity of helium absorbed was measured for each charcoal grade. Porosimetry measurements on each charcoal grade using nitrogen as the sorbent gas were made that included total surface area, adsorption and desorption isotherms, and pore area and pore volume distributions. Significant differences in helium pumping performance and in pore size distribution were observed. Comparisons are made between helium pumping performance and charcoal characteristics and a possible correlation is identified.

Sedgley, D.W.; Tobin, A.G.; Batzer, T.H.; Call, W.R.

1987-07-01

96

An in-situ accelerator-based diagnostic for plasma-material interactions science in magnetic fusion devices  

E-print Network

Plasma-material interactions (PMI) in magnetic fusion devices such as fuel retention, material erosion and redeposition, and material mixing present significant scientific and engineering challenges, particularly for the ...

Hartwig, Zachary Seth

2014-01-01

97

Design of an Ion Source for {sup 3}He Fusion in a Low Pressure IEC Device  

SciTech Connect

Recent developments in helicon ion sources and Inertial Electrostatic Confinement (IEC) device performance at UW-Madison have enabled low pressure (< 50 {mu}torr, 6.7 mPa) operating conditions that should allow the {sup 3}He-{sup 3}He fusion reaction to be observed in an IEC device. An ion source capable of delivering a {approx} 10 mA {sup 3}He ion beam into an IEC device with minimal neutral gas flow has been designed and tested. Furthermore, a new IEC device that has never been operated with deuterium has been constructed to avoid D-{sup 3}He protons from obstructing the {sup 3}He-{sup 3}He reaction product spectrum, and to minimize Penning ionization of deuterium by excited helium, which in the past is suspected to have limited the ionized density of He. These developments make it possible to study beam-background {sup 3}He-{sup 3}He fusion reactions with > 300 mA recirculating ion currents.

Piefer, Gregory R.; Santarius, John F.; Ashley, Robert P.; Kulcinski, Gerald L. [University of Wisconsin-Madison (United States)

2005-05-15

98

Confinement Scaling of Magnetically-Channeled SIEC Array (MCSA) Fusion Device  

NASA Astrophysics Data System (ADS)

A spherical inertia electrostatic confinement (SIEC) is one of the most attractive fusion concepts because of its simple structure. It requires only a spherical meshed grid in a vacuum chamber and yields 108 neutrons/s from deuterium plasma in small laboratory devices. However, detailed studies such as stability analysis and development of special ion beam sources are required for improving the performance of SIEC. After certain improvements to avoid instabilities and to integrate sharp-focusing ion sources, an improved SIEC might first be utilized for various ion beam or neutron beam applications. However, a proof of principle experiment to demonstrate the basic physics (recirculation type stable cusp confinement and end cone loss re-trapping in multiple units) of this concept is required to demonstrate the feasibility of this approach for development as a fusion power reactor. Such a POP experiment is the objective of this proposal. High-temperature plasma (SIEC in low-field region) is confined by stable magnetic configuration while radial losses are minimized by channeling flow is into neighboring IEC regions. Confinement time can be very long due to an extremely large effective mirror ratio resulting in higher efficiency than a single SIEC. Fusion-product heating and ignition is also possible using collimating properties of the confinement field. Predicted scaling is linear with radius of device, possibly allowing break-even machine at a few meter radius with a several Tesla field.

Miley, George; Stubbers, Robert; Webber, Jason; Momota, Hiromu

2003-10-01

99

In vitro corrosion resistance of porous NiTi intervertebral fusion devices  

NASA Astrophysics Data System (ADS)

Porous titanium-nickel (PTN) intervertebral fusion devices, produced by self-propagating high-temperature synthesis, represent an alternative to traditional long-term implants in the orthopaedic field. PTN promotes tissue ingrowth and has succeeded short-term and long-term biocompatibility in vivo testing. In this in vitro study, the PTN morphology was characterized using microfocus computer tomography (?CT) in order to calculate the active PTN surface. Potentiodynamic polarization testing was then performed to evaluate the in vitro corrosion resistance of PTN devices in Hanks' based salt solution. Direct coupling experiments of PTN with Ti6Al4V were also performed in order to establish the galvanic corrosion resistance of PTN intervertebral implants in the presence of potential Ti6Al4V supplemental fixation devices. Compared to the behaviour of other orthopaedic biomaterials and solid NiTi devices, PTN devices showed a level of corrosion resistance that is comparable to other NiTi devices and acceptable for the intended orthopaedic application. Further improvement of the corrosion resistance is still possible by specific electrochemical surface treatments.

Schrooten, Jan; Assad, Michel; Van Humbeeck, Jan; Leroux, Michel A.

2007-02-01

100

Detection of highly enriched uranium and tungsten surface damage studies using a pulsed inertial electrostatic confinement fusion device  

Microsoft Academic Search

The research in this thesis examines two applications of a pulsed Inertial Electrostatic Confinement (EEC) fusion device: detection of highly enriched uranium (HEU) and tungsten surface damage studies. In order to complete this thesis, a pulsed IEC device was developed that is capable of generating converging ion pulses with widths ranging from 0.1 to 5 ms at frequencies between 1

Ross F. Radel

2007-01-01

101

Optimizing Neutron Production Rates from D-D Fusion in an Inertial Electrostatic Confinement Device  

SciTech Connect

Detection of explosives has been identified as a near term commercial opportunity for using a fusion plasma. Typical explosive compositions contain low Z material (C, N, O) which are not easily detected using conventional x-rays or metal detectors. However, 2.45 MeV neutrons produced in a D-D fusion reaction can be used for detection of explosives or other clandestine materials in suitcases, packages, or shipping containers.Steady-state D-D operation is possible using an Inertial Electrostatic Confinement (IEC) fusion device. The University of Wisconsin IEC device has produced D-D neutrons at 1.8 x 10{sup 8} neutrons/second at a true cathode voltage of 166 kV and a meter current of 68 mA. These neutron production rates are approaching the levels required for the detection of explosives. In order to increase and optimize the neutron production rate in the IEC device, experiments were performed altering the cathode's size (diameter), geometry, and material composition. Preliminary results indicate that significant differences in neutron production rates are not achieved by altering the geometry or material composition of the cathode. However, the neutron production rate was found to increase approximately 20% by doubling the cathode's diameter from 10 cm to 20 cm. In addition, increasing the cathode voltage from 34 kV to 94 kV at a meter current of 30 mA increased the neutron production rate from 1.24 x 10{sup 6} n/s to 2.83 x 10{sup 7} n/s.

Wehmeyer, A.L.; Radel, R.F.; Kulcinski, G.L. [University of Wisconsin-Madison (United States)

2005-05-15

102

Analysis of Fast Neutral Particles in Inertial Electrostatic Confinement Fusion Devices  

NASA Astrophysics Data System (ADS)

A neutral particle analyzer was engineered specifically for inertial electrostatic confinement (IEC) fusion devices for the first time and particularly for studies with relevance to operation with helium-3, an advanced fusion fuel. For experiments with helium, this technique yields energy distributions of escaping fast neutral particles produced by atomic and molecular processes between energetic ions and background gas, as well as the line-of-sight-averaged energy distributions of fast ions. The setup uses a 10 nm carbon foil as a stripping target for incident fast neutral particles and cylindrical electrodes with a variable relative voltage for deflecting ions of a specific energy per unit charge into a continuous electron multiplier. The new diagnostic can be used to study neutral particles with kinetic energies between 5 and 170 keV, with a measured energy resolution of 2-4% between 5 and 30 keV. Initial neutral particle analysis experiments have been performed at cathode voltages up to 60 kV for IEC devices in the glow discharge, external-ion-source and filament-assisted source plasma configurations, with both helium-4 and deuterium gas. Comparisons between experimentally determined neutral-particle energy distributions and predictions by the VICTER and HeVICTER integral-transport numerical codes on spherically convergent ion flow in IEC devices show that the codes do not capture many details of the relevant physics. For helium-4 experiments in the external-ion-source mode, the energy distributions were confirmed to be significantly harder at 0.2 millitorr than at 5 millitorr, which is essential for the prospects of the configuration for increasing helium-3 fusion rates.

Becerra Toledo, Gabriel E.

103

Development of accelerator based spatially resolved ion beam analysis techniques for the study of plasma materials interactions in magnetic fusion devices  

E-print Network

Plasma-material interactions (PMI) in magnetic fusion devices pose significant scientific and engineering challenges for the development of steady-state fusion power reactors. Understanding PMI is crucial for the develpment ...

Barnard, Harold Salvadore

2014-01-01

104

One Dimensional Simulation of an Inertial Electrostatic Confinement Fusion Device at Low Gas Pressure Operation  

SciTech Connect

Using a 1-D particle code, we have analyzed characteristics of an Inertial Electrostatic Confinement Fusion device with external ion source which is added to enable low pressure operation. When the pressure becomes low, though neutron yield decreases, the decreasing amount is less than estimated from the decrease in background (target) gas density and it is confirmed that ions are accelerated efficiently with little energy loss through charge-exchange collision with background gas at low pressure. And when the pressure is lower than 0.05Pa, almost all injected ions reach to the cathode and it is expected that applying high geometrical transparency enhances accumulation of ion and enlarges neutron yield.

Noborio, Kazuyuki; Yamamoto, Yasushi; Konishi, Satoshi [Kyoto University (Japan)

2005-05-15

105

Scaling, stability, and fusion mechanisms. Studies using plasma focus devices from tens of kilojoules to tenth of joules  

SciTech Connect

Fusion studies using plasma focus devices from tens of kilojoules to less than one joule performed at the Chilean Nuclear Energy Commission are presented. The similarity of the physical behavior and the scaling observed in these machines are emphasized. Experiments on actual devices show that scaling holds at least through six order of magnitude. In particular all of these devices, from the largest to the smallest, keep the same quantity of energy per particle. Therefore, fusion reactions are possible to be obtained in ultraminiature devices (driven by generators of 0.1 J), as they are in the bigger devices (driven by generators of 1 MJ). However, the stability of the plasma depends on the size and energy of the device.

Soto, Leopoldo; Pavez, Cristian; Moreno, Jose; Cardenas, Miguel [Comision Chilena de Energia Nuclear, Casilla 188-D, Santiago (Chile); Center for Research and Applications in Plasma Physics and Pulsed Power, P4 (Chile); Tarifeno, Ariel [Center for Research and Applications in Plasma Physics and Pulsed Power, P4 (Chile); Universidad de Concepcion (Chile)

2009-01-21

106

High dynamic range imaging on mobile devices using fusion of multiexposure images  

NASA Astrophysics Data System (ADS)

Because the real world scenes have a high dynamic range which exceeds the range of the imaging devices, the captured images sometimes contain under-exposed and saturated regions. In this paper, we propose a simple but effective method to achieve high dynamic range (HDR) rendering results from three multiexposure images comprising under-, normal-, and over-exposure. First, we generate the weight function, for the fusion of multiexposure images, according to the brightness. Then, we employ the bilateral filter-based retouching to enhance image details, especially in the dark regions. Experimental results demonstrate that the proposed method produces clear details in images and achieves natural HDR rendering results on mobile imaging devices.

Jung, Cheolkon; Yang, Yanru; Jiao, Licheng

2013-10-01

107

Study of Fuel Ratios on the Fusion Reactivity in an Inertial Electrostatic Confinement Device Using a Residual Gas Analyzer  

Microsoft Academic Search

Gridded Inertial Electrostatic confinement (IEC) devices are of interest due to their flexibility in burning advanced fuels,\\u000a their tuning ability of the applied voltage to the reaction cross-section. Although this device is not suitable for power\\u000a production in its present form, it does have several near term applications. The number of applications of this device increases\\u000a with increasing fusion reactivity.

S. Krupakar Murali; John F. Santarius; Gerald L. Kulcinski

2009-01-01

108

Ion Extraction from a Helicon Plasma Source for an Inertial Electrostatic Confinement Fusion Device  

NASA Astrophysics Data System (ADS)

HELIOS, an inertial electrostatic confinement (IEC) fusion device designed for advanced fuel studies [1], uses an external helicon plasma source, from which ions are extracted and subsequently accelerated radially into an electrostatic potential well set up by a semi-transparent cathode grid inside a spherical chamber. A campaign is underway to raise fusion rates to allow for diagnostic studies of IEC physics with helium-3 fuel, in order to benchmark the single-atomic-species formalism of VICTER, a Volterra integral-equation code on spherically convergent ion flow [2]. The helicon plasma has been characterized through double probe measurements of plasma density and electron temperature for various rf antenna and magnetic field geometries. Measurements of the extracted ion current using a witness plate and a Faraday cup are also presented.[4pt] [1] G.R. Piefer et al., Fusion Sci. Technol. 47, 1255 (2005).[0pt] [2] G.A. Emmert and J.F. Santarius, Phys. Plasmas 17, 013502 (2010).

Becerra, Gabriel; Kulcinski, Gerald; Santarius, John

2012-10-01

109

Improved Inertial Electrostatic Confinement Device for ^3He-^3He Fusion  

NASA Astrophysics Data System (ADS)

Ions in inertial electrostatic confinement (IEC) systems are accelerated radially by an electrostatic field between two spherical grids, a configuration in which ^3He-^3He fusion has previously been demonstrated as part of the advanced fuels program at the University of Wisconsin [1]. A campaign is underway to enhance the experimental setup, in order to sustain cathode voltages beyond 200 kV. Additionally, the helicon plasma source and its ion extraction system are being upgraded to deliver ion currents of ˜60 mA. These improvements will help achieve the goal of significantly raising the ^3He-^3He fusion rates, to allow for a detailed diagnostic study of IEC physics with helium-3 fuel, as well as a direct comparison with a theoretical model [2]. Initial results will be presented. [4pt] [1] G.R. Piefer, ``Performance of a Low-Pressure, Helicon Driven IEC 3He Fusion Device,'' Ph.D. thesis, University of Wisconsin-Madison (2006). [2] G.A. Emmert and J.F. Santarius, ``Atomic and molecular effects on spherically convergent ion flow. I. Single atomic species,'' Physics of Plasmas 17, 013502 (2010).

Becerra, Gabriel; Santarius, John; Kulcinski, Gerald

2010-11-01

110

Self-organizing plasma behavior in multiple grid IEC fusion devices for propulsion  

NASA Astrophysics Data System (ADS)

Inertial Electrostatic Confinement, IEC, of charged particles for the purpose of producing fusion energy is a low mass alternative to more traditional magnetic and inertial confinement fusion schemes. Experimental fusion production and energy efficiency in IEC devices to date has been hindered by confinement limitations. Analysis of the major loss mechanisms suggests that the low pressure beam-beam interaction regime holds the most promise for improved efficiency operation. Numerical simulation of multiple grid schemes shows greatly increased confinement times over contemporary single grid designs by electrostatic focusing of the ion beams. An analytical model of this focusing is presented. With the increased confinement, beams self-organize from a uniform condition into bunches that oscillate at the bounce frequency. The bunches from neighboring beams are then observed to synchronize with each other. Analysis of the anisotropic collisional dynamics responsible for the synchronization is presented. The importance of focusing and density on the beam dynamics are examined. Further, this synchronization appears to modify the particle distribution so as to maintain the non-maxwellian, beam-like energy profile within a bunch. The ability of synchronization to modify and counter-act the thermalization process is examined analytically at the 2-body interaction level and as a conglomeration of particles via numerical simulation. Detailed description of the experiment under development at MIT to investigate the synchronization phenomenon is presented.

McGuire, Thomas; Dietrich, Carl; Sedwick, Raymond

2004-11-01

111

Study of fusion regimes in an inertial electrostatic confinement device using the new eclipse disk diagnostic  

SciTech Connect

New diagnostics are required to understand the physics operation of an inertial electrostatic confinement (IEC) device. In an attempt to understand the fusion source regimes within the IEC device, a new diagnostic called the eclipse disk has been introduced. This diagnostic was used to exploit the byproduct protons' energy difference between the deuterium-deuterium (D-D) and deuterium--an isotope of helium with two protons and one neutron (D-{sup 3}He) reactions to study the contributions of the protons generated from various source regimes. These source regimes are divided into five categories namely: converged core, embedded, beam background, volume, and wall-surface sources. The eclipse disk diagnostic has provided the first confirmed evidence that D-{sup 3}He reactions are predominantly embedded reactions. It has been observed that at the present operating power levels (6-10 kW) most of the D-D reactions occur in the volume of the chamber caused by the charge exchanged neutrals, and the converged core contribution is significant only for D-D reactions. Since the branching ratio for the proton and neutron generation in a D-D fusion reaction is {approx}50%, it is inferred that the proton to neutron count ratio is a better parameter to monitor than either proton or neutron counts measured alone while studying the source regimes. This parameter may also be used for studying the potential wells within the cathode grid.

Murali, S. Krupakar; Cipiti, B.B.; Santarius, J.F.; Kulcinski, G.L. [Fusion Technology Institute, University of Wisconsin, 1500 Engineering Drive, Madison, Wisconsin 53706 (United States)

2006-05-15

112

Confinement of ions in an inertial electrostatic confinement fusion (IECF) device and its influence on neutron production rate  

Microsoft Academic Search

Using a one-dimensional particle code, low pressure and large current discharge in an inertial electrostatic confinement fusion (IECF) device has been simulated, and confinement level of ions and the neutron yield through beam–beam fusion have been investigated.From the calculation of low-pressure operation, it is clear that the averaged life span of ions is extended but converges to a value corresponding

Kazuyuki Noborio; Yasushi Yamamoto; Yukihisa Ueno; Satoshi Konishi

2006-01-01

113

Kits Including 3-D Ultrasound Imaging Catheters, Connectable Deployable Tools and Deployment Devices for Use in Deployment of Such Tools.  

National Technical Information Service (NTIS)

A kit for use in ultrasound imaging can include a deployment device configured for partial insertion in vivo, a 3-D imaging catheter, moveably coupled to the deployment device including a 2D ultrasound transducer phased array mounted thereon and configure...

E. D. Light, F. Angle, S. W. Smith, W. Lee

2004-01-01

114

Generalized Generators of Very-High-Frequency Gravitational Waves Including Ring Devices  

NASA Astrophysics Data System (ADS)

A number of researchers have previously proposed methods of generating very-high frequency gravitational waves (VHFGWs) using various interactions and mechanisms. These included mechanical devices, electromagnetic actuators, film bulk acoustic resonators (FBARs) using magnetron excitation, and nuclear explosions. In most cases the generated VHFGW power is a minute fraction of the input power needed to create the required excitation. Only on using a nuclear interaction is the output power significant; however, this appears not to be a practical generation method that can potentially achieve wide usage, at least in the near future. When a number of sources interfere constructively the amplitudes add in direct proportion to the number of radiation-element pairs or sources, N, and the radiation pattern narrows correspondingly in proportion to 1/N. Thus, the generated radiation flux (power per unit cross-sectional area) is proportional to the square of the number of sources or radiation element pairs, N2. Therefore, far greater GW power is obtained by using a larger number of smaller sources (consisting of mass pairs) excited (or "jerked") in phase rather than by using a smaller number of large excited (jerked) masses. The present paper examines the consequences of this scaling law to find how to optimize the generation of VHFGW power from a general set of jerked masses so that the result derives from the combination of all the individual excitations. Extreme cases that can be readily achieved using conventional known technology are firstly to jerk a set of atomic nuclei in phase, and secondly to jerk a set of electrons in phase. The former case uses most of the available mass and the second case sacrifices the excitations available from the masses of the corresponding nuclei. Specific devices, consisting of a ring or tube formed of rings of infra-red-excited molecules or electrons, are suggested. Algebraic and numerical estimates are given of the corresponding VHFGW flux produced by these devices under energizing power. For the multi-ring design, theoretical estimates of the GW flux under optimum conditions reach values on the order of 1 ?W. These novel designs may possibly be the most efficient and practical laboratory-based GW generators suggested so far, a significant advance because of the well-known difficulty of generating GW having significant amplitude.

Woods, R. C.; Baker, R. M. L.

2009-03-01

115

The Development of LITER - a Lithium Evaporator for Use in Fusion Devices  

NASA Astrophysics Data System (ADS)

An evaporator to be used for the deposition of elemental lithium onto the plasma facing components of fusion devices has undergone several stages of design, evaluation and development. A 150 Watt prototype evaporator with a modest 10 gram reservoir was first tested in the laboratory before it was successfully employed on the CDX-U device in a horizontally-pointing geometry. Drawing on that experience, the prototype evaporator design then evolved through several stages as its reservoir capacity was increased to 50 to 100 grams, its power consumption increased to about 300 Watts and its pointing-orientation changed from horizontal to vertically-downward so that it could be used to coat the lower divertor in the NSTX device. These design changes were dictated from both laboratory experience and from practical experience on NSTX. The most challenging problems associated with the evaporator have been the need to achieve reasonable rates of evaporation (1 to 100 mg/ min) at operating temperatures in the range of 500 C to 700 C while avoiding the uncontrolled wetting of the lithium onto external regions of the evaporator. The design and performance of the evaporator at each stage of its development will be summarized and discussed in detail.

Mansfield, D. K.; Kugel, H. W.; Kaita, R.; Majeski, R. P.; Zakharov, L.; Bell, M.; Bennet, T.; Guttadora, L.; Jurcyznski, S.; Provost, T.; Taylor, J.; Timberlake, J.

2006-10-01

116

Overall Characteristics of 9 kW Class Helium Refrigerator for Experimental Fusion Device  

NASA Astrophysics Data System (ADS)

The cryogenic system for the experimental fusion device, LHD has an equivalent refrigeration capacity of 9.1 kW at 4.4 K, and will refrigerate all sets of superconducting coils, their supporting structures, superconducting bus-lines and current leads. Eight sets of oil injected screw-type compressors with the massflow rate of 1100 g/s are equipped. Massflow rate to coldbox was controlled to 700 g/s, and the other of 400 g/s was bypassed. To minimize the bypass flow and to reduce the power consumption, overall operating characteristics of the helium refrigerator were investigated in this report. A power consumption of 500 kW was decreased by reducing the massflow rate of 200 g/s in the bypass circuit.

Yamada, S.; Moriuchi, S.; Maekawa, R.; Noguchi, M.; Kuramochi, K.; Kishi, T.; Mito, T.

2006-06-01

117

Measurement of Ion Energy Distribution in a Cylindrical Inertial Electrostatic Confinement Fusion (C-IECF) Device  

SciTech Connect

In recent researches, an assisted glow discharge experiment using an external ion source has been tried to reduce operation gas pressure. As results, operating gas pressure has been successfully reduced from 1.5 Pa to 0.3 Pa, and the neutron production rate has increased.These results are considered to be due to an increase of ion energy. However, it is necessary to measure the ion energy distribution of the Cylindrical Inertial Electrostatic Confinement Fusion (C-IECF) device in order to confirm this. To do this, we have measured the distribution of the neutral particle beam energy (relative to ion energy distribution). These experimental results demonstrate that a decrease of operation gas pressure (from 1.7 Pa to 0.3 Pa) contributes to the increase in ion energy.

Ueno, Yukihisa; Tomizawa, Takahito; Yamamoto, Yasushi [Kyoto University (Japan)

2005-05-15

118

Recent efforts toward developing a transcriptional framework for a large library of composable devices include the creation of  

E-print Network

devices include the creation of synthetic transcriptional modifiers by fusing effector domains to zinc of organisms8,10­13. This mechanism is attractive for engineering a large library of devices in mammalian cells Hall1,2, Zhen Xie5,6, Yinqing Li7 & Ron Weiss1,2,7 A key obstacle to creating sophisticated genetic

Cai, Long

119

Effects of Grid Structures and Dielectric Materials of the Holder in an Inertial Electrostatic Confinement (IEC) Fusion Device  

Microsoft Academic Search

An inertial electrostatic confinement fusion device modeling has been carried out. Finite element method is used in a 3D media\\u000a in order to identify the potential and electrical fields inside the device. The effects of different materials on the electrostatic\\u000a features are found. In addition, different geometric arrangements for cathode sphere (i.e. inner grid) are considered for\\u000a the determination of

E. KurtS; S. Arslan; M. E. Güven

120

(Critical topics of plasma facing materials/plasma facing component data for the next step fusion devices)  

SciTech Connect

The Unites States-Japan Workshop P-165 brought together approximately 60 scientists and engineers to discuss critical topics of plasma facing materials and components for the next-step fusion device. In addition to the United States and Japanese participants, there were several guest attendees from Europe. The international makeup of the participants greatly enhanced the success of the workshop. The author jointly chaired a workshop session entitled Impact of Neutron Effects to Plasma Facing Materials and Plasma Facing Component (PFC) Feasibilities for the International Thermonuclear Experimental Reactor (ITER),'' and presented an overview paper on neutron effects and materials selection for the next-step plasma facing devices. The author presented his work on the effects of neutron irradiation on graphites and carbon-carbon (c/c) composite materials, which are strong candidate materials for PFC's in ITER. The workshop addressed many issues of current concern to the PFC/PFM community including: plasma erosion of PFM's; trapping/detrapping of hydrogen isotopes; large machine operating experience; and extent of the materials database.

Burchell, T.D.

1991-01-04

121

Optimization and Characterization of a Helicon Ion Source on an Inertial Electrostatic Confinement Device for Helium-3 Fusion  

NASA Astrophysics Data System (ADS)

HELIOS is an inertial electrostatic confinement (IEC) fusion device designed for ^3He-^3He fusion studies as part of the advanced fuels program at the University of Wisconsin [1]. HELIOS uses a helicon plasma as a source of ions, which are subsequently accelerated radially to fusion energies by the electrostatic field between the spherical chamber wall and a concentric cathode grid. The experimental setup, in which ^3He-^3He fusion in an IEC system has previously been demonstrated, has since been upgraded to raise fusion rates to allow for diagnostic studies of IEC physics with helium-3 fuel, in order to benchmark the single-atomic-species formalism of a numerical code on spherically convergent ion flow [2]. The helicon ion source has been characterized through double probe measurements of plasma density and electron temperature for various rf antenna and magnetic field geometries and upgraded to deliver higher ion currents.[4pt] [1] G.R. Piefer et al., Fusion Sci. Technol. 47, 1255 (2005).[0pt] [2] G.A. Emmert and J.F. Santarius, Phys. Plasmas 17, 013502 (2010).

Becerra, Gabriel; Kulcinski, Gerald; Santarius, John

2011-11-01

122

Practical Calculation of Nuclear Fusion Power for a Toroidal Plasma Device with Magnetic Confinement  

Microsoft Academic Search

An algorithm has been developed and realized as a FORTRAN code to calculate the volume integral power of a magnetic confinement nuclear fusion reactor and the fusion rate function in a general case taking as input data the nuclei energy distributions, fusion cross-sections and the magnetic surface geometry. Two fast and simple analytic models of practical magnetic flux surface shapes

P. R. Goncharov

123

Thermal modeling of phase change solidification in thermal control devices including natural convection effects  

NASA Technical Reports Server (NTRS)

Natural convection effects in phase change thermal control devices were studied. A mathematical model was developed to evaluate natural convection effects in a phase change test cell undergoing solidification. Although natural convection effects are minimized in flight spacecraft, all phase change devices are ground tested. The mathematical approach to the problem was to first develop a transient two-dimensional conduction heat transfer model for the solidification of a normal paraffin of finite geometry. Next, a transient two-dimensional model was developed for the solidification of the same paraffin by a combined conduction-natural-convection heat transfer model. Throughout the study, n-hexadecane (n-C16H34) was used as the phase-change material in both the theoretical and the experimental work. The models were based on the transient two-dimensional finite difference solutions of the energy, continuity, and momentum equations.

Ukanwa, A. O.; Stermole, F. J.; Golden, J. O.

1972-01-01

124

P and n-type microcrystalline semiconductor alloy material including band gap widening elements, devices utilizing same  

DOEpatents

An n-type microcrystalline semiconductor alloy material including a band gap widening element; a method of fabricating p-type microcrystalline semiconductor alloy material including a band gap widening element; and electronic and photovoltaic devices incorporating said n-type and p-type materials.

Guha, Subhendu (Troy, MI); Ovshinsky, Stanford R. (Bloomfield Hills, MI)

1988-10-04

125

Unified theory for inhomogeneous thermoelectric generators and coolers including multistage devices.  

PubMed

A novel generalized Lagrange multiplier method for functional optimization with inclusion of subsidiary conditions is presented and applied to the optimization of material distributions in thermoelectric converters. Multistaged devices are considered within the same formalism by inclusion of position-dependent electric current in the legs leading to a modified thermoelectric equation. Previous analytical solutions for maximized efficiencies for generators and coolers obtained by Sherman [J. Appl. Phys. 31, 1 (1960)], Snyder [Phys. Rev. B 86, 045202 (2012)], and Seifert et al. [Phys. Status Solidi A 207, 760 (2010)] by a method of local optimization of reduced efficiencies are recovered by independent proof. The outstanding maximization problems for generated electric power and cooling power can be solved swiftly numerically by solution of a differential equation-system obtained within the new formalism. As far as suitable materials are available, the inhomogeneous TE converters can have increased performance by use of purely temperature-dependent material properties in the thermoelectric legs or by use of purely spatial variation of material properties or by a combination of both. It turns out that the optimization domain is larger for the second kind of device which can, thus, outperform the first kind of device. PMID:23214902

Gerstenmaier, York Christian; Wachutka, Gerhard

2012-11-01

126

Thermal-fatigue properties of coated materials for fusion device applications  

SciTech Connect

The adherence of plasma sprayed coatings of TiC, VC, TiB/sub 2/ and B on substrates of Cu, 316 SS, Mo, Ta and Poco AXF-5Q artificial graphite has been evaluated in a pulsed electron beam, thermal fatigue environment. The materials are candidates for application as limiter and armor components of tokamak fusion devices. Up to 500 cycles of heating at power densities of 1.5 kW/cm/sup 2/ for 1.5 sec. were used. Materials were tested both in the as-sprayed (19 to 33% porosity) condition and after hot isostatic pressing (HIP) to increase coating density. Some (e.g. TiC on Mo and Ta) showed good survivability in both the as-sprayed and HIP densified conditions. TiB/sub 2/ on Mo and Ta and VC on Poco graphite were improved while TiC + V on Mo and Ta were degraded by the HIP treatment.

Mullendore, A.W.; Whitley, J.B.; Mattox, D.M.

1981-01-01

127

III-V/Si hybrid photonic devices by direct fusion bonding  

PubMed Central

Monolithic integration of III-V compound semiconductors on silicon is highly sought after for high-speed, low-power-consumption silicon photonics and low-cost, light-weight photovoltaics. Here we present a GaAs/Si direct fusion bonding technique to provide highly conductive and transparent heterojunctions by heterointerfacial band engineering in relation to doping concentrations. Metal- and oxide-free GaAs/Si ohmic heterojunctions have been formed at 300°C; sufficiently low to inhibit active material degradation. We have demonstrated 1.3 ?m InAs/GaAs quantum dot lasers on Si substrates with the lowest threshold current density of any laser on Si to date, and AlGaAs/Si dual-junction solar cells, by p-GaAs/p-Si and p-GaAs/n-Si bonding, respectively. Our direct semiconductor bonding technique opens up a new pathway for realizing ultrahigh efficiency multijunction solar cells with ideal bandgap combinations that are free from lattice-match restrictions required in conventional heteroepitaxy, as well as enabling the creation of novel high performance and practical optoelectronic devices by III-V/Si hybrid integration. PMID:22470842

Tanabe, Katsuaki; Watanabe, Katsuyuki; Arakawa, Yasuhiko

2012-01-01

128

Adhesive flexible barrier film, method of forming same, and organic electronic device including same  

DOEpatents

An adhesive flexible barrier film comprises a substrate and a barrier layer disposed on the substrate. The barrier layer is formed from a barrier composition comprising an organosilicon compound. The adhesive flexible barrier film also comprises an adhesive layer disposed on the barrier layer and formed from an adhesive composition. A method of forming the adhesive flexible barrier film comprises the steps of disposing the barrier composition on the substrate to form the barrier layer, disposing the adhesive composition on the barrier layer to form the adhesive layer, and curing the barrier layer and the adhesive layer. The adhesive flexible barrier film may be utilized in organic electronic devices.

Blizzard, John Donald; Weidner, William Kenneth

2013-02-05

129

Fusion power implosion of laser-type light-ion beam driven reactor-size inertial fusion targets including radiation transport effects  

Microsoft Academic Search

This Letter presents simulation results of compression, ignition and burn of an umtamped (laser-type) inertial confinement fusion target which may be used in a reactor system driven by 33 MeV Li+ ions. These simulations have been carried out using a one-dimensional, three-temperature (electron, ion and radiation), Lagrangian ion-beam fusion code MEDUSA-KAT. The importance of thermal radiation in the simulations of

N. A. Tahir

1989-01-01

130

An enhanced bacterial foraging algorithm approach for optimal power flow problem including FACTS devices considering system loadability.  

PubMed

Obtaining optimal power flow solution is a strenuous task for any power system engineer. The inclusion of FACTS devices in the power system network adds to its complexity. The dual objective of OPF with fuel cost minimization along with FACTS device location for IEEE 30 bus is considered and solved using proposed Enhanced Bacterial Foraging algorithm (EBFA). The conventional Bacterial Foraging Algorithm (BFA) has the difficulty of optimal parameter selection. Hence, in this paper, BFA is enhanced by including Nelder-Mead (NM) algorithm for better performance. A MATLAB code for EBFA is developed and the problem of optimal power flow with inclusion of FACTS devices is solved. After several run with different initial values, it is found that the inclusion of FACTS devices such as SVC and TCSC in the network reduces the generation cost along with increased voltage stability limits. It is also observed that, the proposed algorithm requires lesser computational time compared to earlier proposed algorithms. PMID:23759251

Belwin Edward, J; Rajasekar, N; Sathiyasekar, K; Senthilnathan, N; Sarjila, R

2013-09-01

131

Energy star compliant voice over internet protocol (VoIP) telecommunications network including energy star compliant VoIP devices  

DOEpatents

A Voice over Internet Protocol (VoIP) communications system, a method of managing a communications network in such a system and a program product therefore. The system/network includes an ENERGY STAR (E-star) aware softswitch and E-star compliant communications devices at system endpoints. The E-star aware softswitch allows E-star compliant communications devices to enter and remain in power saving mode. The E-star aware softswitch spools messages and forwards only selected messages (e.g., calls) to the devices in power saving mode. When the E-star compliant communications devices exit power saving mode, the E-star aware softswitch forwards spooled messages.

Kouchri, Farrokh Mohammadzadeh

2012-11-06

132

Studies of Hydrodynamic Processes in Alternative Magneto-Inertial Fusion Devices  

NASA Astrophysics Data System (ADS)

The main goal of the research is evaluation of the plasma jet driven magneto-inertial fusion (PJMIF) concept via simulations. To achieve this goal, the development of mathematical models and numerical algorithms for PJMIF has been performed, and large-scale simulation studies have been conducted. In the PJMIF concept, a plasma liner, formed by the merger of a large number of radial, highly supersonic plasma jets, implodes on a magnetized plasma target and compresses it to conditions of the fusion ignition. 1- (spherically symmetric), 2- and 3-dimensional simulations of the implosion of plasma liners and compression of plasma targets have been performed using the FronTier code based on the method of front tracking. Scaling laws and related fusion theories have been investigated and their conclusions compared with our results. Compared to previous theoretical and numerical studies of PJMIF, our numerical models and algorithms implement several new physics models important to PJMIF. One of them is a numerical model for atomic physics processes. The influence of atomic physics processes on the plasma liners for magneto-inertial nuclear fusion has been studied based on equation of state models with dissociation and ionization. These atomic processes in imploding liners reduce the temperature and increase the Mach number of liners, result in higher stagnation pressure and the fusion energy gain. Other factors influencing liner implosion are the residual vacuum gas and heat conduction. By replacing the idealized vacuum region with realistic residual gas and adding the Spitzer electronic thermal conductivity, we quantified their effects in the low-energy simulation regime. We have demonstrated that the internal structure of argon plasma liners, formed by the merger of plasma jets is strongly influenced by a cascade of oblique shock waves generated by colliding jets. Corresponding studies have been performed using 2- and 3-dimensional simulations. 10 times reduction of the stagnation pressure was found compared to spherically symmetric liner with the same pressure and density profiles at the merging radius, due to the influence of oblique shock waves and adiabatic compression heating. The experiment results of single argon plasma jet propagation and two argon plasma jets merger reported by Plasma Liner Experiment group in Los Alamos National Lab have also been compared with our simulations. A multi-stage computational approach for simulations of the liner-target interaction and the compression of plasma targets has been developed to minimize computing time. Simulations revealed important features of the target implosion process, including instability and disintegration of targets. The non-uniformity of the leading edge of the liner caused by the oblique shock waves between jets leads to instabilities during target compression. By using front tracking, the evolution of targets has been studied in 2- and 3-dimensional simulations. Optimization studies of target compression with different number of jets have also been performed.

Zhang, Lina

133

Strongly Localized Potential Profile Measurements Through Stark Effects in the Central Core Region of an Inertial Electrostatic Fusion Device  

SciTech Connect

Strongly localized electric fields were measured in the central cathode helium plasma core region of an inertial electrostatic confinement fusion device by using laser-induced fluorescence (LIF) by the degree of polarization and by the longitudinal alignment methods. Both results show double well potential formation with a slight concave at the center in excellent agreement. The decay time of the excited states is found to indicate least effects by the collisions to ensure the LIF method.

Yoshikawa, Kiyoshi [Kyoto University (Japan); Takiyama, Ken [Hiroshima University (Japan); Masuda, Kai [Kyoto University (Japan); Toku, Hisayuki [Kyoto University (Japan); Koyama, Takahiro [Kyoto University (Japan); Taruya, Kenji [Kyoto University (Japan); Hashimoto, Hirofumi [Kyoto University (Japan); Yamamoto, Yasushi [Kyoto University (Japan); Ohnishi, Masami [Kansai University (Japan); Horiike, Hiroshi [Osaka University (Japan); Inoue, Nobuyuki [Kyoto University (Japan)

2001-05-15

134

2352 IEEE TRANSACTIONS ON ELECTRON DEVICES, VOL. 54, NO. 9, SEPTEMBER 2007 Simulation of Carbon Nanotube FETs Including  

E-print Network

2352 IEEE TRANSACTIONS ON ELECTRON DEVICES, VOL. 54, NO. 9, SEPTEMBER 2007 Simulation of Carbon Nanotube FETs Including Hot-Phonon and Self-Heating Effects Sayed Hasan, Student Member, IEEE, Muhammad of the nonequilibrium population of optical phonon (hot-phonon effect) and acoustic phonon (self- heating effect

Alam, Muhammad A.

135

Remote monitoring as a key innovation in the management of cardiac patients including those with implantable electronic devices.  

PubMed

This Introduction to the Supplement provides a brief history of remote monitoring, discusses its current status, and indicates the bright future that it possesses with a broad application in many branches of cardiology, at least including arrhythmias, heart failure, and ischaemic heart disease in addition to the management of implantable electronic devices. PMID:23737226

Sutton, Richard

2013-06-01

136

Novel fusion device mimics the planets A novel device built by MIT and Columbia University researchers suggests that nature's  

E-print Network

researchers suggests that nature's way of trapping hot, ionized gases called plasma could one day provide Jupiter--can hold onto plasma, even as temperatures and pressures rise. Fusion occurs when light nuclei a different approach--an approach inspired by the planets. "Satellites that went past Jupiter in the 1980s

137

Air filter devices including nonwoven meshes of electrospun recombinant spider silk proteins.  

PubMed

Based on the natural sequence of Araneus diadematus Fibroin 4 (ADF4), the recombinant spider silk protein eADF4(C16) has been engineered. This highly repetitive protein has a molecular weight of 48kDa and is soluble in different solvents (hexafluoroisopropanol (HFIP), formic acid and aqueous buffers). eADF4(C16) provides a high potential for various technical applications when processed into morphologies such as films, capsules, particles, hydrogels, coatings, fibers and nonwoven meshes. Due to their chemical stability and controlled morphology, the latter can be used to improve filter materials. In this protocol, we present a procedure to enhance the efficiency of different air filter devices, by deposition of nonwoven meshes of electrospun recombinant spider silk proteins. Electrospinning of eADF4(C16) dissolved in HFIP results in smooth fibers. Variation of the protein concentration (5-25% w/v) results in different fiber diameters (80-1,100 nm) and thus pore sizes of the nonwoven mesh. Post-treatment of eADF4(C16) electrospun from HFIP is necessary since the protein displays a predominantly ?-helical secondary structure in freshly spun fibers, and therefore the fibers are water soluble. Subsequent treatment with ethanol vapor induces formation of water resistant, stable ?-sheet structures, preserving the morphology of the silk fibers and meshes. Secondary structure analysis was performed using Fourier transform infrared spectroscopy (FTIR) and subsequent Fourier self-deconvolution (FSD). The primary goal was to improve the filter efficiency of existing filter substrates by adding silk nonwoven layers on top. To evaluate the influence of electrospinning duration and thus nonwoven layer thickness on the filter efficiency, we performed air permeability tests in combination with particle deposition measurements. The experiments were carried out according to standard protocols. PMID:23685883

Lang, Gregor; Jokisch, Stephan; Scheibel, Thomas

2013-01-01

138

Magnetron-Discharge-Based Ion Source for Improvement of an Inertial Electrostatic Confinement Fusion Device  

Microsoft Academic Search

A magnetron discharge as a built-in ion source have studied both experimentally and numerically for a compact discharge-type fusion neutron source called IECF (Inertial Electrostatic Confinement Fusion). With this magnetron discharge, ions are produced in the vicinity of the vacuum chamber (anode) at negative electric potential. Therefore, produced ions are expected to have nearly full energy corresponding to the applied

Teruhisa Takamatsu; Kai Masuda; Kiyoshi Yoshikawa; Hisayuki Toku; Kazunobu Nagasaki; Toshiyuki Kyunai

2005-01-01

139

Designing a 24/7 Fusion Device Towards Solving Plasma-materials Issues  

E-print Network

through fusion reactions. · Indefinite sustainment and duration for burning plasma. · Nuclear science & technology for net energy extraction. #12;3 Burning plasma --> Power density --> Fusion Economics · Net power loading ~ 4 MW/m3 --> 4 MW/m2 Our "nuclear" brethren in fission ~ 40 MW/m3!! Best guess still

140

Development of laser-based techniques for in situ characterization of the first wall in ITER and future fusion devices  

NASA Astrophysics Data System (ADS)

Analysis and understanding of wall erosion, material transport and fuel retention are among the most important tasks for ITER and future devices, since these questions determine largely the lifetime and availability of the fusion reactor. These data are also of extreme value to improve the understanding and validate the models of the in vessel build-up of the T inventory in ITER and future D-T devices. So far, research in these areas is largely supported by post-mortem analysis of wall tiles. However, access to samples will be very much restricted in the next-generation devices (such as ITER, JT-60SA, W7-X, etc) with actively cooled plasma-facing components (PFC) and increasing duty cycle. This has motivated the development of methods to measure the deposition of material and retention of plasma fuel on the walls of fusion devices in situ, without removal of PFC samples. For this purpose, laser-based methods are the most promising candidates. Their feasibility has been assessed in a cooperative undertaking in various European associations under EFDA coordination. Different laser techniques have been explored both under laboratory and tokamak conditions with the emphasis to develop a conceptual design for a laser-based wall diagnostic which is integrated into an ITER port plug, aiming to characterize in situ relevant parts of the inner wall, the upper region of the inner divertor, part of the dome and the upper X-point region.

Philipps, V.; Malaquias, A.; Hakola, A.; Karhunen, J.; Maddaluno, G.; Almaviva, S.; Caneve, L.; Colao, F.; Fortuna, E.; Gasior, P.; Kubkowska, M.; Czarnecka, A.; Laan, M.; Lissovski, A.; Paris, P.; van der Meiden, H. J.; Petersson, P.; Rubel, M.; Huber, A.; Zlobinski, M.; Schweer, B.; Gierse, N.; Xiao, Q.; Sergienko, G.

2013-09-01

141

NaOH-based high temperature heat-of-fusion thermal energy storage device  

NASA Technical Reports Server (NTRS)

A material called Thermkeep, developed as a low-cost method for the storage of thermal energy for solar electric power generating systems is discussed. The storage device consists of an insulated cylinder containing Thermkeep in which coiled tubular heat exchangers are immersed. A one-tenth scale model of the design contains 25 heat-exchanger tubes and 1500 kg of Thermkeep. Its instrumentation includes thermocouples to measure internal Thermkeep temperatures, vessel surface, heated shroud surface, and pressure gauges to indicate heat-exchanger pressure drops. The test-circuit design is presented and experimental results are discussed.

Cohen, B. M.; Rice, R. E.

1978-01-01

142

A Simple Apparatus for the Injection of Lithium Aerosol into the Scrape-Off Layer of Fusion Research Devices  

SciTech Connect

A simple device has been developed to deposit elemental lithium onto plasma facing components in the National Spherical Torus Experiment. Deposition is accomplished by dropping lithium powder into the plasma column. Once introduced, lithium particles quickly become entrained in scrape-off layer flow as an evaporating aerosol. Particles are delivered through a small central aperture in a computer-controlled resonating piezoelectric disk on which the powder is supported. The device has been used to deposit lithium both during discharges as well as prior to plasma breakdown. Clear improvements to plasma performance have been demonstrated. The use of this apparatus provides flexibility in the amount and timing of lithium deposition and, therefore, may benefit future fusion research devices.

D. K. Mansfield, A.L Roquemore, H. Schneider, J. Timberlake, H. Kugel, M.G. Bell and the NSTX Research Team

2010-10-11

143

LETTER TO THE EDITOR: Suppression of hydrogenated carbon film deposition by scavenger techniques and their application to the tritium inventory control of fusion devices  

NASA Astrophysics Data System (ADS)

The well-known radical and ion scavenger techniques of application in amorphous hydrogenated carbon film deposition studies are investigated in relation to the mechanism of tritium and deuterium co-deposition in carbon-dominated fusion devices. A particularly successful scheme results from the injection of nitrogen into methane/hydrogen plasmas for conditions close to those prevailing in the divertor region of present fusion devices. A complete suppression of the a-C : H film deposition has been achieved for N2/CH4 ratios close to one in methane (5%)/hydrogen DC plasma. The implications of these findings in the tritium retention control in future fusion reactors are addressed.

Tabarés, F. L.; Tafalla, D.; Tanarro, I.; Herrero, V. J.; Islyaikin, A.; Maffiotte, C.

2002-08-01

144

Microfluidic Control of Cell Pairing and Fusion  

PubMed Central

Cell fusion has been used for many different purposes, including generation of hybridomas and reprogramming of somatic cells. The fusion step represents the key event in initiation of these procedures. Standard fusion techniques, however, provide poor and random cell contact, leading to low yields. We present here a microfluidic device to trap and properly pair thousands of cells. Using this device we were able to pair different cell types, including fibroblasts, mouse embryonic stem cells (mESCs), and myeloma cells, achieving pairing efficiencies up to 70%. The device is compatible with both chemical and electrical fusion protocols. We observed that electrical fusion was more efficient than chemical fusion, with membrane reorganization efficiencies of up to 89%. We achieved greater than 50% properly paired and fused cells over the entire device, 5× greater than a commercial electrofusion chamber, and were able to observe reprogramming in hybrids between mESCs and mouse embryonic fibroblasts. PMID:19122668

Skelley, Alison M.; Kirak, Oktay; Suh, Heikyung; Jaenisch, Rudolf; Voldman, Joel

2011-01-01

145

High-throughput deterministic single-cell encapsulation and droplet pairing, fusion, and shrinkage in a single microfluidic device.  

PubMed

In this article, we present a microfluidic device capable of successive high-yield single-cell encapsulation in droplets, with additional droplet pairing, fusion, and shrinkage. Deterministic single-cell encapsulation is realized using Dean-coupled inertial ordering of cells in a Yin-Yang-shaped curved microchannel using a double T-junction, with a frequency over 2000 Hz, followed by controlled droplet pairing with a 100% success rate. Subsequently, droplet fusion is realized using electrical actuation resulting in electro-coalescence of two droplets, each containing a single HL60 cell, with 95% efficiency. Finally, volume reduction of the fused droplet up to 75% is achieved by a triple pitchfork structure. This droplet volume reduction is necessary to obtain close cell-cell membrane contact necessary for final cell electrofusion, leading to hybridoma formation, which is the ultimate aim of this research. PMID:23856757

Schoeman, Rogier M; Kemna, Evelien W M; Wolbers, Floor; van den Berg, Albert

2014-02-01

146

April 28, 2005 Itty-Bitty and Shrinking, Fusion Device Has Big Ideas  

E-print Network

be useful as a source of neutrons, the subatomic particles that are a byproduct of fusion. Because neutrons National Laboratory in Tennessee, said the energy of the particles emitted by the collisions convincingly

147

Magnetron-Discharge-Based Ion Source for Improvement of an Inertial Electrostatic Confinement Fusion Device  

SciTech Connect

A magnetron discharge as a built-in ion source have studied both experimentally and numerically for a compact discharge-type fusion neutron source called IECF (Inertial Electrostatic Confinement Fusion). With this magnetron discharge, ions are produced in the vicinity of the vacuum chamber (anode) at negative electric potential. Therefore, produced ions are expected to have nearly full energy corresponding to the applied voltage to the IECF cathode but slightly smaller energy preventing them from hitting the anode of the opposite end, eventually improving both fusion reaction rate and ion recirculation life. Also, the magnetron ion source was found to produce ample ion current for maintenance of the discharge. With the optimization of the configuration of the magnetron discharge, further improvement of the fusion reaction rate is found feasible.

Takamatsu, Teruhisa; Masuda, Kai; Yoshikawa, Kiyoshi; Toku, Hisayuki; Nagasaki, Kazunobu; Kyunai, Toshiyuki [Kyoto University (Japan)

2005-05-15

148

Optimizing Neutron Production Rates from D-D Fusion in an Inertial Electrostatic Confinement Device  

Microsoft Academic Search

Detection of explosives has been identified as a near term commercial opportunity for using a fusion plasma. Typical explosive compositions contain low Z material (C, N, O) which are not easily detected using conventional x-rays or metal detectors. However, 2.45 MeV neutrons produced in a D-D fusion reaction can be used for detection of explosives or other clandestine materials in

A. L. Wehmeyer; R. F. Radel; G. L. Kulcinski

2005-01-01

149

Performance Characteristics of an Inertial Electrostatic Confinement Fusion Device with a Triple-Grid System  

Microsoft Academic Search

Performance characteristics of an inertial electrostatic confinement fusion triple-grid system are experimentally studied to provide an ample fusion reaction rate under a lower-gas-pressure region to make the operation free from glow discharge restrictions between the discharge voltage, current, and gas pressure. With a filament to provide sufficient electrons, the operating gas pressure is found to reduce down to 1\\/5 for

Kai Masuda; Kenji Taruya; Takahiro Koyama; Hirofumi Hashimoto; Kiyoshi Yoshikawa; Hisayuki Toku; Yasushi Yamamoto; Masami Ohnishi; Hiroshi Horiike; Nobuyuki Inoue

2001-01-01

150

Proceedings of 1999 U.S./Japan Workshop (99FT-05) On High Heat Flux Components and Plasma Surface Interactions for Next Fusion Devices  

SciTech Connect

The 1999 US-Japan Workshop on High Heat Flux Components and Plasma Surface Interactions in Next Step Fusion Devices was held at the St. Francis Hotel in Santa Fe, New Mexico, on November 1-4, 1999. There were 42 presentations as well as discussion on technical issues and planning for future collaborations. The participants included 22 researchers from Japan and the United States as well as seven researchers from Europe and Russia. There have been important changes in the programs in both the US and Japan in the areas of plasma surface interactions and plasma facing components. The US has moved away from a strong focus on the ITER Project and has introduced new programs on use of liquid surfaces for plasma facing components, and operation of NSTX has begun. In Japan, the Large Helical Device began operation. This is the first large world-class confinement device operating in a magnetic configuration different than a tokamak. In selecting the presentations for this workshop, the organizers sought a balance between research in laboratory facilities or confinement devices related to plasma surface interactions and experimental research in the development of plasma facing components. In discussions about the workshop itself, the participants affirmed their preference for a setting where ''work-in-progress'' could be informally presented and discussed.

NYGREN,RICHARD E.; STAVROS,DIANA T.

2000-06-01

151

Performance Characteristics of an Inertial Electrostatic Confinement Fusion Device with a Triple-Grid System  

SciTech Connect

Performance characteristics of an inertial electrostatic confinement fusion triple-grid system are experimentally studied to provide an ample fusion reaction rate under a lower-gas-pressure region to make the operation free from glow discharge restrictions between the discharge voltage, current, and gas pressure. With a filament to provide sufficient electrons, the operating gas pressure is found to reduce down to 1/5 for the same discharge current and voltage. Although the gas pressure region that was achieved still remains the region where the fusion reaction between the ion beam and background gas is dominant, the neutron yield normalized by the gas pressure in the triple-grid system shows higher value than the conventional single-grid system.

Masuda, Kai [Kyoto University (Japan); Taruya, Kenji [Kyoto University (Japan); Koyama, Takahiro [Kyoto University (Japan); Hashimoto, Hirofumi [Kyoto University (Japan); Yoshikawa, Kiyoshi [Kyoto University (Japan); Toku, Hisayuki [Kyoto University (Japan); Yamamoto, Yasushi [Kyoto University (Japan); Ohnishi, Masami [Kansai University (Japan); Horiike, Hiroshi [Osaka University (Japan); Inoue, Nobuyuki [Kyoto University (Japan)

2001-05-15

152

Embedded D-{sup 3}He Fusion Reactions and Medical Isotope Production in an Inertial Electrostatic Confinement Device  

SciTech Connect

The high-energy 14.7 MeV protons generated from the D-{sup 3}He fusion reaction can be used to produce medical radioisotopes. Steady-state D-{sup 3}He operation is possible using Inertial Electrostatic Confinement (IEC); however, the location of the reactions must be known to use them effectively for isotope production. In University of Wisconsin IEC Device, it has been found that as much as 2/3 of the total D-{sup 3}He reaction rate can be due to embedded fusion reactions, reactions occurring within the cathode due to ion implantation. Therefore, the cathode surface sees a large, high-energy proton flux. Using a solid molybdenum cathode, and taking advantage of the embedded reactions, about 1 nCi of the medical isotope {sup 94m}Tc was created via {sup 94}Mo(p,n){sup 94m}Tc in a proof of principle experiment. This represents the first time the IEC concept has been used to produce a radioisotope using D-{sup 3}He fusion.

Cipiti, B.B.; Kulcinski, G.L. [University of Wisconsin-Madison (United States)

2003-09-15

153

An in situ accelerator-based diagnostic for plasma-material interactions science on magnetic fusion devices.  

PubMed

This paper presents a novel particle accelerator-based diagnostic that nondestructively measures the evolution of material surface compositions inside magnetic fusion devices. The diagnostic's purpose is to contribute to an integrated understanding of plasma-material interactions in magnetic fusion, which is severely hindered by a dearth of in situ material surface diagnosis. The diagnostic aims to remotely generate isotopic concentration maps on a plasma shot-to-shot timescale that cover a large fraction of the plasma-facing surface inside of a magnetic fusion device without the need for vacuum breaks or physical access to the material surfaces. Our instrument uses a compact (~1 m), high-current (~1 milliamp) radio-frequency quadrupole accelerator to inject 0.9 MeV deuterons into the Alcator C-Mod tokamak at MIT. We control the tokamak magnetic fields--in between plasma shots--to steer the deuterons to material surfaces where the deuterons cause high-Q nuclear reactions with low-Z isotopes ~5 ?m into the material. The induced neutrons and gamma rays are measured with scintillation detectors; energy spectra analysis provides quantitative reconstruction of surface compositions. An overview of the diagnostic technique, known as accelerator-based in situ materials surveillance (AIMS), and the first AIMS diagnostic on the Alcator C-Mod tokamak is given. Experimental validation is shown to demonstrate that an optimized deuteron beam is injected into the tokamak, that low-Z isotopes such as deuterium and boron can be quantified on the material surfaces, and that magnetic steering provides access to different measurement locations. The first AIMS analysis, which measures the relative change in deuterium at a single surface location at the end of the Alcator C-Mod FY2012 plasma campaign, is also presented. PMID:24387430

Hartwig, Zachary S; Barnard, Harold S; Lanza, Richard C; Sorbom, Brandon N; Stahle, Peter W; Whyte, Dennis G

2013-12-01

154

An in situ accelerator-based diagnostic for plasma-material interactions science on magnetic fusion devices  

SciTech Connect

This paper presents a novel particle accelerator-based diagnostic that nondestructively measures the evolution of material surface compositions inside magnetic fusion devices. The diagnostic's purpose is to contribute to an integrated understanding of plasma-material interactions in magnetic fusion, which is severely hindered by a dearth of in situ material surface diagnosis. The diagnostic aims to remotely generate isotopic concentration maps on a plasma shot-to-shot timescale that cover a large fraction of the plasma-facing surface inside of a magnetic fusion device without the need for vacuum breaks or physical access to the material surfaces. Our instrument uses a compact (?1 m), high-current (?1 milliamp) radio-frequency quadrupole accelerator to inject 0.9 MeV deuterons into the Alcator C-Mod tokamak at MIT. We control the tokamak magnetic fields – in between plasma shots – to steer the deuterons to material surfaces where the deuterons cause high-Q nuclear reactions with low-Z isotopes ?5 ?m into the material. The induced neutrons and gamma rays are measured with scintillation detectors; energy spectra analysis provides quantitative reconstruction of surface compositions. An overview of the diagnostic technique, known as accelerator-based in situ materials surveillance (AIMS), and the first AIMS diagnostic on the Alcator C-Mod tokamak is given. Experimental validation is shown to demonstrate that an optimized deuteron beam is injected into the tokamak, that low-Z isotopes such as deuterium and boron can be quantified on the material surfaces, and that magnetic steering provides access to different measurement locations. The first AIMS analysis, which measures the relative change in deuterium at a single surface location at the end of the Alcator C-Mod FY2012 plasma campaign, is also presented.

Hartwig, Zachary S.; Barnard, Harold S.; Lanza, Richard C.; Sorbom, Brandon N.; Stahle, Peter W.; Whyte, Dennis G. [Plasma Science and Fusion Center, Massachusetts Institute of Technology, 77 Massachusetts Ave, Cambridge Massachusetts 02139 (United States)] [Plasma Science and Fusion Center, Massachusetts Institute of Technology, 77 Massachusetts Ave, Cambridge Massachusetts 02139 (United States)

2013-12-15

155

Nonelectric Applications of Fusion  

NASA Astrophysics Data System (ADS)

This is the final report of a panel set up by the U.S. Department of Energy (DOE) Fusion Energy Sciences Advisory Committee (FESAC) in response to a charge letter from Dr. James Decker, Acting Director of the DOE Office of Science. In that letter, Dr. Decker asked FESAC to consider "whether the Fusion Energy Sciences program should broaden its scope and activities to include non-electric applications of intermediate-term fusion devices." This report, submitted to FESAC July 31, 2003, and subsequently approved by them (Appendix B), presents FESAC's response to that charge.

McCarthy, Kathryn; Baker, Charles; Cheng, Edward; Kulcinski, Gerald; Logan, Grant; Miley, George; Perkins, John; Petti, Dave; Sheffield, John; Steiner, Don; Stacey, Weston; Waganer, Lester

2002-12-01

156

High-speed repetitive pellet injector for plasma fueling of magnetic confinement fusion devices  

SciTech Connect

The projected fueling requirements of future magnetic confinement devices for controlled thermonuclear research [e.g., the International Thermonuclear Experimental Reactor (ITER)] indicate that a flexible plasma fueling capability is required. This includes a mix of traditional gas puffing and low- and high-velocity deuterium-tritium pellets. Conventional pellet injectors (based on light gas guns or centrifugal accelerators) can reliably provide frozen hydrogen pellets (1- to 6-mm-diam sizes tested) up to {approximately}1.3-km/s velocity at the appropriate pellet fueling rates (1 to 10 Hz or greater). For long-pulse operation in a higher velocity regime (>2 km/s), an experiment in collaboration between Oak Ridge National Laboratory (ORNL) and ENEA Frascati is under way. This activity will be carried out in the framework of a collaborative agreement between the US Department of Energy and European Atomic Energy Community -- ENEA Association. In this experiment, an existing ORNL hydrogen extruder (equipped with a pellet chambering mechanism/gun barrel assembly) and a Frascati two-stage light gas gun driver have been combined on a test facility at ORNL. Initial testing has been carried out with single deuterium pellets accelerated up to 2.05 km/s with the two-stage driver; in addition, some preliminary repetitive testing (to commission the diagnostics) was performed at reduced speeds, including sequences at 0.5 to 1 Hz and 10 to 30 pellets. The primary objective of this study is to demonstrate repetitive operation (up to {approximately}1 Hz) with speeds in the 2- to 3-km/s range. In addition, the strength of extruded hydrogen ice as opposed to that produced in situ by direct condensation in pipe guns can be investigated. The equipment and initial experimental results are described.

Combs, S.K.; Baylor, L.R.; Foust, C.R. [and others

1993-11-01

157

Combined sheath and thermal analysis of overheated surfaces in fusion devices  

Microsoft Academic Search

The phenomenon of runaway surfaces overheating in fusion experiments due to plasma-sheath\\/surface-emission coupling has been analyzed. A semi-analytic model has been used as well as the BPHI-3D kinetic sheath code (J.N. Brooks, D. Naujoks, Phys. Plasmas 7 (2000) 2565) coupled with the THERM code which solves the non-stationary heat conduction equation also in 3D geometry. Runaway heating due to initial

D. Naujoks; J. N. Brooks

2001-01-01

158

Improved Inertial Electrostatic Confinement Device for ^3He^3He Fusion  

Microsoft Academic Search

Ions in inertial electrostatic confinement (IEC) systems are accelerated radially by an electrostatic field between two spherical grids, a configuration in which ^3He-^3He fusion has previously been demonstrated as part of the advanced fuels program at the University of Wisconsin [1]. A campaign is underway to enhance the experimental setup, in order to sustain cathode voltages beyond 200 kV. Additionally,

Gabriel Becerra; John Santarius; Gerald Kulcinski

2010-01-01

159

Development of a new concept ion source for high performance inertial electrostatic confinement fusion device  

Microsoft Academic Search

An Inertial Electrostatic Confinement Fusion (IECF) is a concept for retaining a plasma using an electrostatic potential well. It consists of two spherical grids inside the vacuum chamber. An insulated high voltage feed-through supplies power to the inner grid cathode, and a small amount of deuterium or tritium gas (0.1-1.0 Pa) is fed into the chamber. When the voltage is

Y. Taniuchi; Y. Matsumura; K. Taira; M. Utsumi

2010-01-01

160

Apparatus and method for removing particle species from fusion-plasma-confinement devices  

DOEpatents

In a mirror fusion plasma confinement apparatus, method and apparatus are provided for selectively removing (pumping) trapped low energy (thermal) particle species from the end cell region, without removing the still useful high energy particle species, and without requiring large power input to accomplish the pumping. Perturbation magnets are placed in the thermal barrier region of the end cell region at the turning point characteristic of trapped thermal particles, thus deflecting the thermal particles from their closed trajectory, causing them to drift sufficiently to exit the thermal barrier.

Hamilton, G.W.

1981-10-26

161

Statistical analysis of temporal and spatial evolution of in-vessel dust particles in fusion devices by using CCD images  

NASA Astrophysics Data System (ADS)

Images of wide-angle visible standard CCD cameras contain information on Dust Creation Events (DCEs) that occur during plasma operations. Database on the DCEs can be built by analyzing the straight line-like dust trajectories in scrape-off layer caused by plasma-dust interaction along the vacuum vessel. The database provides short/long term temporal evolution and spatial distribution of origins of DCEs in fusion devices. We have studied DCEs of 2011 KSTAR campaign and compared with that of 2006 Tore Supra (TS) and 2007 ASDEX Upgrade (AUG) campaign. An analysis software, with which the location of dust trajectories in 3D position in the KSTAR vacuum vessel is identified, is developed and the dust velocity distribution in 2011 campaign is measured. ©2001 Elsevier Science.

Hong, Suk-Ho; Kim, Kyung-Rae; Nam, Yong-Un; Chung, Jinil; Grisolia, Christian; Rohde, Volker; KSTAR Team; TORE SUPRA Team; ASDEX Upgrade Team

2013-08-01

162

Comparison of Hand-assisted Laparoscopic Surgery Using Tissue Fusion Devices and Open Resection for Treatment of Rectosigmoid Carcinoma.  

PubMed

Modern tissue fusion devices used in hand-assisted laparoscopic surgery (HALS), a method of combining endoscopic surgery with tactile sensation, can minimize surgical trauma and hospitalization times beyond both conventional laparoscopy and open surgery. The outcomes of HALS using tissue fusion devices and conventional open surgery for curative resection of rectosigmoid carcinoma were compared. A total of 78 (45 males, 33 females; mean age, 57.2±11.7 y) rectosigmoid carcinoma patients underwent HALS surgery (HALS group) and 78 age-matched, sex-matched, and tumor status-matched rectosigmoid carcinoma patients (control group) underwent open resection between June 2008 and June 2010. In the HALS and control groups, abdominal incision length, intraoperative blood loss, procedure time, postoperative abdominal drainage, time to first flatus (bowel function return), length of hospital stay, morbidity, mortality, and pathology were assessed. Procedure times were similar in both groups (142.37±42.09 vs. 137.56±36.24 min). However, length of abdominal incision (5.14±0.47 vs. 13.17±2.41 cm), intraoperative blood loss (125.96±75.58 vs. 142.56±65.37 mL), need for postoperative analgesia, bowel function return (68.01±22.64 vs. 79.77±19.94 h), and postoperative hospital stay (6.47±1.73 vs. 7.73±1.71 d) were all significantly improved in the HALS group. At a median follow-up of 26 months, no significant differences in anastomotic recurrence were observed between groups (1 case/each group). Thus, the HALS approach for curative resection of rectosigmoid carcinoma was found to be similarly safe and effective compared with open resection. Furthermore, HALS may improve postoperative recovery and reduce hospitalization times. PMID:25090290

Zhu, Yuping; Feng, Haiyang; Li, Qiken; Chen, Yinbo; Qian, Jun; Liu, Yong; Li, Dechuan

2014-10-01

163

Preliminary Results of Low Pressure Discharge Experiments of a Cylindrical Inertial Electrostatic Confinement Fusion Device Aimed for a Small Neutron Source  

Microsoft Academic Search

The effects of operating gas pressure on a Cylindrical Inertial Electrostatic Confinement Fusion (IECF) device are investigated. First we did glow discharge experiments, and we obtained 1.8 x 10⁶ neutrons production per second with 45-kV, 44-mA discharge at 1.2 Pa. Next we modified the device and tried to reduce the operating gas pressure with an ion source, aimed to increase

Takanori Higashi; Takahito Tomizawa; Mitsugu Daino; Yasushi Yamamoto

2003-01-01

164

Measurement of the energy distribution of fast excited atoms by Doppler shift spectroscopy in an inertial-electrostatic confinement fusion device  

Microsoft Academic Search

Energy distributions of energetic neutral atoms resulted from charge-exchange reactions between accelerated ions and background atoms or molecules were measured by the Doppler shift spectroscopy in an inertial-electrostatic confinement fusion (IECF) device composed of a spherical vacuum chamber as an anode and a spherical hollow cathode grid concentrically placed in the chamber. Since ions generated between the cathode and the

Kai Masuda; Toshiyuki Mizutani; Kiyoshi Yoshikawa; Kazunobu Nagasaki; Ken Takiyama; Hisayuki Toku; Hirofumi Hashimoto; Akihiro Nagafuchi

2002-01-01

165

Evaluation of an electrostatic dust removal system with potential application in next-step fusion devices  

NASA Astrophysics Data System (ADS)

The ability to manage inventories of carbon, tritium, and high-Z elements in fusion plasmas depends on means for effective dust removal. A dust conveyor, based on a moving electrostatic potential well, was tested with particles of tungsten, carbon, glass, and sand. A digital microscope imaged a representative portion of the conveyor, and dust particle size and volume distributions were derived before and after operation. About 10 mm3 volume of carbon and tungsten particles were moved in under 5 s. The highest driving amplitude tested of 3 kV was the most effective. The optimal driving frequency was 210 Hz (maximum tested) for tungsten particles, decreasing to below 60 Hz for the larger sand particles. Measurements of particle size and volume distributions after 10 and 100 cycles show the breaking apart of agglomerated carbon and the change in particle distribution over short timescales (<1 s).

Friesen, F. Q. L.; John, B.; Skinner, C. H.; Roquemore, A. L.; Calle, C. I.

2011-05-01

166

Evaluation of an electrostatic dust removal system with potential application in next-step fusion devices.  

PubMed

The ability to manage inventories of carbon, tritium, and high-Z elements in fusion plasmas depends on means for effective dust removal. A dust conveyor, based on a moving electrostatic potential well, was tested with particles of tungsten, carbon, glass, and sand. A digital microscope imaged a representative portion of the conveyor, and dust particle size and volume distributions were derived before and after operation. About 10 mm(3) volume of carbon and tungsten particles were moved in under 5 s. The highest driving amplitude tested of 3 kV was the most effective. The optimal driving frequency was 210 Hz (maximum tested) for tungsten particles, decreasing to below 60 Hz for the larger sand particles. Measurements of particle size and volume distributions after 10 and 100 cycles show the breaking apart of agglomerated carbon and the change in particle distribution over short timescales (<1 s). PMID:21639499

Friesen, F Q L; John, B; Skinner, C H; Roquemore, A L; Calle, C I

2011-05-01

167

Liquid metals as alternative solution for the power exhaust of future fusion devices: status and perspective  

NASA Astrophysics Data System (ADS)

Applying liquid metals as plasma facing components for fusion power-exhaust can potentially ameliorate lifetime issues as well as limitations to the maximum allowed surface heat loads by allowing for a more direct contact with the coolant. The material choice has so far been focused on lithium (Li), as it showed beneficial impact on plasma operation. Here materials such as tin (Sn), gallium (Ga) and aluminum (Al) are discussed as alternatives potentially allowing higher operating temperatures without strong evaporation. Power loads of up to 25 MW m-2 for a Sn/W component can be envisioned based on calculations and modeling. Reaching a higher operating temperature due to material re-deposition will be discussed. Liquids typically face stability issues due to j × B forces, potential pressure and magnetohydrodynamic driven instabilities. The capillary porous system is used for stabilization by a mesh (W and Mo) substrate and replenishment by means of capillary action.

Coenen, J. W.; De Temmerman, G.; Federici, G.; Philipps, V.; Sergienko, G.; Strohmayer, G.; Terra, A.; Unterberg, B.; Wegener, T.; Van den Bekerom, D. C. M.

2014-04-01

168

Computerized cost estimation spreadsheet and cost data base for fusion devices  

SciTech Connect

Component design parameters (weight, surface area, etc.) and cost factors are input and direct and indirect costs are calculated. The cost data base file derived from actual cost experience within the fusion community and refined to be compatible with the spreadsheet costing approach is a catalog of cost coefficients, algorithms, and component costs arranged into data modules corresponding to specific components and/or subsystems. Each data module contains engineering, equipment, and installation labor cost data for different configurations and types of the specific component or subsystem. This paper describes the assumptions, definitions, methodology, and architecture incorporated in the development of the cost estimation spreadsheet and cost data base, along with the type of input required and the output format.

Hamilton, W.R.; Rothe, K.E.

1985-01-01

169

Effects of Displaced Grids on the Fusion Reactivity of an Inertial Electrostatic Confinement Device  

Microsoft Academic Search

Inertial Electrostatic Confinement (IEC) devices consist of nearly transparent, concentric grid electrodes that accelerate\\u000a ions radially using voltage differences of 10–100s of kV. This paper investigates the effect of offsetting the inner grid\\u000a with respect to the outer grid. Offsetting the grids changes the electric fields set up between the two grids and hence affects\\u000a the ion flow into the

S. Krupakar Murali; John F. Santarius; Gerald L. Kulcinski

2010-01-01

170

Effects of DD and DT neutron irradiation on some Si devices for fusion diagnostics  

Microsoft Academic Search

In order to examine the difference in the irradiation effects on Si devices between DT and DD neutrons, CCD image sensors, memory ICs and a Si detector were irradiated with neutrons from a deuteron accelerator. The transient effects (i.e. neutron-induced background noises) and permanent effects (i.e. neutron damage) on them were in situ measured during irradiation. Regarding the transient effects,

Yoshihiko Tanimura; Toshiyuki Iida

1998-01-01

171

Electromechanical analysis of the technology demonstrator for the IGNITEX fusion device  

SciTech Connect

The Texas Ignition Experiment (IGNITEX) device is a single turn coil tokamak designed to produce and control an ignited plasma using ohmic heating alone. The proposed high strength magnet system operates at a magnetic field on-axis of 20 T, using homopolar generators (HPGs), which meet the power supply requirements (150 MA, 10 V) inexpensively. In this paper, the electromechanical analysis of a scaled down prototype (1/10 scale in linear dimensions) of the IGNITEX toroidal field (TF) magnet is presented. The primary goal of the IGNITEX Technology Demonstrator (ITD) is to prove the operation of a single turn, 20 T, toroidal field coil powered by a homopolar generator power supply system of 60 MJ, 9 MA, current operating at the Center for Electromechanics. The University of Texas at Austin (CEM-UT). In order to simulate the actual operating conditions of the full-scale device, the ITD coil will be precooled at liquid nitrogen temperature and driven by the six homopolar generators in parallel. Scaling relationships have shown that electromagnetic loading mechanical and thermal loading of the coil and their relative distribution will approximate well predicted levels of the full-scale IGNITEX device.

Driga, M.D.; Hsieh, K.T.; Weldon, W.F.; Werst, M.D.

1989-03-01

172

Optimization of transistor design including large signal device/circuit interactions at extremely high frequencies (20-100+GHz)  

NASA Technical Reports Server (NTRS)

Transistor design for extremely high frequency applications requires consideration of the interaction between the device and the circuit to which it is connected. Traditional analytical transistor models are to approximate at some of these frequencies and may not account for variations of dopants and semiconductor materials (especially some of the newer materials) within the device. Physically based models of device performance are required. These are based on coupled systems of partial differential equations and typically require 20 minutes of Cray computer time for a single AC operating point. A technique is presented to extract parameters from a few partial differential equation solutions for the device to create a nonlinear equivalent circuit model which runs in approximately 1 second of personal computer time. This nonlinear equivalent circuit model accurately replicates the contact current properties of the device as computed by the partial differential solver on which it is based. Using the nonlinear equivalent circuit model of the device, optimization of systems design can be performed based on device/circuit interactions.

Levy, Ralph; Grubin, H. L.

1991-01-01

173

Visualization and Analysis Tools for Next-Generation Tokamak Fusion Devices  

NASA Astrophysics Data System (ADS)

Recent studies of tokamak fusion nuclear science facilities, which could achieve net electricity generation, have involved searching a rich parameter space for optimal reactor characteristics using a 0-D systems code. Large amounts of data were generated, on the order of one hundred million different sets of reactor parameters. The systems code has been interfaced with PPPL's visualization program called ElVis and tools have been developed to handle large amounts of data. This work has motivated further development of ElVis, allowing it to accommodate the systems code output data. ElVis enables a user to make arbitrary plots of different reactor parameters. The data manipulation and graphing capability has enabled the review of a large number of viable operating points, the observation of trends and the identification of desirable operating points. This will enable a study of the impact of enhanced physics and technology on the operation of a power plant that produces net electricity. This work is supported by U.S. DOE Contract #DE-AC02-09CH11466.

Kastner, Robert; Kessel, Charles; Hawryluk, R. J.; Feibush, Eliot; Milano, Matthew; Phillips, Ben

2010-11-01

174

Plasma-wall interactions and plasma behaviour in fusion devices with liquid lithium plasma facing components  

NASA Astrophysics Data System (ADS)

The application of lithium as a self-recovery and renewable material of plasma facing components (PFC) can be used to solve steady state fusion reactor PFC problems. This paper is a survey of liquid Li use in current tokamaks. Liquid Li as tokamak limiter material has been tested in T-11 M tokamak (TRINITI, RF), in FTU (Italy) and in CDX-U (USA). The idea of T-11 M and FTU liquid Li limiters is based on the Capillary-Pore System (CPS) concept. The main feature of CDX-U toroidal limiter was free liquid Li surface. The crucial issue of tokamak is impurity contamination. Lithium experiments in tokamaks discovered that poor lithium penetration into hot plasma core from its periphery (lithium screening) and the development close to plasma boundary lithium non-coronal irradiative blanket. Lithium screening can be physical ground of lithium 'emitter-collector' limiter concept with irradiated blanket and PFC prevention from a high local power load up to level of ITER parameters.

Mirnov, S.

2009-06-01

175

LN/sub 2/ cyclic cooling considerations of fusion ignition devices  

SciTech Connect

The purpose of this study is to develop a simple model to calculate the cooldown rate of a magnet with various cooling surface configurations. The results will be useful in developing a configuration to provide the desired cooling time between pulses, which should be approx. 1 h or less. The preliminary results indicate that the cooldown time between pulses is approx. 1 to 2 h, thus limiting the number of pulses to four to eight per day. A shorter cooldown time is feasible by increasing the cooling surface area. The inner leg radial dimension should be increased to obtain a larger cooling surface area for the fixed ratio of cooling channel-to-inner leg cross section. This will directly impact the capital cost of the device.

Dabiri, A.E.

1986-01-01

176

Benefits and Challenges of the Use of High-Z Plasma Facing Materials in Fusion Devices  

NASA Astrophysics Data System (ADS)

The use of high-Z plasma facing components requires intensive research in all areas, i.e. in plasma wall-interaction, in the physics of the confined plasma, diagnostic, and in material development. Only a few present day divertor tokamaks - mainly Alcator C-Mod and ASDEX Upgrade - gained experience with the refractory metals molybdenum and tungsten, respectively. ASDEX Upgrade was stepwise converted from graphite to tungsten PFCs and in parallel a reduction of the deuterium retention by almost a factor of ten has been observed due to the strong suppression of D co-deposition with carbon. The deuterium retained in W is in line with laboratory results. In order to diagnose W sources and the W content in the main plasma adequate spectroscopic methods had to be developed. As expected from the sputtering threshold of Mo and W, negligible erosion by the thermal divertor background plasma is found in ASDEX Upgrade and Alcator C-Mod under low temperature divertor conditions. However, erosion by fast particles and intrinsic impurities, which additionally might be accelerated in rectified electrical fields observed during ion cyclotron frequency heating, plays an important role. The Mo and W concentrations in the plasma centre are strongly affected by plasma transport and variations up to a factor of 50 are observed for similar influxes. However, it could be demonstrated that sawteeth and turbulent transport driven by central heating can suppress central accumulation. The inward transport of high-Z ions at the edge can be efficiently reduced by `flushing' the pedestal region caused by frequent edge instabilities. Since with metal walls the edge radiation by low-Z impurities is reduced, it has to be substituted in a pure high-Z device by artificially injected low-Z impurities in order to keep the power load at an acceptable level. Experiments at ASDEX Upgrade suggest that a regime with benign erosion and favourable confinement can be achieved. Extrapolations to ITER and DEMO are difficult since the physics of plasma transport is not yet completely understood, the particle and energy fluxes are orders of magnitude higher and the technical boundary conditions in DEMO strongly differ from those of present day devices.

Neu, R.

2010-05-01

177

Benefits and Challenges of the Use of High-Z Plasma Facing Materials in Fusion Devices  

SciTech Connect

The use of high-Z plasma facing components requires intensive research in all areas, i.e. in plasma wall-interaction, in the physics of the confined plasma, diagnostic, and in material development. Only a few present day divertor tokamaks - mainly Alcator C-Mod and ASDEX Upgrade - gained experience with the refractory metals molybdenum and tungsten, respectively. ASDEX Upgrade was stepwise converted from graphite to tungsten PFCs and in parallel a reduction of the deuterium retention by almost a factor of ten has been observed due to the strong suppression of D co-deposition with carbon. The deuterium retained in W is in line with laboratory results. In order to diagnose W sources and the W content in the main plasma adequate spectroscopic methods had to be developed. As expected from the sputtering threshold of Mo and W, negligible erosion by the thermal divertor background plasma is found in ASDEX Upgrade and Alcator C-Mod under low temperature divertor conditions. However, erosion by fast particles and intrinsic impurities, which additionally might be accelerated in rectified electrical fields observed during ion cyclotron frequency heating, plays an important role. The Mo and W concentrations in the plasma centre are strongly affected by plasma transport and variations up to a factor of 50 are observed for similar influxes. However, it could be demonstrated that sawteeth and turbulent transport driven by central heating can suppress central accumulation. The inward transport of high-Z ions at the edge can be efficiently reduced by 'flushing' the pedestal region caused by frequent edge instabilities. Since with metal walls the edge radiation by low-Z impurities is reduced, it has to be substituted in a pure high-Z device by artificially injected low-Z impurities in order to keep the power load at an acceptable level. Experiments at ASDEX Upgrade suggest that a regime with benign erosion and favourable confinement can be achieved. Extrapolations to ITER and DEMO are difficult since the physics of plasma transport is not yet completely understood, the particle and energy fluxes are orders of magnitude higher and the technical boundary conditions in DEMO strongly differ from those of present day devices.

Neu, R. [Max-PIanck-Institut fuer Plasmaphysik, EURATOM Association, Boltzmannstr. 2, 85748 Garching (Germany)

2010-05-20

178

ECR heating power modulation as a means to ease the overcoming of the radiation barrier in fusion devices  

SciTech Connect

A method is proposed to ease the overcoming of the impurity radiation barrier during current drive in tokamaks, as well as in alternative fusion and plasmochemical systems with ECR plasma heating. The method is based on the fact that the dependence of the ionization rate on the electron temperature is strongly nonlinear and the dependence of the recombination rate on the latter is weaker. The result is that, during temperature oscillations, the effective temperature for ionization-recombination processes is higher than that in a steady state, so the ionization equilibrium is shifted and strongly emitting ions are stripped more rapidly. Thereby, ECR plasma heating in the initial discharge stage can be made more efficient by modulating the heating power at a low frequency. The evolution of the electron temperature in a homogeneous hydrogen plasma with a carbon impurity and in small ISX-scale tokamaks is simulated numerically, as well as the evolution of the electron and ion temperatures and of the current during discharge startup in the ITER device. Numerical simulations of the effect of modulation of the ECR heating power on the rate of heating of nitrogen, oxygen, and argon plasmas were also carried out. The assumption of coronal equilibrium is not used. It is shown that the low-frequency modulation of the heating power can substantially ease the overcoming of the radiation barrier.

Morozov, D. Kh.; Pshenov, A. A. [Russian Research Centre Kurchatov Institute (Russian Federation); Mineev, A. B. [D.V. Efremov Scientific Research Institute of Electrophysical Apparatus (Russian Federation)

2010-06-15

179

Irradiation creep at temperatures of 400 {degrees}C and below for application to near-term fusion devices  

SciTech Connect

To study irradiation creep at 400{degrees}C and below, a series of six austenitic stainless steels and two ferritic alloys was irradiated sequentially in two research reactors where the neutron spectrum was tailored to produce a He production rate typical of a fusion device. Irradiation began in the Oak Ridge Research Reactor; and, after an atomic displacement level of 7.4 dpa, the specimens were moved to the High Flux Isotope Reactor for the remainder of the 19 dpa accumulated. Irradiation temperatures of 60, 200, 330, and 400{degrees}C were studied with internally pressurized tubes of type 316 stainless steel, PCA, HT 9, and a series of four laboratory heats of: Fe-13.5Cr-15Ni, Fe-13.5Cr-35Ni, Fe-1 3.5Cr-1 W-0.18Ti, and Fe-16Cr. At 330{degrees}C, irradiation creep was shown to be linear in fluence and stress. There was little or no effect of cold-work on creep under these conditions at all temperatures investigated. The HT9 demonstrated a large deviation from linearity at high stress levels, and a minimum in irradiation creep with increasing stress was observed in the Fe-Cr-Ni ternary alloys.

Grossbeck, M.L.; Gibson, L.T.; Mansur, L.K. [and others

1996-12-31

180

Mixed SOC diffusive dynamics as a paradigm for transport in fusion devices  

E-print Network

-organized criticality (SOC), is extended to include the interplay among the many transport mechanisms existing in real of such an extended model reveal a dramatic change in the dynamics, with the edge coming to play a dominant role, one associated with the drive and the other with the instability relaxation. It is easy to find

Martín-Solís, José Ramón

181

Fracture of the L-4 vertebral body after use of a stand-alone interbody fusion device in degenerative spondylolisthesis for anterior L3-4 fixation.  

PubMed

Many studies attest to the excellent results achieved using anterior lumbar interbody fusion (ALIF) for degenerative spondylolisthesis. The purpose of this report is to document a rare instance of L-4 vertebral body fracture following use of a stand-alone interbody fusion device for L3-4 ALIF. The patient, a 55-year-old man, had suffered intractable pain of the back, right buttock, and left leg for several weeks. Initial radiographs showed Grade I degenerative spondylolisthesis, with instability in the sagittal plane (upon 15° rotation) and stenosis of central and both lateral recesses at the L3-4 level. Anterior lumbar interbody fusion of the affected vertebrae was subsequently conducted using a stand-alone cage/plate system. Postoperatively, the severity of spondylolisthesis diminished, with resolution of symptoms. However, the patient returned 2 months later with both leg weakness and back pain. Plain radiographs and CT indicated device failure due to anterior fracture of the L-4 vertebral body, and the spondylolisthesis had recurred. At this point, bilateral facetectomies were performed, with reduction/fixation of L3-4 by pedicle screws. Again, degenerative spondylolisthesis improved postsurgically and symptoms eased, with eventual healing of the vertebral body fracture. This report documents a rare instance of L-4 vertebral body fracture following use of a stand-alone device for ALIF at L3-4, likely as a consequence of angular instability in degenerative spondylolisthesis. Under such conditions, additional pedicle screw fixation is advised. PMID:24725181

Kwon, Yoon-Kwang; Jang, Ju-Hee; Lee, Choon-Dae; Lee, Sang-Ho

2014-06-01

182

Oxidation of carbon deposits as a fuel removal technique for application in fusion devices  

NASA Astrophysics Data System (ADS)

In tokamaks, such as ITER, with low-temperature, low-Z walls (Be or C), it is predicted that codeposition of hydrogen fuel with sputtered wall atoms will be the dominating mechanism for in-vessel tritium retention. Limits on in-vessel inventory will require the periodic removal of such tritium, and a variety of procedures have been proposed. In the case of carbon-based deposits, it is possible to use chemical reactions with oxygen to produce volatile products, which may be removed from the vacuum vessel via the vacuum pumps. Thermo-oxidation has some major advantages compared to other techniques for removing tritium from codeposits, in that it can act on all surfaces inside the vessel, including tile gaps and other non-line-of-sight surfaces, and there is no requirement for mechanical entry into the torus. This paper discusses recent experimental results and the use of oxidation in future tokamaks such as ITER.

Davis, J. W.; Haasz, A. A.

2009-06-01

183

Anterior cervical discectomy and fusion with a zero-profile integrated plate and spacer device: a clinical and radiological study.  

PubMed

Object Anterior cervical plating decreases the risk of pseudarthrosis following anterior cervical discectomy and fusion (ACDF). Dysphagia is a common complication of ACDF, with the anterior plate implicated as a potential contributor. A zero-profile, stand-alone polyetheretherketone (PEEK) interbody spacer has been postulated to minimize soft-tissue irritation and postoperative dysphagia, but studies are limited. The object of the present study was to determine the clinical and radiological outcomes for patients who underwent ACDF using a zero-profile integrated plate and spacer device, with a focus on the course of postoperative prevertebral soft-tissue thickness and the incidence of dysphagia. Methods Using a surgical database, the authors conducted a retrospective analysis of all patients who had undergone ACDF between August 2008 and October 2011. All patients received a Zero-P implant (DePuy Synthes Spine). The Neck Disability Index (NDI) and visual analog scale (VAS) scores for arm and neck pain were documented. Dysphagia was determined using the Bazaz criteria. Prevertebral soft-tissue thickness, spinal alignment, and subsidence were assessed as well. Results Twenty-two male and 19 female consecutive patients, with a mean age of 58.4 ± 14.68, underwent ACDF (66 total operated levels) in the defined study period. The mean clinical follow-up in 36 patients was 18.6 ± 9.93 months. Radiological outcome in 37 patients was assessed at a mean follow-up of 9.76 months (range 7.2-19.7 months). There were significant improvements in neck and arm VAS scores and the NDI following surgery. The neck VAS score improved from a median of 6 (range 0-10) to 0 (range 0-8; p < 0.001). The arm VAS score improved from a median of 2 (range 0-10) to 0 (range 0-7; p = 0.006). Immediate postoperative dysphagia was experienced by 58.4% of all patients. Complete resolution was demonstrated in 87.8% of affected patients at the latest follow-up. The overall median Bazaz score decreased from 1 (range 0-3) immediately postoperatively to 0 (range 0-2; p < 0.001) at the latest follow-up. Prevertebral soft-tissue thickness significantly decreased across all levels from a mean of 15.8 ± 4.38 mm to 10.1 ± 2.93 mm. Postoperative lordosis was maintained at the latest follow-up. Mean subsidence from the immediate postoperative to the latest follow-up was 4.1 ± 4.7 mm (p < 0.001). Radiographic fusion was achieved in 92.6% of implants. No correlation was found between prevertebral soft-tissue thickness and Bazaz dysphagia score. Conclusions A zero-profile integrated plate and spacer device for ACDF surgery produces clinical and radiological outcomes that are comparable to those for nonintegrated plate and spacer constructs. Chronic dysphagia rates are comparable to or better than those for previously published case series. PMID:25105338

Njoku, Innocent; Alimi, Marjan; Leng, Lewis Z; Shin, Benjamin J; James, Andrew R; Bhangoo, Sandeep; Tsiouris, Apostolos John; Härtl, Roger

2014-10-01

184

Preliminary Results of Low Pressure Discharge Experiments of a Cylindrical Inertial Electrostatic Confinement Fusion Device Aimed for a Small Neutron Source  

SciTech Connect

The effects of operating gas pressure on a Cylindrical Inertial Electrostatic Confinement Fusion (IECF) device are investigated. First we did glow discharge experiments, and we obtained 1.8 x 10{sup 6} neutrons production per second with 45-kV, 44-mA discharge at 1.2 Pa. Next we modified the device and tried to reduce the operating gas pressure with an ion source, aimed to increase neutron production. Although the discharge currents are small, we can make steady discharges at less than 0.1 Pa. The neutron production rates per current are larger than those of glow discharge at higher pressure. We consider it should suggest the validity of reducing operating pressure in IECF devices.

Higashi, Takanori; Tomizawa, Takahito; Daino, Mitsugu; Yamamoto, Yasushi [Kyoto University (Japan)

2003-09-15

185

Dosimetric verification of radiation therapy including intensity modulated treatments, using an amorphous-silicon electronic portal imaging device  

NASA Astrophysics Data System (ADS)

Radiation therapy is continuously increasing in complexity due to technological innovation in delivery techniques, necessitating thorough dosimetric verification. Comparing accurately predicted portal dose images to measured images obtained during patient treatment can determine if a particular treatment was delivered correctly. The goal of this thesis was to create a method to predict portal dose images that was versatile and accurate enough to use in a clinical setting. All measured images in this work were obtained with an amorphous silicon electronic portal imaging device (a-Si EPID), but the technique is applicable to any planar imager. A detailed, physics-motivated fluence model was developed to characterize fluence exiting the linear accelerator head. The model was further refined using results from Monte Carlo simulations and schematics of the linear accelerator. The fluence incident on the EPID was converted to a portal dose image through a superposition of Monte Carlo-generated, monoenergetic dose kernels specific to the a-Si EPID. Predictions of clinical IMRT fields with no patient present agreed with measured portal dose images within 3% and 3 mm. The dose kernels were applied ignoring the geometrically divergent nature of incident fluence on the EPID. A computational investigation into this parallel dose kernel assumption determined its validity under clinically relevant situations. Introducing a patient or phantom into the beam required the portal image prediction algorithm to account for patient scatter and attenuation. Primary fluence was calculated by attenuating raylines cast through the patient CT dataset, while scatter fluence was determined through the superposition of pre-calculated scatter fluence kernels. Total dose in the EPID was calculated by convolving the total predicted incident fluence with the EPID-specific dose kernels. The algorithm was tested on water slabs with square fields, agreeing with measurement within 3% and 3 mm. The method was then applied to five prostate and six head-and-neck IMRT treatment courses (˜1900 clinical images). Deviations between the predicted and measured images were quantified. The portal dose image prediction model developed in this thesis work has been shown to be accurate, and it was demonstrated to be able to verify patients' delivered radiation treatments.

Chytyk-Praznik, Krista Joy

186

Fusion-driven transmutations of nuclear waste—a misconception or an incentive for promotion of fusion energy?  

Microsoft Academic Search

A fusion-driven system of transmutation of nuclear waste is presented. The main positive aspect of this fusion power option, thanks to energy release from fission, is the prospect of a radical reduction of necessary plasma energy gain, Q, to levels achievable in relatively simple mirror devices. Further advantages of the system include lower FW load and homogeneous heating distribution. The

Stefan Taczanowski; Gra?yna Doma?ska; Jerzy Cetnar

1998-01-01

187

Controlled nuclear fusion apparatus  

Microsoft Academic Search

A fusion power generating device is disclosed having a relatively small and inexpensive core region which may be contained within an energy absorbing blanket region. The fusion power core region contains apparatus of the toroidal type for confining a high density plasma. The fusion power core is removable from the blanket region and may be disposed and\\/or recycled for subsequent

R. W. Bussard; B. Coppi

1982-01-01

188

Image fusion  

NASA Technical Reports Server (NTRS)

The topics covered include the following: a system overview of the basic components of a system designed to improve the ability of a pilot to fly through low-visibility conditions such as fog; the role of visual sciences; fusion issues; sensor characterization; sources of information; image processing; and image fusion.

Pavel, M.

1993-01-01

189

Overview of fusion reactor safety  

NASA Astrophysics Data System (ADS)

Use of deuterium-tritium fusion reactors requires examination of several major safety and environmental issues: (1) tritium inventory control; (2) neutron activation of structural materials, fluid streams and reactor hall environment; (3) release of radioactivity from energy sources including lithium spill reactions, superconducting magnet stored energy release, and plasma disruptions; (4) high magnetic and electromagnetic fields associated with fusion reactor superconducting magnets and radio frequency heating devices; and (5) handling and disposal of radioactive waste. Early recognition of potential safety problems with fusion reactors provides the opportunity for improvement in design and materials to eliminate or greatly reduce these problems. With an early start in this endeavor, fusion should be among the lower risk technologies for generation of commercial electrical power.

Cohen, S.; Crocker, J. G.

190

Fusion facility siting considerations  

SciTech Connect

Inherent in the fusion program's transition from hydrogen devices to commercial power machines is a general increase in the size and scope of succeeding projects. This growth will lead to increased emphasis on safety, environmental impact, and the external effects of fusion in general, and of each new device in particular. A critically important consideration in this regard is site selection. The purpose of this paper is to examine major siting issues that may affect the economics, safety, and environmental impact of fusion.

Bussell, G.T.

1985-01-01

191

78 FR 66942 - Orthopaedic and Rehabilitation Devices Panel of the Medical Devices Advisory Committee; Notice of...  

Federal Register 2010, 2011, 2012, 2013

...and to help promote intervertebral body fusion. During the arthrodesis procedure, they...intended for use in motion-sparing, non-fusion procedures. Spinal sphere devices are...under the heading of ``Intervertebral Fusion Device with Bone Graft,...

2013-11-07

192

Robotic-Assisted Device in Posterior Spinal Fusion for a High Risk Thoraculombar Fracture in Ankylosing Spondylitis  

PubMed Central

Fractures in ankylosing spondylitis (AS) are often difficult to treat and surgical treatment may be fraught with complications. We describe the use of a robotic-assisted device in the surgical treatment of an unstable L1 fracture in an elderly patient with chronic lymphocytic leukemia and AS. The postoperative course was uneventful and the patient was discharged after 3 days. The use of a robotic-assisted device in spine surgery is particularly indicated in difficult high risk cases. PMID:24596607

Suliman, Ali; Bernfeld, Benjamin; Bruskin, Alexander

2014-01-01

193

Comparative Study of Clinical and Radiological Outcomes of a Zero-Profile Device Concerning Reduced Postoperative Dysphagia after Single Level Anterior Cervical Discectomy and Fusion  

PubMed Central

Objective This study analyzed clinical and radiological outcomes of a zero-profile anchored spacer (Zero-P) and conventional cage-plate (CCP) for single level anterior cervical discectomy and fusion (ACDF) to compare the incidence and difference of postoperative dysphagia with both devices. Methods We retrospectively reviewed our experiences of single level ACDF with the CCP and Zero-P. From January 2011 to December 2013, 48 patients who had single level herniated intervertebral disc were operated on using ACDF, with CCP in 27 patients and Zero-P in 21 patients. Patients who received more than double-level ACDF or combined circumferential fusion were excluded. Age, operation time, estimated blood loss (EBL), pre-operative modified Japanese Orthopaedic Association (mJOA) scores, post-operative mJOA scores, achieved mJOA scores and recovery rate of mJOA scores were assessed. Prevertebral soft tissue thickness and postoperative dysphagia were analyzed on the day of surgery, and 2 weeks and 6 months postoperatively. Results The Zero-P group showed same or favorable clinical and radiological outcomes compared with the CCP group. Postoperative dysphagia was significantly low in the Zero-P group. Conclusions Application of Zero-P may achieve favorable outcomes and reduce postoperative dysphagia in single level ACDF.

Son, Doo Kyung; Kim, Ho Sang; Sung, Soon Ki; Lee, Sang Weon; Song, Geun Sung

2014-01-01

194

Which one is safer - performing a laparoscopic hysterectomy with a tissue fusion device involving diagnostic cystoscopy or traditional abdominal hysterectomy with ureteral dissection?  

PubMed Central

Introduction It still remains an unanswered question whether, in the absence of gynecological malignancy and under elective conditions, to perform abdominal hysterectomy (AH), offering a safer approach, or to perform a laparoscopic hysterectomy (LH) procedure. Aim We aimed to compare LH operations performed with a tissue fusion device accompanied by intraoperative diagnostic cystoscopy with traditional AH operations involving bilateral ureteral dissection. Material and methods The integrity of the ureters, ureteral peristalsis and the diameter of the ureters were examined during AH by inspection. At the end of LH, the bladder wall was systematically evaluated by cystoscopy and a jet of urine spurting was noted from both ureteral orifices. Results The operation time was longer in patients who underwent LH + CYS (p = 0.0001). The decline in hematocrit and hemoglobin levels in the postoperative period was significantly higher in patients who underwent AH + UD (p = 0.0001 and p = 0.002, respectively). No significant difference was found between the two groups in terms of ureteral injury, bowel injury or bladder injury (p = 0.378, p = 1.000 and p = 1.000, respectively). There was no statistically significant difference between the two groups in terms of mean body temperature and postoperative blood transfusion requirements (p = 0.051 and p = 0.210, respectively). Mean parenteral analgesic requirement and length of hospital stay were significantly different between the groups (p = 0.005 and p = 0.0001). No statistically significant difference was found between the two groups in terms of postoperative cardiopulmonary complications, re-operation rate or occurrence of genitourinary fistula (p = 1.000, p = 1.000 and p = 1.000, respectively). Conclusions We concluded that LH performed with a tissue fusion device involving diagnostic cystoscopy yields major and minor complication rates similar to safely performed AH operations preserving ureters. PMID:24501597

Yildiz, Gazi; Caglar, Mete; Alt?ntas, Rasit; Dilbaz, Serdar; Yildiz, Pinar; Kumru, Selahattin; Ustun, Yusuf

2013-01-01

195

Large Scale Computing and Storage Requirements for Fusion Energy Sciences: Target 2017  

E-print Network

with   background   thermal  plasmas.  This  case  study  either   be   for   thermal   plasma   components   with  plasma-­?facing   materials   in   a   steady-­?state   fusion   device   include   extreme   particle   and   thermal  

Gerber, Richard

2014-01-01

196

TranS1 VEO system: a novel psoas-sparing device for transpsoas lumbar interbody fusion  

PubMed Central

Minimally invasive approaches for lumbar interbody fusion have been popularized in recent years. The retroperitoneal transpsoas approach to the lumbar spine is a technique that allows direct lateral access to the intervertebral disc space while mitigating the complications associated with traditional anterior or posterior approaches. However, a common complication of this procedure is iatrogenic injury to the psoas muscle and surrounding nerves, resulting in postsurgical motor and sensory deficits. The TranS1 VEO system (TranS1 Inc, Raleigh, NC, USA) utilizes a novel, minimally invasive transpsoas approach to the lumbar spine that allows direct visualization of the psoas and proximal nerves, potentially minimizing iatrogenic injury risk and resulting clinical morbidity. This paper describes the clinical uses, procedural details, and indications for use of the TranS1 VEO system. PMID:23766663

Hardenbrook, Mitchell A; Miller, Larry E; Block, Jon E

2013-01-01

197

Fusion Energy Division: Annual progress report, period ending December 31, 1987  

SciTech Connect

The Fusion Program of Oak Ridge National Laboratory (ORNL), a major part of the national fusion program, carries out research in nearly all areas of magnetic fusion. Collaboration among staff from ORNL, Martin Marietta Energy Systems, Inc., private industry, the academic community, and other fusion laboratories, in the United States and abroad, is directed toward the development of fusion as an energy source. This report documents the program's achievements during 1987. Issued as the annual progress report of the ORNL Fusion Energy Division, it also contains information from components of the Fusion Program that are external to the division (about 15% of the program effort). The areas addressed by the Fusion Program include the following: experimental and theoretical research on magnetic confinement concepts, engineering and physics of existing and planned devices, development and testing of diagnostic tools and techniques in support of experiments, assembly and distribution to the fusion community of databases on atomic physics and radiation effects, development and testing of technologies for heating and fueling fusion plasmas, development and testing of superconducting magnets for containing fusion plasmas, and development and testing of materials for fusion devices. Highlights from program activities are included in this report. 126 figs., 15 tabs.

Morgan, O.B. Jr.; Berry, L.A.; Sheffield, J.

1988-11-01

198

Fusion Energy Division progress report, 1 January 1990--31 December 1991  

SciTech Connect

The Fusion Program of the Oak Ridge National Laboratory (ORNL), a major part of the national fusion program, encompasses nearly all areas of magnetic fusion research. The program is directed toward the development of fusion as an economical and environmentally attractive energy source for the future. The program involves staff from ORNL, Martin Marietta Energy systems, Inc., private industry, the academic community, and other fusion laboratories, in the US and abroad. Achievements resulting from this collaboration are documented in this report, which is issued as the progress report of the ORNL Fusion Energy Division; it also contains information from components for the Fusion Program that are external to the division (about 15% of the program effort). The areas addressed by the Fusion Program include the following: experimental and theoretical research on magnetic confinement concepts; engineering and physics of existing and planned devices, including remote handling; development and testing of diagnostic tools and techniques in support of experiments; assembly and distribution to the fusion community of databases on atomic physics and radiation effects; development and testing of technologies for heating and fueling fusion plasmas; development and testing of superconducting magnets for containing fusion plasmas; development and testing of materials for fusion devices; and exploration of opportunities to apply the unique skills, technology, and techniques developed in the course of this work to other areas (about 15% of the Division`s activities). Highlights from program activities during 1990 and 1991 are presented.

Sheffield, J.; Baker, C.C.; Saltmarsh, M.J.

1994-03-01

199

Usefulness of Leksell GammaPlan for preoperative planning of brain tumor resection: delineation of the cranial nerves and fusion of the neuroimaging data, including diffusion tensor imaging.  

PubMed

Leksell GammaPlan (LGP) software was initially designed for Gamma Knife radiosurgery, but it can be successfully applied to planning of the open neurosurgical procedures as well. We present our initial experience of delineating the cranial nerves in the vicinity of skull base tumors, combined visualization of the implanted subdural electrodes and cortical anatomy to facilitate brain mapping, and fusion of structural magnetic resonance imaging and diffusion tensor imaging performed with the use of LGP before removal of intracranial neoplasms. Such preoperative information facilitated choosing the optimal approach and general surgical strategy, and corresponded well to the intraoperative findings. Therefore, LGP may be helpful for planning open neurosurgical procedures in cases of both extraaxial and intraaxial intracranial tumors. PMID:23417477

Tamura, Manabu; Konishi, Yoshiyuki; Tamura, Noriko; Hayashi, Motohiro; Nakao, Naoyuki; Uematsu, Yuji; Itakura, Toru; Régis, Jean; Mangin, Jean François; Muragaki, Yoshihiro; Iseki, Hiroshi

2013-01-01

200

Fusion Energy Division progress report, January 1, 1992--December 31, 1994  

SciTech Connect

The report covers all elements of the ORNL Fusion Program, including those implemented outside the division. Non-fusion work within FED, much of which is based on the application of fusion technologies and techniques, is also discussed. The ORNL Fusion Program includes research and development in most areas of magnetic fusion research. The program is directed toward the development of fusion as an energy source and is a strong and vital component of both the US and international fusion efforts. The research discussed in this report includes: experimental and theoretical research on magnetic confinement concepts; engineering and physics of existing and planned devices; development and testing of plasma diagnostic tools and techniques; assembly and distribution of databases on atomic physics and radiation effects; development and testing of technologies for heating and fueling fusion plasmas; and development and testing of materials for fusion devices. The activities involving the use of fusion technologies and expertise for non-fusion applications ranged from semiconductor manufacturing to environmental management.

Sheffield, J.; Baker, C.C.; Saltmarsh, M.J.; Shannon, T.E.

1995-09-01

201

Spinal fusion  

MedlinePLUS

Vertebral interbody fusion; Posterior spinal fusion; Arthrodesis; Anterior spinal fusion; Spine surgery - spinal fusion ... Spinal fusion is most often done along with other surgical procedures of the spine. It may be done: With ...

202

Wireless Power May Cut the Cord for Plug-In Devices, Including Cars1 by Will Ferguson for National Geographic News, abbreviated2  

E-print Network

7 WiTricity, a company spun off from research at the Massachusetts Institute of Technology (MIT into an outlet. In WiTricity's lab, various devices run on9 power transmitted via electric coils through the air. WiTricity CEO Eric Giler imagines a future15 where power devices are embedded in the walls

South Bohemia, University of

203

Code for the 3D simulation of nanoscale semiconductor devices, including drift-diffusion and ballistic transport in 1D and 2D subbands, and 3D tunneling  

Microsoft Academic Search

Device modeling tools capable to address different degrees of quantum confinement and different transport regimes are required to address both MOSFETs at the end of the ITRS Roadmap and alternative device structures. In this work, we present a code based on the self-consistent solution of the i) many particle Schrodinger equation based on density functional theory, it) on the nonlinear

G. Fiori; G. Iannaccone

2004-01-01

204

An accurate and efficient self-consistent approach for calculating electron transport through molecular electronic devices: including the corrections of electrodes  

Microsoft Academic Search

A self-consistent ab initio approach for calculating electron transport through molecular electronic devices is developed. It is based on density functional theory (DFT) calculations and the Green's function technique employing a finite basis of local orbitals. The device is rigorously separated into the extended molecule region and the electrode region. In the DFT part calculating the Hamiltonian matrix of the

Jiaxing Zhang; Shimin Hou; Rui Li; Zekan Qian; Rushan Han; Ziyong Shen; Xingyu Zhao; Zengquan Xue

2005-01-01

205

Simulation and measurement of complete dye sensitised solar cells: including the influence of trapping, electrolyte, oxidised dyes and light intensity on steady state and transient device behaviour.  

PubMed

A numerical model of the dye sensitised solar cell (DSSC) is used to assess the importance of different loss pathways under various operational conditions. Based on our current understanding, the simulation describes the processes of injection, regeneration, recombination and transport of electrons, oxidised dye molecules and electrolyte within complete devices to give both time dependent and independent descriptions of performance. The results indicate that the flux of electrons lost from the nanocrystalline TiO(2) film is typically at least twice as large under conditions equivalent to 1 sun relative to dark conditions at matched TiO(2) charge concentration. This is in agreement with experimental observations (Barnes et al. Phys. Chem. Chem. Phys. [DOI: 10.1039/c0cp01855d]). The simulated difference in recombination flux is shown to be due to variation in the concentration profile of electron accepting species in the TiO(2) pores between light and dark conditions and to recombination to oxidised dyes in the light. The model is able to easily incorporate non-ideal behaviour of a cell such as the variation of open circuit potential with light intensity and non-first order recombination of conduction band electrons. The time dependent simulations, described by the multiple trapping model of electron transport and recombination, show good agreement with both small and large transient photocurrent and photovoltage measurements at open circuit, including photovoltage rise measurements. The simulation of photovoltage rise also suggests the possibility of assessing the interfacial resistance between the TiO(2) and substrate. When cells with a short diffusion length relative to film thickness were modelled, the simulated small perturbation photocurrent transients at short circuit (but not open circuit) yielded significantly higher effective diffusion coefficients than expected from the mean concentration of electrons and the electrolyte in the cell. This implies that transient measurements can overestimate the electron diffusion length in cells which have a low collection efficiency. The model should provide a useful general framework for exploring new cell descriptions, architectures and other factors influencing device performance. PMID:21327204

Barnes, Piers R F; Anderson, Assaf Y; Durrant, James R; O'Regan, Brian C

2011-04-01

206

Code for the 3D simulation of nanoscale semiconductor devices, including drift-diffusion and ballistic transport in 1D and 2D subbands, and 3D tunneling  

Microsoft Academic Search

We present a three-dimensional device simulator, suitable for the study of a wide range of nanoscale devices, in which quantum confinement and carrier transport are taken into account. In particular, depending on the confinement, the 1D, 2D or 3D Schrödinger equation with density functional theory in the local density approximation is coupled with the Poisson equation in the three-dimensional domain.

G. Fiori; G. Iannaccone

2005-01-01

207

Control mechanism for attenuation of thermal energy pulses using cold circulators in the cryogenic distribution system of fusion devices in tokamak configuration  

NASA Astrophysics Data System (ADS)

Operation and control of superconducting (SC) magnets in the fusion devices having tokamak configuration opens up the domain of varying peak thermal energy environment as a function of time, commensurate with the plasma pulses. The varied thermal energy environment, thus propagated to upstream of the cooling system, is responsible for the system level instability of the overall cryogenic system. The cryogenic distribution system, the regime of first impact point, therefore, has to be tuned so as to stay at the nearly stable zone of operation. The configuration of the cryogenic distribution system, considered in the present study, involves a liquid helium (LHe) bath as a thermal buffer, LHe submerged heat exchangers and cold circulator apart from the valves for implementations of the precise controls. The cold circulator supplies the forced flow supercritical helium, used for the cooling of SC magnets. The transients of the thermal energy pulses can be attenuated in the cryogenic distribution system by various methodologies. One of the adopted methodologies in the present study is with the precise speed control of the cold circulators. The adopted methodology is applied to various configurations of arrangements of internal components in the distribution system for obtaining system responses with superior attenuation of energy pulses. The process simulation approach, assumptions, considered inputs and constraints, process modeling with different configuration as well as results to accomplish the control scheme for the attenuation of the thermal energy pulses are described.

Bhattacharya, R.; Sarkar, B.; Vaghela, H.; Shah, N.

2014-01-01

208

Fusion Energy: Visions of the Future  

E-print Network

Scale, Terrapower, Areva Nat'l Ignition Facility, Iter, General Fusion TriAlpha, Polywell, LPP #12;DeuteriumFusion Energy: Visions of the Future Dec. 10-11, 2013 FOCUS FUSION Cheap, Clean, Safe & Unlimited Energy #12;Controlled Nuclear Fusion With a Dense Plasma Focus Device Running on Aneutronic Fuel What

209

General Atomics Fusion Group Educational Home Page  

NSDL National Science Digital Library

This site from the General Atomics Energy Group features a collection of educational resources on fusion. Both naturally occuring fusion and fusion as an energy source are included. Resources for teachers to use in the classroom are included.

2010-03-31

210

First wall for polarized fusion reactors  

DOEpatents

A first-wall or first-wall coating for use in a fusion reactor having polarized fuel may be formed of a low-Z non-metallic material having slow spin relaxation, i.e., a depolarization rate greater than 1 sec/sup -1/. Materials having these properties include hydrogenated and deuterated amorphous semiconductors. A method for preventing the rapid depolarization of a polarized plasma in a fusion device may comprise the step of providing a first-wall or first-wall coating formed of a low-Z, non-metallic material having a depolarization rate greater than 1 sec/sup -1/.

Greenside, H.S.; Budny, R.V.; Post, D.E. Jr.

1985-01-29

211

Probing the plasma near high power wave launchers in fusion devices for static and dynamic electric fields (invited)a)  

NASA Astrophysics Data System (ADS)

An exploratory study was carried out in the long-pulse tokamak Tore Supra, to determine if electric fields in the plasma around high-power, RF wave launchers could be measured with non-intrusive, passive, optical emission spectroscopy. The focus was in particular on the use of the external electric field Stark effect. The feasibility was found to be strongly dependent on the spatial extent of the electric fields and overlap between regions of strong (>˜1 kV/cm) electric fields and regions of plasma particle recycling and plasma-induced, spectral line emission. Most amenable to the measurement was the RF electric field in edge plasma, in front of a lower hybrid heating and current drive launcher. Electric field strengths and direction, derived from fitting the acquired spectra to a model including time-dependent Stark effect and the tokamak-range magnetic field Zeeman-effect, were found to be in good agreement with full-wave modeling of the observed launcher.

Klepper, C. C.; Martin, E. H.; Isler, R. C.; Colas, L.; Goniche, M.; Hillairet, J.; Panayotis, S.; Pegourié, B.; Jacquot, J.; Lotte, Ph.; Colledani, G.; Biewer, T. M.; Caughman, J. B.; Ekedahl, A.; Green, D. L.; Harris, J. H.; Hillis, D. L.; Shannon, S. C.; Litaudon, X.

2014-11-01

212

Probing the plasma near high power wave launchers in fusion devices for static and dynamic electric fields  

SciTech Connect

An exploratory study was carried out in the long-pulse tokamak Tore Supra, to determine if electric fields in the plasma around high-power, RF wave launchers could be measured with non-intrusive, passive, optical emission spectroscopy. The focus was in particular on the use of the external electric field Stark effect. The feasibility was found to be strongly dependent on the spatial extent of the electric fields and overlap between regions of strong (> 1 kV/cm) electric fields and regions of plasma particle recycling and plasma-induced, spectral line emission. Most amenable to the measurement was the RF electric field in edge plasma, in front of a lower hybrid heating and current drive launcher. Electric field strengths and direction, derived from fitting the acquired spectra to a model including time-dependent Stark effect and the tokamak-range magnetic field Zeeman-effect, were found to be in good agreement with full-wave modeling of the observed launcher.

Klepper, C Christopher [ORNL; Martin, Elijah H [ORNL; Isler, Ralph C [ORNL; Colas, L. [French Atomic Energy Commission (CEA), Cadarache, St. Paul lez Durance; Goniche, M. [French Atomic Energy Commission (CEA), Cadarache, St. Paul lez Durance; Hillairet, J. [French Atomic Energy Commission (CEA), Institute for Magnetic Fusion Research (IRFM); Panayotis, Stephanie [French Atomic Energy Commission (CEA), Institute for Magnetic Fusion Research (IRFM); Jacquot, Jonathan [French Atomic Energy Commission (CEA), Institute for Magnetic Fusion Research (IRFM); Lotte, Ph. [French Atomic Energy Commission (CEA), Cadarache, St. Paul lez Durance; Colledani, G. [French Atomic Energy Commission (CEA), Institute for Magnetic Fusion Research (IRFM); Biewer, Theodore M [ORNL; Caughman, J. B. O. [Oak Ridge National Laboratory (ORNL); Ekedahl, A. [French Atomic Energy Commission (CEA), Institute for Magnetic Fusion Research (IRFM); Green, David L [ORNL; Harris, Jeffrey H [ORNL; Hillis, Donald Lee [ORNL; Shannon, Prof. Steven [North Carolina State University; Litaudon, X [French Atomic Energy Commission (CEA)

2014-01-01

213

Response to "Fusion Power: Will It Come?" By W. E. Parkins Farrokh Najmabadi, University of California, San Diego  

E-print Network

-fired plants. Mr. Parkins overestimates the cost of blanket/shield in a fusion device by a factor of ten or more. He uses a heat flux of 0.3 MW/m2 to estimate the first wall area, citing a pressurized water ignores the fact that these components include a coolant. In a fusion plant such as ARIES-AT, coolant

214

Trends in fusion reactor safety research  

SciTech Connect

Fusion has the potential to be an attractive energy source. From the safety and environmental perspective, fusion must avoid concerns about catastrophic accidents and unsolvable waste disposal. In addition, fusion must achieve an acceptable level of risk from operational accidents that result in public exposure and economic loss. Finally, fusion reactors must control routine radioactive effluent, particularly tritium. Major progress in achieving this potential rests on development of low-activation materials or alternative fuels. The safety and performance of various material choices and fuels for commercial fusion reactors can be investigated relatively inexpensively through reactor design studies. These studies bring together experts in a wide range of backgrounds and force the group to either agree on a reactor design or identify areas for further study. Fusion reactors will be complex with distributed radioactive inventories. The next generation of experiments will be critical in demonstrating that acceptable levels of safe operation can be achieved. These machines will use materials which are available today and for which a large database exists (e.g. for 316 stainless steel). Researchers have developed a good understanding of the risks associated with operation of these devices. Specifically, consequences from coolant system failures, loss of vacuum events, tritium releases, and liquid metal reactions have been studied. Recent studies go beyond next step designs and investigate commercial reactor concerns including tritium release and liquid metal reactions. 18 refs.

Herring, J.S.; Holland, D.F.; Piet, S.J.

1991-01-01

215

MMMMaaaaggggnnnneeeettttiiiicccc FFFFuuuussssiiiioooonnnn EEEEnnnneeeerrrrggggyyyy MAGNETIC FUSION ENERGY  

E-print Network

FusionPlasma ScienceandTechnology Attractive Fusion Energy Previous Strategy Basic Plasma Science Innovative Concepts Science of Magnetic Fusion · The Magnetic Fusion Energy Portfolio · Science and Technology Spin Advanced Tokamaks Tokamaks NEW FUSION PROGRAM STRATEGY Portfolio of innovative concepts, including inertial

216

Heat Generation and Transport in Nanometer-Scale Transistors Heat problems in ever-smaller integrated circuits include hot-spots at transistor drain areas, reduced heat conduction in new devices and higher thermal resistance at material boundaries  

Microsoft Academic Search

As transistor gate lengths are scaled towards the 10-nm range, thermal device design is becoming an important part of microprocessor engineering. Decreasing dimensions lead to nanometer-scale hot spots in the transistor drain region, which may increase the drain series and source injection electrical resistances. Such trends are accelerated by the introduction of novel materials and nontraditional transistor geometries, including ultrathin

Eric Pop; Sanjiv Sinha; Kenneth E. Goodson

217

Research on fusion neutron sources  

NASA Astrophysics Data System (ADS)

The use of fusion devices as powerful neutron sources has been discussed for decades. Whereas the successful route to a commercial fusion power reactor demands steady state stable operation combined with the high efficiency required to make electricity production economic, the alternative approach to advancing the use of fusion is free of many of complications connected with the requirements for economic power generation and uses the already achieved knowledge of Fusion physics and developed Fusion technologies. "Fusion for Neutrons" (F4N), has now been re-visited, inspired by recent progress achieved on comparably compact fusion devices, based on the Spherical Tokamak (ST) concept. Freed from the requirement to produce much more electricity than used to drive it, a fusion neutron source could be efficiently used for many commercial applications, and also to support the goal of producing energy by nuclear power. The possibility to use a small or medium size ST as a powerful or intense steady-state fusion neutron source (FNS) is discussed in this paper in comparison with the use of traditional high aspect ratio tokamaks. An overview of various conceptual designs of compact fusion neutron sources based on the ST concept is given and they are compared with a recently proposed Super Compact Fusion Neutron Source (SCFNS), with major radius as low as 0.5 metres but still able to produce several MW of neutrons in a steady-state regime.

Gryaznevich, M. P.

2012-06-01

218

Research on fusion neutron sources  

SciTech Connect

The use of fusion devices as powerful neutron sources has been discussed for decades. Whereas the successful route to a commercial fusion power reactor demands steady state stable operation combined with the high efficiency required to make electricity production economic, the alternative approach to advancing the use of fusion is free of many of complications connected with the requirements for economic power generation and uses the already achieved knowledge of Fusion physics and developed Fusion technologies. 'Fusion for Neutrons' (F4N), has now been re-visited, inspired by recent progress achieved on comparably compact fusion devices, based on the Spherical Tokamak (ST) concept. Freed from the requirement to produce much more electricity than used to drive it, a fusion neutron source could be efficiently used for many commercial applications, and also to support the goal of producing energy by nuclear power. The possibility to use a small or medium size ST as a powerful or intense steady-state fusion neutron source (FNS) is discussed in this paper in comparison with the use of traditional high aspect ratio tokamaks. An overview of various conceptual designs of compact fusion neutron sources based on the ST concept is given and they are compared with a recently proposed Super Compact Fusion Neutron Source (SCFNS), with major radius as low as 0.5 metres but still able to produce several MW of neutrons in a steady-state regime.

Gryaznevich, M. P. [Tokamak Solutions UK, Culham Science Centre, Abingdon, OXON, OX133DB (United Kingdom)

2012-06-19

219

Fusion Energy Education  

NSDL National Science Digital Library

The basics of fusion are deceptively simple: the process powers the sun and other stars, and it all takes place when atomic nuclei collide at high speed. But many questions remain. How can humans develop and exploit fusion energy? Is there a way to convert it more efficiently into useful mechanical, electrical, or thermal energy? This intriguing site, created by the Lawrence Livermore National Laboratory and the Princeton Plasma Physics Laboratory, presents an online fusion course designed to teach students and others about how fusion works and how it might be harnessed in the future. Visitors can try out The Guided Tour to get started, or they can click on one of the Main Topics. These include Energy Sources and Conversions, Two Key Fusion Reactions, and Creating the Conditions for Fusion. Each section contains graphics, explanatory text, and various diagrams. The site also includes charts which can be printed out for classroom use.

220

An Assessment of Hazards Caused by Electromagnetic Interaction on Humans Present near Short-Wave Physiotherapeutic Devices of Various Types Including Hazards for Users of Electronic Active Implantable Medical Devices (AIMD)  

PubMed Central

Leakage of electromagnetic fields (EMF) from short-wave radiofrequency physiotherapeutic diathermies (SWDs) may cause health and safety hazards affecting unintentionally exposed workers (W) or general public (GP) members (assisting patient exposed during treatment or presenting there for other reasons). Increasing use of electronic active implantable medical devices (AIMDs), by patients, attendants, and workers, needs attention because dysfunctions of these devices may be caused by electromagnetic interactions. EMF emitted by 12 SWDs (with capacitive or inductive applicators) were assessed following international guidelines on protection against EMF exposure (International Commission on Nonionizing Radiation Protection for GP and W, new European directive 2013/35/EU for W, European Recommendation for GP, and European Standard EN 50527-1 for AIMD users). Direct EMF hazards for humans near inductive applicators were identified at a distance not exceeding 45?cm for W or 62?cm for GP, but for AIMD users up to 90?cm (twice longer than that for W and 50% longer than that for GP because EMF is pulsed modulated). Near capacitive applicators emitting continuous wave, the corresponding distances were: 120?cm for W or 150?cm for both—GP or AIMD users. This assessment does not cover patients who undergo SWD treatment (but it is usually recommended for AIMD users to be careful with EMF treatment). PMID:24089662

Gryz, Krzysztof

2013-01-01

221

Scalable data fusion using Astrolabe  

Microsoft Academic Search

The dramatic growth of computer networks creates both an opportunity and a daunting distributed computing problem for users seeking to perform data fusion and data mining. The problem is that data often resides on large numbers of devices and evolves rapidly. Systems that collect data at a single location scale poorly and suffer from single-point-failures. Astrolabe performs data fusion in

Kenneth P. Birman; Robbert van Renesse; Werner Vogels

2002-01-01

222

Fusion Science Education Outreach  

NASA Astrophysics Data System (ADS)

This presentation will focus on education outreach activities at General Atomics that have been expanded to include the general population on science education with a focus on fusion energy. Outreach materials are distributed upon request both nationally and internationally. These materials include a notebook containing copies of DIII--D tour panels, fusion poster, new fusion energy video, new fusion energy brochure, and the electromagnetic spectrum curriculum. The 1996 Fusion Forum (held in the House Caucus Room) included a student/ teacher lunch with Energy Secretary Hazel O'Leary and a private visit to the Forum exhibits. The continuing partnership with Kearny High School includes lectures, job shadowing, internship, equipment donations and an award-winning electric car-racing program. Development of distribution by CD of the existing interactive fusion energy kiosk and a virtual reality tour of the DIII--D facility are underway. The DIII--D fusion education WWW site includes e-mail addresses to ``Ask the Wizard,'' and/or receive GA's outreach materials. Steve Rodecker, a local science teacher, aided by DIII--D fusion staff, won his second Tapestry Award; he also was named the ``1995 National Science Teacher of the Year'' and will be present to share his experiences with the DIII--D educational outreach program.

Danielson, C. A.; DIII-D Education Group

1996-11-01

223

Nuclear fusion  

Microsoft Academic Search

The advantages of nuclear fusion as an energy source and research progress in this area are summarized. The current state of the art is described. Laser fusion, inertial confinement fusion, and magnetic fusion (the tokamak) are explained, the latter in some detail. Remaining problems and planned future reactors are considered. They are the Compact Ignition Tokamak (CIT), the International Thermonuclear

T. K. Fowler

1989-01-01

224

On dust grain interactions with fusion plasmas  

NASA Astrophysics Data System (ADS)

Recently different aspects of dust physics in fusion devices brought additional attention from both theoreticians and experimentalists, which, in part, was motivated by the work on the ITER project. To predict the role of dust in core plasma contamination and material migration we need to use some models describing the processes of the interactions of dust grains with fusion plasmas (including charging, forces and energy deposition). So far the models based on the interactions of collisionless plasma with the grain immersed in the self-consistent ambipolar electric field, which were developed for the study of so-called ``dusty plasmas'' are utilized. However, rather hot and dense edge plasma environment in fusion devices results in a strong heating of dust grain and subsequent grain sublimation and evaporation. When the vapor density and/or the amount of ionized impurity atoms become large enough they can alter the grain-plasma interactions. Somewhat similar processes occur during pellet injection in fusion plasma and the interactions of comets with sun radiation and Earth atmosphere. In this presentation we discuss: i) dust and plasma parameter range where the role of dust grain evaporation/sublimation and the processes associated with it do not have a significant impact on grain-plasma interactions, and ii) statistical issues of the description of dust-pasma interactions. This work was supported the US DoE under Grant DEFG02-04ER54852.

Krasheninnikov, Sergei; Smirnov, Roman

2009-11-01

225

Effect of superbanana diffusion on fusion reactivity in stellarators  

SciTech Connect

Fusion reactivity is usually obtained using a Maxwellian distribution. However, energy-dependent radial diffusion can modify the energy distribution. Superbanana diffusion is energy-dependent and occurs in nonaxisymmetric magnetic confinement devices, such as stellarators, because of ripple-trapped particles which can take large steps between collisions. In this paper, the D-T fusion reactivity is calculated using a non-Maxwellian energy distribution obtained by solving the Fokker-Planck equation numerically, including radial superbanana diffusion as well as energy scattering. The ions in the tail of the distribution, with energies larger than thermal, which are most needed for fusion, are depleted by superbanana diffusion. In this paper, it is shown that the D-T fusion reactivity is reduced by tail ion depletion due to superbanana diffusion, by roughly a factor of 0.5 for the parameters used in the calculation.

Hinton, Fred L. [Center for Astrophysics and Space Sciences, University of California, San Diego, La Jolla, California 92093-0424 (United States)

2012-08-15

226

Developments in inertial fusion energy and beam fusion at magnetic confinement  

Microsoft Academic Search

The 70-year anniversary of the first nuclear fusion reaction of hydrogen isotopes by Oliphant, Harteck, and Rutherford is an opportunity to realize how beam fusion is the path for energy production, including both branches, the magnetic confinement fusion and the inertial fusion energy (IFE). It is intriguing that Oliphant's basic concept for igniting controlled fusion reactions by beams has made

Heinrich Hora

2004-01-01

227

Empirical analysis of generalised uncertainty measures with dempster shafer fusion  

Microsoft Academic Search

Data fusion within the evidential reasoning framework is a well established, robust and conservative technique to fuse uncertain information from multiple sensors. A number of fusion methods within this formalism were introduced including Dempster-Shafer theory (DST) fusion, Dezert Samarandche fusion (DSmT), and Smets' transferable belief model (TBM) based fusion. However, the impact of fusion on the level of uncertainty within

Peter Pong; Subhash Challa

2007-01-01

228

Surgical Outcome of a Zero-profile Device Comparing with Stand-alone Cage and Anterior Cervical Plate with Iliac Bone Graft in the Anterior Cervical Discectomy and Fusion  

PubMed Central

Objective A Zero-profile device is a cervical stand-alone cage with integrated segmental fixation device. We characteristically evaluated the radiological changes as well as clinical outcomes in the application of Zero-profile devices compared with stand-alone cages and anterior cervical plates with iliac bone grafts for the cervical disease. Methods Retrospectively, total 60 patients at least more than one year follow-up were enrolled. Twenty patients were treated with Zero-profile devices (Group A), twenty patients with stand-alone cages (Group B) and twenty patients with anterior cervical plates and iliac bone grafts (Group C) for a single level cervical disease. The clinical outcomes were evaluated by Odom's criteria and Bazaz-Yoo dysphagia index. The radiologic parameters were by subsidence and the changes of the midpoint interbody height (IBH), the segmental kyphotic angle (SKA), the overall kyphotic angle (OKA) in index level. Results Although there was no significant clinical difference according to the Odom's criteria among them(p=0.766), post-operative dysphagia was significantly decreased in the Group A and B compared with the Group C (p=0.04). From the immediate postoperative to the last follow-up time, the mean change of IBH decrement and SKA increment were significant in the Group B compared with the Group A (p=0.025, p=0.033) and the Group C (p=0.001, p=0.000). The subsidence rate was not significant among all groups (p=0.338). Conclusion This Zero-profile device is a valuable alternative to the anterior cervical discectomy and fusion with a low incidence of postoperative dysphagia and without segmental kyphotic change. PMID:25346764

Shin, Jae Sik; Cho, Pyoung Goo

2014-01-01

229

Nuclear fusion  

SciTech Connect

The advantages of nuclear fusion as an energy source and research progress in this area are summarized. The current state of the art is described. Laser fusion, inertial confinement fusion, and magnetic fusion (the tokamak) are explained, the latter in some detail. Remaining problems and planned future reactors are considered. They are the compact ignition tokamak (CIT), the international thermonuclear experimental reactor (ITER), and TIBER II. The design of the latter is shown.

Fowler, T.K. (Dept. of Nuci. Eng., California Univ., Berkeley, CA (US))

1989-05-01

230

Fusion Basics  

NSDL National Science Digital Library

This website from the Princeton Plasma Physics Laboratory provides background information about fusion. Different sections cover fusion reactions, plasma heating, and how a fusion power plant would work. In addition, the site offers links to research projects at the Princeton Plasma Physics Laboratory.

2009-11-05

231

Glossary of fusion energy  

SciTech Connect

The Glossary of Fusion Energy is an attempt to present a concise, yet comprehensive collection of terms that may be beneficial to scientists and laymen who are directly or tangentially concerned with this burgeoning energy enterprise. Included are definitions of terms in theoretical plasma physics, controlled thermonuclear fusion, and some related physics concepts. Also, short descriptions of some of the major thermonuclear experiments currently under way in the world today are included.

Whitson, M.O. (ed.)

1985-02-01

232

Fusion Development Path Panel Preliminary Report  

E-print Network

Fusion Development Path Panel Preliminary Report Summary for NRC BPAC Panel (Focus on MFE of a demonstration power plant in approximately 35 years. The plan should recognize the capabilities of all fusion facilities around the world, and include both magnetic fusion energy (MFE) and inertial fusion energy (IFE

233

Fusion Protein Products Screen Purify Detect Cleave  

E-print Network

Fusion Protein Products · Screen · Purify · Detect · Cleave Fusion Protein Products · Screen researchers look to plasmid vectors to express fusion proteins, they find themselves in need of methods proteins is also included for those fusion proteins that may have an inaccessible tag. Pierce offers a host

Lebendiker, Mario

234

Lithium-based surfaces controlling fusion plasma behavior at the plasma-material interface  

SciTech Connect

The plasma-material interface and its impact on the performance of magnetically confined thermonuclear fusion plasmas are considered to be one of the key scientific gaps in the realization of nuclear fusion power. At this interface, high particle and heat flux from the fusion plasma can limit the material's lifetime and reliability and therefore hinder operation of the fusion device. Lithium-based surfaces are now being used in major magnetic confinement fusion devices and have observed profound effects on plasma performance including enhanced confinement, suppression and control of edge localized modes (ELM), lower hydrogen recycling and impurity suppression. The critical spatial scale length of deuterium and helium particle interactions in lithium ranges between 5-100 nm depending on the incident particle energies at the edge and magnetic configuration. Lithium-based surfaces also range from liquid state to solid lithium coatings on a variety of substrates (e.g., graphite, stainless steel, refractory metal W/Mo/etc., or porous metal structures). Temperature-dependent effects from lithium-based surfaces as plasma facing components (PFC) include magnetohydrodynamic (MHD) instability issues related to liquid lithium, surface impurity, and deuterium retention issues, and anomalous physical sputtering increase at temperatures above lithium's melting point. The paper discusses the viability of lithium-based surfaces in future burning-plasma environments such as those found in ITER and DEMO-like fusion reactor devices.

Allain, Jean Paul; Taylor, Chase N. [School of Nuclear Engineering, Purdue University, 400 Central Avenue, West Lafayette, Indiana 47907 (United States)

2012-05-15

235

Lithium-based surfaces controlling fusion plasma behavior at the plasma-material interfacea)  

NASA Astrophysics Data System (ADS)

The plasma-material interface and its impact on the performance of magnetically confined thermonuclear fusion plasmas are considered to be one of the key scientific gaps in the realization of nuclear fusion power. At this interface, high particle and heat flux from the fusion plasma can limit the material's lifetime and reliability and therefore hinder operation of the fusion device. Lithium-based surfaces are now being used in major magnetic confinement fusion devices and have observed profound effects on plasma performance including enhanced confinement, suppression and control of edge localized modes (ELM), lower hydrogen recycling and impurity suppression. The critical spatial scale length of deuterium and helium particle interactions in lithium ranges between 5-100 nm depending on the incident particle energies at the edge and magnetic configuration. Lithium-based surfaces also range from liquid state to solid lithium coatings on a variety of substrates (e.g., graphite, stainless steel, refractory metal W/Mo/etc., or porous metal structures). Temperature-dependent effects from lithium-based surfaces as plasma facing components (PFC) include magnetohydrodynamic (MHD) instability issues related to liquid lithium, surface impurity, and deuterium retention issues, and anomalous physical sputtering increase at temperatures above lithium's melting point. The paper discusses the viability of lithium-based surfaces in future burning-plasma environments such as those found in ITER and DEMO-like fusion reactor devices.

Allain, Jean Paul; Taylor, Chase N.

2012-05-01

236

Investigations of image fusion  

NASA Astrophysics Data System (ADS)

The objective of image fusion is to combine information from multiple images of the same scene. The result of image fusion is a single image which is more suitable for the purpose of human visual perception or further image processing tasks. In this thesis, a region-based fusion algorithm using the wavelet transform is proposed. The identification of important features in each image, such as edges and regions of interest, are used to guide the fusion process. The idea of multiscale grouping is also introduced and a generic image fusion framework based on multiscale decomposition is studied. The framework includes all of the existing multiscale-decomposition- based fusion approaches we found in the literature which did not assume a statistical model for the source images. Comparisons indicate that our framework includes some new approaches which outperform the existing approaches for the cases we consider. Registration must precede our fusion algorithms. So we proposed a hybrid scheme which uses both feature-based and intensity-based methods. The idea of robust estimation of optical flow from time- varying images is employed with a coarse-to-fine multi- resolution approach and feature-based registration to overcome some of the limitations of the intensity-based schemes. Experiments show that this approach is robust and efficient. Assessing image fusion performance in a real application is a complicated issue. In this dissertation, a mixture probability density function model is used in conjunction with the Expectation- Maximization algorithm to model histograms of edge intensity. Some new techniques are proposed for estimating the quality of a noisy image of a natural scene. Such quality measures can be used to guide the fusion. Finally, we study fusion of images obtained from several copies of a new type of camera developed for video surveillance. Our techniques increase the capability and reliability of the surveillance system and provide an easy way to obtain 3-D information of objects in the space monitored by the system.

Zhang, Zhong

1999-12-01

237

Fusion Power Deployment  

SciTech Connect

Fusion power plants could be part of a future portfolio of non-carbon dioxide producing energy supplies such as wind, solar, biomass, advanced fission power, and fossil energy with carbon dioxide sequestration. In this paper, we discuss key issues that could impact fusion energy deployment during the last half of this century. These include geographic issues such as resource availability, scale issues, energy storage requirements, and waste issues. The resource needs and waste production associated with fusion deployment in the U.S. should not pose serious problems. One important feature of fusion power is the fact that a fusion power plant should be locatable within most local or regional electrical distribution systems. For this reason, fusion power plants should not increase the burden of long distance power transmission to our distribution system. In contrast to fusion power, regional factors could play an important role in the deployment of renewable resources such as wind, solar and biomass or fossil energy with CO2 sequestration. We examine the role of these regional factors and their implications for fusion power deployment.

J.A. Schmidt; J.M. Ogden

2002-02-06

238

Ceramics for fusion applications  

SciTech Connect

Ceramics are required for a variety of uses in both near-term fusion devices and in commercial powerplants. These materials must retain adequate structural and electrical properties under conditions of neutron, particle, and ionizing irradiation; thermal and applied stresses; and physical and chemical sputtering. Ceramics such as Al/sub 2/O/sub 3/, MgAl/sub 2/O/sub 4/, BeO, Si/sub 3/N/sub 4/ and SiC are currently under study for fusion applications, and results to date show widely-varying response to the fusion environment. Materials can be identified today which will meet initial operating requirements, but improvements in physical properties are needed to achieve satisfactory lifetimes for critical applications.

Clinard, F.W. Jr.

1986-01-01

239

SAR and LIDAR fusion: experiments and applications  

NASA Astrophysics Data System (ADS)

In recent years ARTEMIS, Inc. has developed a series of compact, versatile Synthetic Aperture Radar (SAR) systems which have been operated on a variety of small manned and unmanned aircraft. The multi-frequency-band SlimSAR has demonstrated a variety of capabilities including maritime and littoral target detection, ground moving target indication, polarimetry, interferometry, change detection, and foliage penetration. ARTEMIS also continues to build upon the radar's capabilities through fusion with other sensors, such as electro-optical and infrared camera gimbals and light detection and ranging (LIDAR) devices. In this paper we focus on experiments and applications employing SAR and LIDAR fusion. LIDAR is similar to radar in that it transmits a signal which, after being reflected or scattered by a target area, is recorded by the sensor. The differences are that a LIDAR uses a laser as a transmitter and optical sensors as a receiver, and the wavelengths used exhibit a very different scattering phenomenology than the microwaves used in radar, making SAR and LIDAR good complementary technologies. LIDAR is used in many applications including agriculture, archeology, geo-science, and surveying. Some typical data products include digital elevation maps of a target area and features and shapes extracted from the data. A set of experiments conducted to demonstrate the fusion of SAR and LIDAR data include a LIDAR DEM used in accurately processing the SAR data of a high relief area (mountainous, urban). Also, feature extraction is used in improving geolocation accuracy of the SAR and LIDAR data.

Edwards, Matthew C.; Zaugg, Evan C.; Bradley, Joshua P.; Bowden, Ryan D.

2013-05-01

240

Fusion breeder  

SciTech Connect

The fusion breeder is a fusion reactor designed with special blankets to maximize the transmutation by 14 MeV neutrons of uranium-238 to plutonium or thorium to uranium-233 for use as a fuel for fission reactors. Breeding fissile fuels has not been a goal of the US fusion energy program. This paper suggests it is time for a policy change to make the fusion breeder a goal of the US fusion program and the US nuclear energy program. The purpose of this paper is to suggest this policy change be made and tell why it should be made, and to outline specific research and development goals so that the fusion breeder will be developed in time to meet fissile fuel needs.

Moir, R.W.

1982-04-20

241

Fusion breeder  

SciTech Connect

The fusion breeder is a fusion reactor designed with special blankets to maximize the transmutation by 14 MeV neutrons of uranium-238 to plutonium or thorium to uranium-233 for use as a fuel for fission reactors. Breeding fissile fuels has not been a goal of the US fusion energy program. This paper suggests it is time for a policy change to make the fusion breeder a goal of the US fusion program and the US nuclear energy program. The purpose of this paper is to suggest this policy change be made and tell why it should be made, and to outline specific research and development goals so that the fusion breeder will be developed in time to meet fissile fuel needs.

Moir, R.W.

1982-02-22

242

Modeling the time variation of beam-grid fusion reaction rates in an Inertial Electrostatic Confinement device driven by a ring-shaped magnetron ion source  

Microsoft Academic Search

We use the two-dimensional analysis code KUAD2 to simulate D^{+_{2}} trajectories in an Inertial Electrostatic Confinement (IEC) device driven by a ring-shaped magnetron ion source (RS-MIS). This aims to maximize the path length lambdaCX for ion-gas charge exchange by operating at just units of mPa D2 gas pressures; however, under these conditions simulations reveal a surprisingly small path length for

J. Kipritidis; K. Masuda; T. Kajiwara; Y. Yamagaki; K. Nagasaki

2011-01-01

243

Fusion product spectra  

SciTech Connect

Accurate fusion product data is required for most fusion plasma simulations. The energy broadening of reaction products is demonstrated to be more complicated than the usual Gaussian broadening. The accurate integrals are performed to obtain , , and for all binary reactions in the four- and five-nucleon systems. Reaction cross sections were developed using R-Matrix models that include most recent measurements.

Talley, T.L.; Hale, G.M.

1988-01-01

244

Annual Report of the EURATOM/CCFE Fusion Programme 2009/10 6.1 INTRODUCTION  

E-print Network

Annual Report of the EURATOM/CCFE Fusion Programme 2009/10 6.1 6 Theory 6 Theory 6.1 INTRODUCTION of energy in the tokamak; b) The avoidance or mitigation of instabilities that can limit plasma pressure, heating and current, and hence plasma performance, or damage the device ­ this for examples includes

245

The path to fusion power  

Microsoft Academic Search

Fusion, which powers the sun and stars, is potentially an environmentally responsible and intrinsically safe source of essentially\\u000a limitless energy. The Joint European Torus (JET) has produced 16 MW of fusion power, and construction of a power station sized\\u000a device called ITER (International Tokamak Experimental Reactor), which should produce at least 500 MW, is about to begin.\\u000a Further work on

C. Llewellyn Smith

2009-01-01

246

"Polarized" Fusion  

NASA Astrophysics Data System (ADS)

Increasing energy demand in view of limited supply, as well as environmental and nuclear-safety concerns leading to increased emphasis on renewable energy sources such as solar or wind energy are expected to focus public and scientific interest increasingly also on fusion energy. With the decision to build ITER (low-density magnetic confinement) and also continuing research on (high-density) inertial-confinement fusion (cf. the inauguration of the laser fusion facility at the Lawrence Livermore National Laboratory) prospects of fusion energy have probably entered a new era.

Schieck, Hans Paetz Gen.

247

Fusion Implementation  

SciTech Connect

If a fusion DEMO reactor can be brought into operation during the first half of this century, fusion power production can have a significant impact on carbon dioxide production during the latter half of the century. An assessment of fusion implementation scenarios shows that the resource demands and waste production associated with these scenarios are manageable factors. If fusion is implemented during the latter half of this century it will be one element of a portfolio of (hopefully) carbon dioxide limiting sources of electrical power. It is time to assess the regional implications of fusion power implementation. An important attribute of fusion power is the wide range of possible regions of the country, or countries in the world, where power plants can be located. Unlike most renewable energy options, fusion energy will function within a local distribution system and not require costly, and difficult, long distance transmission systems. For example, the East Coast of the United States is a prime candidate for fusion power deployment by virtue of its distance from renewable energy sources. As fossil fuels become less and less available as an energy option, the transmission of energy across bodies of water will become very expensive. On a global scale, fusion power will be particularly attractive for regions separated from sources of renewable energy by oceans.

J.A. Schmidt

2002-02-20

248

Fusion development and technology  

SciTech Connect

This report discusses the following: superconducting magnet technology; high field superconductors; advanced magnetic system and divertor development; poloidal field coils; gyrotron development; commercial reactor studies--aries; ITER physics: alpha physics and alcator R D for ITER; lower hybrid current drive and heating in the ITER device; ITER superconducting PF scenario and magnet analysis; ITER systems studies; and safety, environmental and economic factors in fusion development.

Montgomery, D.B.

1992-01-01

249

(Fusion energy research)  

SciTech Connect

This report discusses the following topics: principal parameters achieved in experimental devices (FY88); tokamak fusion test reactor; Princeton beta Experiment-Modification; S-1 Spheromak; current drive experiment; x-ray laser studies; spacecraft glow experiment; plasma deposition and etching of thin films; theoretical plasma; tokamak modeling; compact ignition tokamak; international thermonuclear experimental reactor; Engineering Department; Project Planning and Safety Office; quality assurance and reliability; and technology transfer.

Phillips, C.A. (ed.)

1988-01-01

250

Assisted fusion  

E-print Network

A model of nuclear fusion consisting of a wave packet impinging into a well located between square one dimensional barriers is treated analytically. The wave function inside the well is calculated exactly for the assisted tunneling induced by a perturbation mimicking a constant electric field with arbitrary time dependence. Conditions are found for the enhancement of fusion.

German Kälbermann

2009-10-19

251

FusionSeq: a modular framework for finding gene fusions by analyzing paired-end RNA-sequencing data  

PubMed Central

We have developed FusionSeq to identify fusion transcripts from paired-end RNA-sequencing. FusionSeq includes filters to remove spurious candidate fusions with artifacts, such as misalignment or random pairing of transcript fragments, and it ranks candidates according to several statistics. It also has a module to identify exact sequences at breakpoint junctions. FusionSeq detected known and novel fusions in a specially sequenced calibration data set, including eight cancers with and without known rearrangements. PMID:20964841

2010-01-01

252

Security on the US Fusion Grid  

SciTech Connect

The National Fusion Collaboratory project is developing and deploying new distributed computing and remote collaboration technologies with the goal of advancing magnetic fusion energy research. This work has led to the development of the US Fusion Grid (FusionGrid), a computational grid composed of collaborative, compute, and data resources from the three large US fusion research facilities and with users both in the US and in Europe. Critical to the development of FusionGrid was the creation and deployment of technologies to ensure security in a heterogeneous environment. These solutions to the problems of authentication, authorization, data transfer, and secure data storage, as well as the lessons learned during the development of these solutions, may be applied outside of FusionGrid and scale to future computing infrastructures such as those for next-generation devices like ITER.

Burruss, Justin R.; Fredian, Tom W.; Thompson, Mary R.

2005-06-01

253

Data security on the national fusion grid  

SciTech Connect

The National Fusion Collaboratory project is developing and deploying new distributed computing and remote collaboration technologies with the goal of advancing magnetic fusion energy research. This work has led to the development of the US Fusion Grid (FusionGrid), a computational grid composed of collaborative, compute, and data resources from the three large US fusion research facilities and with users both in the US and in Europe. Critical to the development of FusionGrid was the creation and deployment of technologies to ensure security in a heterogeneous environment. These solutions to the problems of authentication, authorization, data transfer, and secure data storage, as well as the lessons learned during the development of these solutions, may be applied outside of FusionGrid and scale to future computing infrastructures such as those for next-generation devices like ITER.

Burruss, Justine R.; Fredian, Tom W.; Thompson, Mary R.

2005-06-01

254

Magnetized Target Fusion  

NASA Technical Reports Server (NTRS)

Magnetized target fusion (MTF) is under consideration as a means of building a low mass, high specific impulse, and high thrust propulsion system for interplanetary travel. This unique combination is the result of the generation of a high temperature plasma by the nuclear fusion process. This plasma can then be deflected by magnetic fields to provide thrust. Fusion is initiated by a small traction of the energy generated in the magnetic coils due to the plasma's compression of the magnetic field. The power gain from a fusion reaction is such that inefficiencies due to thermal neutrons and coil losses can be overcome. Since the fusion reaction products are directly used for propulsion and the power to initiate the reaction is directly obtained from the thrust generation, no massive power supply for energy conversion is required. The result should be a low engine mass, high specific impulse and high thrust system. The key is to successfully initiate fusion as a proof-of-principle for this application. Currently MSFC is implementing MTF proof-of-principle experiments. This involves many technical details and ancillary investigations. Of these, selected pertinent issues include the properties, orientation and timing of the plasma guns and the convergence and interface development of the "pusher" plasma. Computer simulations of the target plasma's behavior under compression and the convergence and mixing of the gun plasma are under investigation. This work is to focus on the gun characterization and development as it relates to plasma initiation and repeatability.

Griffin, Steven T.

2002-01-01

255

Stellarator and Heliotron Devices  

Microsoft Academic Search

Stellarators and tokamaks are the most advanced devices that have been developed for magnetic fusion applications. The two approaches have much in common; tokamaks have received the most attention because their axisymmetry justifies the use of simpler models and provides a more forgiving geometry. However, recent advances in treating more complicated three dimensional systems have made it possible to design

John L. Johnson

1999-01-01

256

Transforaminal lumbar interbody fusion and posterior lumbar interbody fusion utilizing BMP-2 in treatment of degenerative spondylolisthesis: neither safe nor cost effective  

PubMed Central

Background: With the rise of health care costs, there is increased emphasis on evaluating the cost of a particular surgical procedure for quality adjusted life year (QALY) gained. Recent data have shown that surgical intervention for the treatment of degenerative spondylolisthesis (DS) is as cost-effective as total joint arthroplasty. Despite these excellent outcomes, some argue that the addition of interbody fusion supplemented with bone morphogenetic protein (BMP) enhances the value of this procedure. Methods: This review examines the current research regarding the cost-effectiveness of the surgical management of lumbar DS utilizing interbody fusion along with BMP. Results: Posterolateral spinal fusion with instrumentation for focal lumbar spinal stenosis with DS can provide and maintain improvement in self-reported quality of life. Based on the available literature, including nonrandomized comparative studies and case series, the addition of interbody fusion along with BMP does not lead to significantly better clinical outcomes and increases costs when compared with more routine posterolateral fusion techniques. Conclusions: To enhance the value of the surgical management for DS, costs must decrease or there should be substantial improvement in effectiveness as measured by clinical outcomes. To date, there is insufficient evidence to support the use of interbody fusion devices along with BMP to treat routine cases of focal stenosis accompanied by DS, which are routinely adequately treated utilizing posterolateral fusion techniques. PMID:23646277

Moatz, Bradley; Tortolani, P. Justin

2013-01-01

257

Measurement of magnetic field and velocity profiles in 3.6 kJ United Nations University/International Center For Theoretical Physics plasma focus fusion device  

SciTech Connect

A Mather-type small plasma focus device was operated in air filling in the pressure range of 0.5 to 1.0 Torr and capacitor bank charging voltage of 13{endash}15 kV. A strong focusing action was observed in this pressure range. Magnetic probe signals at various axial positions were used to estimate velocity of current sheet and axial magnetic field distribution profiles. It was observed that under the present experimental conditions the magnetic field remains constant at 0.72 T from {ital z}=0.0 cm to {ital z}=8.0 cm but falls rapidly to 0.52 T at about {ital z}=14.5 cm at a fixed radial distance of 2.65 cm. The magnetic field and velocity measurements indicate a current shedding effect{emdash}only 68.5{percent} of the total injected current flows into the focus region. The rapid drop of the magnetic field at {ital z}=8.0 cm suggests that further (initial shedding is at the insulator) current and mass shedding in the focus tube is significant after this value of {ital z}. Experimental values of velocity of the current sheet are compared with those of the snow plough theoretical model. {copyright} {ital 1996 American Institute of Physics.}

Mathuthu, M.; Zengeni, T.G. [Physics Department, University of Zimbabwe, Harare (Zimbabwe)] [Physics Department, University of Zimbabwe, Harare (Zimbabwe); Gholap, A.V. [Applied Physics Department, National University of Science and Technology, Bulawayo (Zimbabwe)] [Applied Physics Department, National University of Science and Technology, Bulawayo (Zimbabwe)

1996-12-01

258

The project is to design a power supply that will drive a piezoelectric device. The requirements for this power supply include: 1-20 Watts output power, 120VAC input voltage,  

E-print Network

Stain Remover. The Buzz device controls a small piezoelectric material which vibrates and removes stains for the final presentation is a reverse engineered version of the Ultrasonic Buzz Stain Remove. The deliverables does more than what he wants. The project is to analyze and reverse engineer the Buzz device, remove

Demirel, Melik C.

259

The scientific status of fusion  

NASA Astrophysics Data System (ADS)

The development of fusion energy has been a large-scale scientific undertaking of broad interest. The magnetic plasma containment in tokamaks and the laser-drive ignition of microfusion capsules appear to be scientifically feasible sources of energy. These concepts are bounded by questions of required intensity in magnetic field and plasma currents or in drive energy and, for both concepts, by issues of plasma stability and energy transport. The basic concept and the current scientific issues are described for magnetic fusion and for the interesting, but likely infeasible, muon-catalyzed fusion concept. Inertial fusion is mentioned, qualitatively, to complete the context. Fusion appears to release energy in rather large quantities (about 1000 MW) and significant new devices are needed to make progress. For magnetic fusion, the required net energy production within the plasma may be accomplished soon, but the more useful goal of self-sustained plasma ignition requires a new device of somewhat uncertain (factor of 2) cost and size.

Crandall, D. H.

1989-07-01

260

Automated targeting data fusion (ATDF)  

Microsoft Academic Search

Automated all source data fusion primarily fuses analyst generated messages. The Automated Targeting Data Fusion (ATDF) effort created an application that rapidly associated very diverse information sources automatically. In recent military conflict situations, enormous amounts of multi-source data have been made available to war-fighters. These data include imagery, signals intelligence, acoustic information, input from human analysts, and other sources. The

Randy K. Young; Peter S. Wyckoff; James H. Wise

2003-01-01

261

Cellulose binding domain fusion proteins  

DOEpatents

A cellulose binding domain (CBD) having a high affinity for crystalline cellulose and chitin is disclosed, along with methods for the molecular cloning and recombinant production. Fusion products comprising the CBD and a second protein are likewise described. A wide range of applications are contemplated for both the CBD and the fusion products, including drug delivery, affinity separations, and diagnostic techniques. 16 figs.

Shoseyov, O.; Yosef, K.; Shpiegl, I.; Goldstein, M.A.; Doi, R.H.

1998-02-17

262

Cellulose binding domain fusion proteins  

DOEpatents

A cellulose binding domain (CBD) having a high affinity for crystalline cellulose and chitin is disclosed, along with methods for the molecular cloning and recombinant production thereof. Fusion products comprising the CBD and a second protein are likewise described. A wide range of applications are contemplated for both the CBD and the fusion products, including drug delivery, affinity separations, and diagnostic techniques.

Shoseyov, Oded (Karmey Yosef, IL); Shpiegl, Itai (Rehovot, IL); Goldstein, Marc A. (Davis, CA); Doi, Roy H. (Davis, CA)

1998-01-01

263

Fusion Simulation  

NSDL National Science Digital Library

In this activity, kids are able to see with their own eyes how fusion works. The simple experiment requires only Velcro and two strong magnets.The activity begins with a brief overview that introduces students to the science they are about to see. Then, the procedure is laid out in simple step-by-step directions. The activity ends with an explanation that gives students a deeper understanding of how what they've just witnessed relates to fusion.

264

Glow Discharge Characteristics in Relation to Anode Size in Inertial Electrostatic Confinement Fusion  

Microsoft Academic Search

An Inertial Electrostatic Confinement Fusion device is a very simple and safe neutron source that uses a glow discharge for deuterium-deuterium fusion. The discharge characteristics of the device were studied experimentally. The relationship between gas pressure and applied voltage was examined by light changes of the device's anode size. The gas pressure ranges in which the device was able to

Hodaka Osawa; Shigehisa Yoshimura; Takehiro Tabata; Masami Ohnishi

2008-01-01

265

Plasma Physics. Basic Theory with Fusion Applications  

Microsoft Academic Search

Plasma Physics - Basic Theory with Fusion Applications presents a thorough treatment of plasma physics, beginning at an introductory level and including an extensive discussion of its applications in thermonuclear fusion research. The physics of fusion plasmas is explained mainly in relation to recent progress in tokamak research, but other plasma confinement schemes, such as stellarators and inertial confinement, are

Kyoji Nishikawa; Masahiro Wakatani

1994-01-01

266

Plasma Physics. Basic Theory with Fusion Applications  

Microsoft Academic Search

Beginning at an introductory level, this text presents a thorough treatment of plasma physics, including an extensive discussion of its applications in thermonuclear fusion research. A novel feature of this book is its comprehensive description of the various concepts and formulas widely used in fusion theory based on the fundamental equations of the plasma fluid. The physics of fusion plasmas

Kyoji Nishikawa; Masashiro Wakatani

1990-01-01

267

A wavelet-based image fusion tutorial  

Microsoft Academic Search

The objective of image fusion is to combine information from multiple images of the same scene. The result of image fusion is a new image which is more suitable for human and machine perception or further image-processing tasks such as segmentation, feature extraction and object recognition. Di4erent fusion methods have been proposed in literature, including multiresolution analysis. This paper is

Gonzalo Pajares; Jesús Manuel De La Cruz

2004-01-01

268

RSNA 2002: Image Fusion Image Fusion  

E-print Network

RSNA 2002: Image Fusion Image Fusion: Introduction to the Technology Charles A. Pelizzari, Ph.D. Department of Radiation and Cellular Oncology The University of Chicago #12;RSNA 2002: Image Fusion "Fusion and limitations) ·Where do we need to go? (future directions) #12;RSNA 2002: Image Fusion Terminology

Pelizzari, Charles A.

269

Fracto-fusion. Mechanism of cold fusion  

Microsoft Academic Search

As a cold fusion mechanism, a fracto-fusion was investigated by which reacting particles are accelerated by the electric field generated between the crack surfaces in a crystal and the beam fusion occurs. By assuming the possible magnitude of the potential difference the fusion rate and energy multiplication factor were calculated. These results are consistent with cold fusion experiments. On the

Tatsuoki Takeda; Tomonori Takizuka

1989-01-01

270

Comparison of Options for a Pilot Plant Fusion Nuclear Mission  

SciTech Connect

A fusion pilot plant study was initiated to clarify the development needs in moving from ITER to a first of a kind fusion power plant, following a path similar to the approach adopted for the commercialization of fission. The pilot plant mission encompassed component test and fusion nuclear science missions plus the requirement to produce net electricity with high availability in a device designed to be prototypical of the commercial device. Three magnetic configuration options were developed around this mission: the advanced tokamak (AT), spherical tokamak (ST) and compact stellarator (CS). With the completion of the study and separate documentation of each design option a question can now be posed; how do the different designs compare with each other as candidates for meeting the pilot plant mission? In a pro/con format this paper will examine the key arguments for and against the AT, ST and CS magnetic configurations. Key topics addressed include: plasma parameters, device configurations, size and weight comparisons, diagnostic issues, maintenance schemes, availability influences and possible test cell arrangement schemes.

Brown, T; Goldston, R J; El-Guebaly, L; Kessel, C; Neilson, G H; Malang, S; Menard, J E; Prager, S; Waganer, L; Titus, P

2012-08-27

271

Revisions to the JDL data fusion model  

Microsoft Academic Search

The Joint Directors of Laboratories {(JDL)} Data Fusion Group's Data Fusion Model is the most widely used method for categorizing data fusion-related functions. This model is modified to facilitate the cost-effective development, acquisition, integration and operation of multi-sensor\\/multi-source systems. Proposed modifications include broadening of the functional model and related taxonomy beyond the original military focus, and integrating the Data Fusion

A. N. Steinberg; C. L. Bowman; F. E. White

1999-01-01

272

Multimodal options for materials research to advance the basis for fusion energy in the ITER era  

NASA Astrophysics Data System (ADS)

Well-coordinated international fusion materials research on multiple fundamental feasibility issues can serve an important role during the next ten years. Due to differences in national timelines and fusion device concepts, a parallel-track (multimodal) approach is currently being used for developing fusion energy. An overview is given of the current state-of-the-art of major candidate materials systems for next-step fusion reactors, including a summary of existing knowledge regarding operating temperature and neutron irradiation fluence limits due to high-temperature strength and radiation damage considerations, coolant compatibility information, and current industrial manufacturing capabilities. There are two inter-related overarching objectives of fusion materials research to be performed in the next decade: (1) understanding materials science phenomena in the demanding DT fusion energy environment, and (2) application of this knowledge to develop and qualify materials to provide the basis for next-step facility construction authorization by funding agencies and public safety licensing authorities. The critical issues and prospects for development of high-performance fusion materials are discussed along with recent research results and planned activities of the international materials research community.

Zinkle, S. J.; Möslang, A.; Muroga, T.; Tanigawa, H.

2013-10-01

273

Alternative approaches to fusion. [reactor design and reactor physics for Tokamak fusion reactors  

NASA Technical Reports Server (NTRS)

The limitations of the Tokamak fusion reactor concept are discussed and various other fusion reactor concepts are considered that employ the containment of thermonuclear plasmas by magnetic fields (i.e., stellarators). Progress made in the containment of plasmas in toroidal devices is reported. Reactor design concepts are illustrated. The possibility of using fusion reactors as a power source in interplanetary space travel and electric power plants is briefly examined.

Roth, R. J.

1976-01-01

274

Fusion welding process  

DOEpatents

A process for the fusion welding of nickel alloy steel members wherein a ferrite containing pellet is inserted into a cavity in one member and melted by a welding torch. The resulting weld nugget, a fusion of the nickel containing alloy from the members to be welded and the pellet, has a composition which is sufficiently low in nickel content such that ferrite phases occur within the weld nugget, resulting in improved weld properties. The steel alloys encompassed also include alloys containing carbon and manganese, considered nickel equivalents.

Thomas, Kenneth C. (Export, PA); Jones, Eric D. (Salem, PA); McBride, Marvin A. (Hempfield Township, Westmoreland County, PA)

1983-01-01

275

Myoblast fusion in Drosophila  

SciTech Connect

The body wall musculature of a Drosophila larva is composed of an intricate pattern of 30 segmentally repeated muscle fibers in each abdominal hemisegment. Each muscle fiber has unique spatial and behavioral characteristics that include its location, orientation, epidermal attachment, size and pattern of innervation. Many, if not all, of these properties are dictated by founder cells, which determine the muscle pattern and seed the fusion process. Myofibers are then derived from fusion between a specific founder cell and several fusion competent myoblasts (FCMs) fusing with as few as 3-5 FCMs in the small muscles on the most ventral side of the embryo and as many as 30 FCMs in the larger muscles on the dorsal side of the embryo. The focus of the present review is the formation of the larval muscles in the developing embryo, summarizing the major issues and players in this process. We have attempted to emphasize experimentally-validated details of the mechanism of myoblast fusion and distinguish these from the theoretically possible details that have not yet been confirmed experimentally. We also direct the interested reader to other recent reviews that discuss myoblast fusion in Drosophila, each with their own perspective on the process . With apologies, we use gene nomenclature as specified by Flybase (http://flybase.org) but provide Table 1 with alternative names and references.

Haralalka, Shruti [Stowers Institute for Medical Research, Kansas City, MO 64110 (United States)] [Stowers Institute for Medical Research, Kansas City, MO 64110 (United States); Abmayr, Susan M., E-mail: sma@stowers.org [Stowers Institute for Medical Research, Kansas City, MO 64110 (United States); Department of Anatomy and Cell Biology, University of Kansas Medical Center, Kansas City, MO 66160 (United States)

2010-11-01

276

EDITORIAL: The Nuclear Fusion Award The Nuclear Fusion Award  

NASA Astrophysics Data System (ADS)

The Nuclear Fusion Award ceremony for 2009 and 2010 award winners was held during the 23rd IAEA Fusion Energy Conference in Daejeon. This time, both 2009 and 2010 award winners were celebrated by the IAEA and the participants of the 23rd IAEA Fusion Energy Conference. The Nuclear Fusion Award is a paper prize to acknowledge the best distinguished paper among the published papers in a particular volume of the Nuclear Fusion journal. Among the top-cited and highly-recommended papers chosen by the Editorial Board, excluding overview and review papers, and by analyzing self-citation and non-self-citation with an emphasis on non-self-citation, the Editorial Board confidentially selects ten distinguished papers as nominees for the Nuclear Fusion Award. Certificates are given to the leading authors of the Nuclear Fusion Award nominees. The final winner is selected among the ten nominees by the Nuclear Fusion Editorial Board voting confidentially. 2009 Nuclear Fusion Award nominees For the 2009 award, the papers published in the 2006 volume were assessed and the following papers were nominated, most of which are magnetic confinement experiments, theory and modeling, while one addresses inertial confinement. Sabbagh S.A. et al 2006 Resistive wall stabilized operation in rotating high beta NSTX plasmas Nucl. Fusion 46 635-44 La Haye R.J. et al 2006 Cross-machine benchmarking for ITER of neoclassical tearing mode stabilization by electron cyclotron current drive Nucl. Fusion 46 451-61 Honrubia J.J. et al 2006 Three-dimensional fast electron transport for ignition-scale inertial fusion capsules Nucl. Fusion 46 L25-8 Ido T. et al 2006 Observation of the interaction between the geodesic acoustic mode and ambient fluctuation in the JFT-2M tokamak Nucl. Fusion 46 512-20 Plyusnin V.V. et al 2006 Study of runaway electron generation during major disruptions in JET Nucl. Fusion 46 277-84 Pitts R.A. et al 2006 Far SOL ELM ion energies in JET Nucl. Fusion 46 82-98 Berk H.L. et al 2006 Explanation of the JET n = 0 chirping mode Nucl. Fusion 46 S888-97 Urano H. et al 2006 Confinement degradation with beta for ELMy HH-mode plasmas in JT-60U tokamak Nucl. Fusion 46 781-7 Izzo V.A. et al 2006 A numerical investigation of the effects of impurity penetration depth on disruption mitigation by massive high-pressure gas jet Nucl. Fusion 46 541-7 Inagaki S. et al 2006 Comparison of transient electron heat transport in LHD helical and JT-60U tokamak plasmas Nucl. Fusion 46 133-41 Watanabe T.-H. et al 2006 Velocity-space structures of distribution function in toroidal ion temperature gradient turbulence Nucl. Fusion 46 24-32 2010 Nuclear Fusion Award nominees For the 2010 award, the papers published in the 2007 volume were assessed and the following papers were nominated, all of which are magnetic confinement experiments and theory. Rice J.E. et al 2007 Inter-machine comparison of intrinsic toroidal rotation in tokamaks Nucl. Fusion 47 1618-24 Lipschultz B. et al 2007 Plasma-surface interaction, scrape-off layer and divertor physics: implications for ITER Nucl. Fusion 47 1189-205 Loarer T. et al 2007 Gas balance and fuel retention in fusion devices Nucl. Fusion 47 1112-20 Garcia O.E et al 2007 Fluctuations and transport in the TCV scrape-off layer Nucl. Fusion 47 667-76 Zonca F. et al 2007 Electron fishbones: theory and experimental evidence Nucl. Fusion 47 1588-97 Maggi C.F. et al 2007 Characteristics of the H-mode pedestal in improved confinement scenarios in ASDEX Upgrade, DIII-D, JET and JT-60U Nucl. Fusion 47 535-51 Yoshida M. et al 2007 Momentum transport and plasma rotation profile in toroidal direction in JT-60U L-mode plasmas Nucl. Fusion 47 856-63 Zohm H. et al 2007 Control of MHD instabilities by ECCD: ASDEX Upgrade results and implications for ITER Nucl. Fusion 47 228-32 Snyder P.B. et al 2007 Stability and dynamics of the edge pedestal in the low collisionality regime: physics mechanisms for steady-state ELM-free operation Nucl. Fusion 47 961-8 Urano H. et al 2007 H-mode pedestal structure in the variation of toroidal rotation and toroidal f

Kikuchi, M.

2011-01-01

277

Detection device  

DOEpatents

The present invention is directed to a detection device comprising: (1) an entrance chamber, (2) a central chamber, and (3) an exit chamber. The central chamber includes an ionizing gas, anode, and means for connecting the anode with an external power supply and pulse counter.

Smith, Jay E. (Pittsburgh, PA)

1984-01-01

278

Detection device  

DOEpatents

The present invention is directed to a detection device comprising: (1) an entrance chamber; (2) a central chamber; and (3) an exit chamber. The central chamber includes an ionizing gas, anode, and means for connecting the anode with an external power supply and pulse counter.

Smith, J.E.

1981-02-27

279

Optimization of Processing and Modeling Issues for Thin Film Solar Cell Devices Including Concepts for the Development of Polycrystalline Multijunctions Annual Subcontract Report, 24 August 1999 - 23 August 2000  

SciTech Connect

This report describes the results achieved during Phase I of a three-phase subcontract to develop and understand thin-film solar cell technology associated with CuInSe2 and related alloys, a-Si and its alloys, and CdTe. Modules based on all these thin films are promising candidates to meet DOE long-range efficiency, reliability, and manufacturing cost goals. The critical issues being addressed under this program are intended to provide the science and engineering basis for developing viable commercial processes and to improve module performance. The generic research issues addressed are: (1) quantitative analysis of processing steps to provide information for efficient commercial-scale equipment design and operation; (2) device characterization relating the device performance to materials properties and process conditions; (3) development of alloy materials with different bandgaps to allow improved device structures for stability and compatibility with module design; (4) development of improved window/heterojunction layers and contacts to improve device performance and reliability; and (5) evaluation of cell stability with respect to illumination, temperature, and ambient, and with respect to device structure and module encapsulation.

Birkmire, R. W.; Phillips, J. E.; Shafarman, W. N.; Eser, E.; Hegedus, S. S.; McCandless, B. E.

2001-11-14

280

Cold fusion: Alchemist's dream  

Microsoft Academic Search

In this report the following topics relating to cold fusion are discussed: muon catalyzed cold fusion; piezonuclear fusion; sundry explanations pertaining to cold fusion; cosmic ray muon catalyzed cold fusion; vibrational mechanisms in excited states of D2 molecules; barrier penetration probabilities within the hydrogenated metal lattice\\/piezonuclear fusion; branching ratios of D2 fusion at low energies; fusion of deuterons into He-4;

E. D. Clayton

1989-01-01

281

Near Term Fission-Fusion Hybrids- Advantages for Fission and Fusion  

NASA Astrophysics Data System (ADS)

Fission-fusion hybrids are described with unique advantages relative to fission only systems, for different missions. Innovative designs allow hybrids to incinerate waste, or produce fuel, with far fewer hybrids than would be possible with fission-only fast reactors. In addition, hybrids can perform these missions while addressing concerns regarding proliferation, by using unique fuel cycles, not accessible to fission alone, that use no reprocessing, or greatly reduced reprocessing. These goals can be achieved using fusion devices in the range considered for fusion Component Test Facilities (CTF). The fusion physics and fusion engineering performance necessary for these missions is far less stringent than for a pure fusion power reactor. Unique designs aspects substantially separate the fission and fusion aspects, allowing much more independent development of each. Hence, a suitable hybrid can provide a nearer term, lower risk, application for fusion, and be an additional incentive to implement a fusion CTF device. The fuel cycle possibilities above are verified using Monte-Carlo neutron calculations. Fusion neutron sources with high power densities and modest power levels are sufficient and necessary.

Kotschenreuther, M.; Mahajan, S.; Valanju, P.

2010-11-01

282

Overview of University of Wisconsin Inertial-Electrostatic Confinement Fusion Research  

SciTech Connect

In Inertial Electrostatic Confinement (IEC) devices, a voltage difference between concentric, nearly transparent spherical grids accelerates ions to fusion-relevant velocities. The University of Wisconsin (UW) operates two IEC devices: a cylindrical aluminum chamber and a spherical, water-cooled, stainless-steel chamber, with a power supply capable of 75 mA and 200 kV. The research program aims to generate fusion reaction products for various applications, including protons for creating radioisotopes for nuclear medicine and neutrons for detecting clandestine materials. Most IEC devices worldwide, including the UW devices, presently operate primarily in a pressure range (1-10 mtorr) that allows ions to make only a few passes through the core before they charge exchange and lose substantial energy or they collide with cathode grid wires. It is believed that fusion rates can be raised by operating at a pressure where neutral gas does not impede ion flow, and a helicon ion source has been developed to explore operation at pressures of {approx}0.05 mtorr. The UW IEC research group uses proton detectors, neutron detectors, residual gas analyzers, and spectroscopic diagnostics. New diagnostic techniques have also been developed, including eclipse disks to localize proton production and chordwires to estimate ion fluxes using power balance.

Santarius, J.F.; Kulcinski, G.L.; Ashley, R.P.; Boris, D.R.; Cipiti, B.B.; Murali, S. Krupakar; Piefer, G.R.; Radel, R.F.; Radel, T.E.; Wehmeyer, A.L. [University of Wisconsin (United States)

2005-05-15

283

Selectively detail-enhanced fusion of differently exposed images with moving objects.  

PubMed

In this paper, we introduce an exposure fusion scheme for differently exposed images with moving objects. The proposed scheme comprises a ghost removal algorithm in a low dynamic range domain and a selectively detail-enhanced exposure fusion algorithm. The proposed ghost removal algorithm includes a bidirectional normalization-based method for the detection of nonconsistent pixels and a two-round hybrid method for the correction of nonconsistent pixels. Our detail-enhanced exposure fusion algorithm includes a content adaptive bilateral filter, which extracts fine details from all the corrected images simultaneously in gradient domain. The final image is synthesized by selectively adding the extracted fine details to an intermediate image that is generated by fusing all the corrected images via an existing multiscale algorithm. The proposed exposure fusion algorithm allows fine details to be exaggerated while existing exposure fusion algorithms do not provide such an option. The proposed scheme usually outperforms existing exposure fusion schemes when there are moving objects in real scenes. In addition, the proposed ghost removal algorithm is simpler than existing ghost removal algorithms and is suitable for mobile devices with limited computational resource. PMID:25148667

Li, Zhengguo; Zheng, Jinghong; Zhu, Zijian; Wu, Shiqian

2014-10-01

284

Intense fusion neutron sources  

NASA Astrophysics Data System (ADS)

The review describes physical principles underlying efficient production of free neutrons, up-to-date possibilities and prospects of creating fission and fusion neutron sources with intensities of 1015-1021 neutrons/s, and schemes of production and application of neutrons in fusion-fission hybrid systems. The physical processes and parameters of high-temperature plasmas are considered at which optimal conditions for producing the largest number of fusion neutrons in systems with magnetic and inertial plasma confinement are achieved. The proposed plasma methods for neutron production are compared with other methods based on fusion reactions in nonplasma media, fission reactions, spallation, and muon catalysis. At present, intense neutron fluxes are mainly used in nanotechnology, biotechnology, material science, and military and fundamental research. In the near future (10-20 years), it will be possible to apply high-power neutron sources in fusion-fission hybrid systems for producing hydrogen, electric power, and technological heat, as well as for manufacturing synthetic nuclear fuel and closing the nuclear fuel cycle. Neutron sources with intensities approaching 1020 neutrons/s may radically change the structure of power industry and considerably influence the fundamental and applied science and innovation technologies. Along with utilizing the energy produced in fusion reactions, the achievement of such high neutron intensities may stimulate wide application of subcritical fast nuclear reactors controlled by neutron sources. Superpower neutron sources will allow one to solve many problems of neutron diagnostics, monitor nano-and biological objects, and carry out radiation testing and modification of volumetric properties of materials at the industrial level. Such sources will considerably (up to 100 times) improve the accuracy of neutron physics experiments and will provide a better understanding of the structure of matter, including that of the neutron itself.

Kuteev, B. V.; Goncharov, P. R.; Sergeev, V. Yu.; Khripunov, V. I.

2010-04-01

285

Cold fusion, Alchemist's dream  

SciTech Connect

In this report the following topics relating to cold fusion are discussed: muon catalysed cold fusion; piezonuclear fusion; sundry explanations pertaining to cold fusion; cosmic ray muon catalysed cold fusion; vibrational mechanisms in excited states of D{sub 2} molecules; barrier penetration probabilities within the hydrogenated metal lattice/piezonuclear fusion; branching ratios of D{sub 2} fusion at low energies; fusion of deuterons into {sup 4}He; secondary D+T fusion within the hydrogenated metal lattice; {sup 3}He to {sup 4}He ratio within the metal lattice; shock induced fusion; and anomalously high isotopic ratios of {sup 3}He/{sup 4}He.

Clayton, E.D.

1989-09-01

286

Hydrogen inventories in nuclear fusion devices  

Microsoft Academic Search

Hydrogen retention in tokamaks is due to implantation into plasma-facing materials and trapping in deposited layers. In the limiter tokamak TEXTOR-94 hydrogen-rich deposited layers with thicknesses up to 1 mm are observed on recessed parts of the limiters, areas perpendicular to the magnetic field in the scrape-off layer (SOL), neutralizer plates of the pumped limiter and inside the pumping ducts.

M. Mayer; V. Philipps; P. Wienhold; H. G Esser; J von Seggern; M. Rubel

2001-01-01

287

Cold fusion: muon-catalysed fusion  

Microsoft Academic Search

The authors put into perspective and further develop their recent work in muon catalysed fusion, with the objective of identifying the key physical processes in the t(d,n) alpha fusion cycle relevant to energy related applications. They begin by discussing the fusion cycle and point out the importance of direct nuclear reactions in the catalysed fusion processes. This is followed by

H. E. Rafelski; D. Harley; G. R. Shin; J. Rafelski

1991-01-01

288

Vertical Interconnect for Organic Electronic Devices.  

National Technical Information Service (NTIS)

A device includes a plurality of organic electronic devices disposed on a substrate, wherein each of the organic electronic devices comprises a first electrode and a second electrode. Furthermore, the device includes an organic layer disposed between the ...

A. R. Duggal, C. M. A. Heller, D. F. Foust, J. Liu, T. J. Faircloth

2004-01-01

289

Hyperspectral and LiDAR Data Fusion: Outcome of the 2013 GRSS Data Fusion Contest  

E-print Network

Hyperspectral and LiDAR Data Fusion: Outcome of the 2013 GRSS Data Fusion Contest Christian Debes Detection And Ranging (LiDAR) data. The data sets distributed to the participants during the Contest investi- gated different approaches for the fusion of hyperspectral and LiDAR data, including a combined

Du, Jenny (Qian)

290

Electrochromic device  

DOEpatents

An electrochromic device includes a first substrate spaced from a second substrate. A first conductive member is formed over at least a portion of the first substrate. A first electrochromic material is formed over at least a portion of the first conductive member. The first electrochromic material includes an organic material. A second conductive member is formed over at least a portion of the second substrate. A second electrochromic material is formed over at least a portion of the second conductive member. The second electrochromic material includes an inorganic material. An ionic liquid is positioned between the first electrochromic material and the second electrochromic material.

Schwendemanm, Irina G. (Wexford, PA); Polcyn, Adam D. (Pittsburgh, PA); Finley, James J. (Pittsburgh, PA); Boykin, Cheri M. (Kingsport, TN); Knowles, Julianna M. (Apollo, PA)

2011-03-15

291

Fusion Nuclear Science Facility (FNSF) before Upgrade to Component Test Facility (CTF)  

NASA Astrophysics Data System (ADS)

The Fusion Nuclear Science Facility (FNSF) aims to address Fusion Energy Sciences research needs in ``Materials in Fusion Environment''. Such an environment can be provided initially in an ST device with the JET-level plasma conditions (Q=0.86 in Hot-Ion H-Mode) providing 0.25 MW/m**2 in outboard fusion neutron wall loading, and subsequently at twice the JET conditions (Q=1.7) to provide 1 MW/m**2. Conservative high-q and moderate-beta plasma conditions are calculated for the FNSF to minimize plasma-induced disruptions and allow the delivery of the required neutron fluence of 1 MW-yr/m**2 and duty factor of 10%. Fully modular designs for all the chamber components, including the single-turn toroidal field coil center-post, allow component installation and replacement via remote handling, which is required for the research operations of FNSF. Since the device support structures are hidden behind the chamber components, the FNSF provides a ready upgrade path to the Component Test Facility (CTF), which will require more stringent fusion nuclear and operational capabilities. Details of the physics, engineering, and research prerequisites assessments for the FNSF will be reported.

Peng, Y. K. M.

2010-11-01

292

Dynamic stabilization versus fusion for treatment of degenerative spine conditions  

PubMed Central

Study design:?Comparative effectiveness review. Study rationale:?Spinal fusion is believed to accelerate the degeneration of the vertebral segment above or below the fusion site, a condition called adjacent segment disease (ASD). The premise of dynamic stabilization is that motion preservation allows for less loading on the discs and facet joints at the adjacent, non-fused segments. In theory, this should decrease the rate of ASD. However, clinical evidence of this theoretical decrease in ASD is still lacking. We performed a systematic review to evaluate the evidence in the literature comparing dynamic stabilization with fusion. Clinical question:?In patients 18 years or older with degenerative disease of the cervical or lumbar spine, does dynamic stabilization lead to better outcomes and fewer complications, including ASD, than fusion in the short-term and the long-term? Methods:?A systematic search and review of the literature was undertaken to identify studies published through March 7, 2011. PubMed, Cochrane, and National Guideline Clearinghouse Databases as well as bibliographies of key articles were searched. Two individuals independently reviewed articles based on inclusion and exclusion criteria which were set a priori. Each article was evaluated using a predefined quality-rating scheme. Results:?No significant differences were identified between fusion and dynamic stabilization with regard to VAS, ODI, complications, and reoperations. There are no long-term data available to show whether dynamic stabilization decreases the rate of ASD. Conclusions:?There are no clinical data from comparative studies supporting the use of dynamic stabilization devices over standard fusion techniques. PMID:23526895

Chou, Dean; Lau, Darryl; Skelly, Andrea; Ecker, Erika

2011-01-01

293

Purdue Contribution of Fusion Simulation Program  

SciTech Connect

The overall science goal of the FSP is to develop predictive simulation capability for magnetically confined fusion plasmas at an unprecedented level of integration and fidelity. This will directly support and enable effective U.S. participation in research related to the International Thermonuclear Experimental Reactor (ITER) and the overall mission of delivering practical fusion energy. The FSP will address a rich set of scientific issues together with experimental programs, producing validated integrated physics results. This is very well aligned with the mission of the ITER Organization to coordinate with its members the integrated modeling and control of fusion plasmas, including benchmarking and validation activities. [1]. Initial FSP research will focus on two critical areas: 1) the plasma edge and 2) whole device modeling including disruption avoidance. The first of these problems involves the narrow plasma boundary layer and its complex interactions with the plasma core and the surrounding material wall. The second requires development of a computationally tractable, but comprehensive model that describes all equilibrium and dynamic processes at a sufficient level of detail to provide useful prediction of the temporal evolution of fusion plasma experiments. The initial driver for the whole device model (WDM) will be prediction and avoidance of discharge-terminating disruptions, especially at high performance, which are a critical impediment to successful operation of machines like ITER. If disruptions prove unable to be avoided, their associated dynamics and effects will be addressed in the next phase of the FSP. The FSP plan targets the needed modeling capabilities by developing Integrated Science Applications (ISAs) specific to their needs. The Pedestal-Boundary model will include boundary magnetic topology, cross-field transport of multi-species plasmas, parallel plasma transport, neutral transport, atomic physics and interactions with the plasma wall. It will address the origins and structure of the plasma electric field, rotation, the L-H transition, and the wide variety of pedestal relaxation mechanisms. The Whole Device Model will predict the entire discharge evolution given external actuators (i.e., magnets, power supplies, heating, current drive and fueling systems) and control strategies. Based on components operating over a range of physics fidelity, the WDM will model the plasma equilibrium, plasma sources, profile evolution, linear stability and nonlinear evolution toward a disruption (but not the full disruption dynamics). The plan assumes that, as the FSP matures and demonstrates success, the program will evolve and grow, enabling additional science problems to be addressed. The next set of integration opportunities could include: 1) Simulation of disruption dynamics and their effects; 2) Prediction of core profile including 3D effects, mesoscale dynamics and integration with the edge plasma; 3) Computation of non-thermal particle distributions, self-consistent with fusion, radio frequency (RF) and neutral beam injection (NBI) sources, magnetohydrodynamics (MHD) and short-wavelength turbulence.

Jeffrey Brooks

2011-09-30

294

Measuring D(d,p)T fusion reactant energy spectra with Doppler shifted fusion products  

SciTech Connect

Deuterium fusion reactant energy spectra have been measured using a diagnostic that records the Doppler shift imparted to charged particle fusion products of the D(d,p)T reaction by the center-of-mass velocity of the deuterium reactants. This diagnostic, known as the fusion ion Doppler shift diagnostic (FIDO) measures fast deuterium energy spectra in the inertial electrostatic confinement (IEC) experiment at the University of Wisconsin-Madison {l_brace}Santarius et al. [Fusion Sci. Technol. 47, 1238 (2005)]{r_brace}, a device to confine high energy light ions in a spherically symmetric, electrostatic potential well. This article details the first measurements of the fusion reactant energy spectra in an IEC device as well as the design and principles of operation of the FIDO diagnostic. Scaling of reactant energy spectra with a variety of experimental parameters have been explored.

Boris, D. R. [Naval Research Laboratory, 4555 Overlook Avenue, South West, Washington, DC 20375 (United States); Kulcinski, G. L.; Santarius, J. F.; Donovan, D. C. [Fusion Technology Institute, University of Wisconsin-Madison, 1500 Engineering Drive, Madison, Wisconsin 53706 (United States); Piefer, G. R. [Phoenix Nuclear Labs, 8123 Forsythia Street, Suite 140, Middleton, Wisconsin 53562 (United States)

2010-06-15

295

Nuclear Fusion  

NSDL National Science Digital Library

This simple and engaging astronomy activity explains nuclear fusion and how radiation is generated by stars, using marshmallows as a model. Learners will explore what cosmic radiation is and where it comes from, and how the elements in the universe are generated. The PDF contains step-by-step instructions, photos, presentation tips, links to background information, and a printable Periodic Table of the Elements.

Pacific, Astronomical S.

2008-01-01

296

Discharge Characteristics of Anode Size in an Inertial Electrostatic Confinement Fusion  

Microsoft Academic Search

An IECF (Inertial Electrostatic Confinement Fusion) device is a very simple and safe neutron source using the glow discharge in deuterium gas and deuterium - deuterium fusion. The discharge characteristic is studied experimentally. The gas pressure - applied voltage characteristics are examined altering the device's anode size. The gas pressure range that the device is able to work is differed

H. Osawa; S. Yoshimura; Takehiro TABATA; M. Ohnishi

2006-01-01

297

Bubble fusion: Preliminary estimates  

SciTech Connect

The collapse of a gas-filled bubble in disequilibrium (i.e., internal pressure {much_lt} external pressure) can occur with a significant focusing of energy onto the entrapped gas in the form of pressure-volume work and/or acoustical shocks; the resulting heating can be sufficient to cause ionization and the emission of atomic radiations. The suggestion that extreme conditions necessary for thermonuclear fusion to occur may be possible has been examined parametrically in terms of the ratio of initial bubble pressure relative to that required for equilibrium. In this sense, the disequilibrium bubble is viewed as a three-dimensional ``sling shot`` that is ``loaded`` to an extent allowed by the maximum level of disequilibrium that can stably be achieved. Values of this disequilibrium ratio in the range 10{sup {minus}5}--10{sup {minus}6} are predicted by an idealized bubble-dynamics model as necessary to achieve conditions where nuclear fusion of deuterium-tritium might be observed. Harmonic and aharmonic pressurizations/decompressions are examined as means to achieve the required levels of disequilibrium required to create fusion conditions. A number of phenomena not included in the analysis reported herein could enhance or reduce the small levels of nuclear fusions predicted.

Krakowski, R.A.

1995-02-01

298

Experiences with a Barista Robot, FusionBot  

NASA Astrophysics Data System (ADS)

In this paper, we describe the implemented service robot, called FusionBot. The goal of this research is to explore and demonstrate the utility of an interactive service robot in a smart home environment, thereby improving the quality of human life. The robot has four main features: 1) speech recognition, 2) object recognition, 3) object grabbing and fetching and 4) communication with a smart coffee machine. Its software architecture employs a multimodal dialogue system that integrates different components, including spoken dialog system, vision understanding, navigation and smart device gateway. In the experiments conducted during the TechFest 2008 event, the FusionBot successfully demonstrated that it could autonomously serve coffee to visitors on their request. Preliminary survey results indicate that the robot has potential to not only aid in the general robotics but also contribute towards the long term goal of intelligent service robotics in smart home environment.

Limbu, Dilip Kumar; Tan, Yeow Kee; Wong, Chern Yuen; Jiang, Ridong; Wu, Hengxin; Li, Liyuan; Kah, Eng Hoe; Yu, Xinguo; Li, Dong; Li, Haizhou

299

Laser fusion monthly -- August 1980  

SciTech Connect

This report documents the monthly progress for the laser fusion research at Lawrence Livermore National Laboratory. First it gives facilities report for both the Shiva and Argus projects. Topics discussed include; laser system for the Nova Project; the fusion experiments analysis facility; optical/x-ray streak camera; Shiva Dante System temporal response; 2{omega}{sub 0} experiment; and planning for an ICF engineering test facility.

Ahlstrom, H.G. [ed.

1980-08-01

300

Basics of Fusion-Fissison Research Facility (FFRF) as a Fusion Neutron Source  

SciTech Connect

FFRF, standing for the Fusion-Fission Research Facility represents an option for the next step project of ASIPP (Hefei, China) aiming to a first fusion-fission multifunctional device [1]. FFRF strongly relies on new, Lithium Wall Fusion plasma regimes, the development of which has already started in the US and China. With R/a=4/1m/m, Ipl=5 MA, Btor=4-6 T, PDT=50- 100 MW, Pfission=80-4000MW, 1 m thick blanket, FFRF has a unique fusion mission of a stationary fusion neutron source. Its pioneering mission of merging fusion and fission consists in accumulation of design, experimental, and operational data for future hybrid applications.

Leonid E. Zakharov

2011-06-03

301

Cold fusion prospects  

Microsoft Academic Search

The requirements for cold fusion may include, but are not limited to the following: a nuclear mass-energy resonance with an excitation level in the compound nucleus or in two output nuclei; very high density; a large neutron capture cross-section isotope and a neutron-rich isotope; overlapping de Broglie interaction wavelengths; nuclear spin and polarizability compatibility; and\\/or catalytic action by a passing

1989-01-01

302

Neutron sources and spectra from cold fusion  

Microsoft Academic Search

Deterministic methods are used to calculate the neutron and photon sources and spectra that would develop if fusion reactions were occurring in cold fusion experimental devices. The results from the calculations give the neutron and gamma spectra resulting from a 2.45-MeV and a 14.1 MeV neutron source. The neutron source strength from certain (gamma,n) and (alpha,n) reactions are also determined.

T. A. Parish; R. T. Perry; W. B. Wilson

1990-01-01

303

Fusion Simulation Project Workshop Report  

NASA Astrophysics Data System (ADS)

The mission of the Fusion Simulation Project is to develop a predictive capability for the integrated modeling of magnetically confined plasmas. This FSP report adds to the previous activities that defined an approach to integrated modeling in magnetic fusion. These previous activities included a Fusion Energy Sciences Advisory Committee panel that was charged to study integrated simulation in 2002. The report of that panel [Journal of Fusion Energy 20, 135 (2001)] recommended the prompt initiation of a Fusion Simulation Project. In 2003, the Office of Fusion Energy Sciences formed a steering committee that developed a project vision, roadmap, and governance concepts [Journal of Fusion Energy 23, 1 (2004)]. The current FSP planning effort involved 46 physicists, applied mathematicians and computer scientists, from 21 institutions, formed into four panels and a coordinating committee. These panels were constituted to consider: Status of Physics Components, Required Computational and Applied Mathematics Tools, Integration and Management of Code Components, and Project Structure and Management. The ideas, reported here, are the products of these panels, working together over several months and culminating in a 3-day workshop in May 2007.

Kritz, Arnold; Keyes, David

2009-03-01

304

Poxvirus entry and membrane fusion  

SciTech Connect

The study of poxvirus entry and membrane fusion has been invigorated by new biochemical and microscopic findings that lead to the following conclusions: (1) the surface of the mature virion (MV), whether isolated from an infected cell or by disruption of the membrane wrapper of an extracellular virion, is comprised of a single lipid membrane embedded with non-glycosylated viral proteins; (2) the MV membrane fuses with the cell membrane, allowing the core to enter the cytoplasm and initiate gene expression; (3) fusion is mediated by a newly recognized group of viral protein components of the MV membrane, which are conserved in all members of the poxvirus family; (4) the latter MV entry/fusion proteins are required for cell to cell spread necessitating the disruption of the membrane wrapper of extracellular virions prior to fusion; and furthermore (5) the same group of MV entry/fusion proteins are required for virus-induced cell-cell fusion. Future research priorities include delineation of the roles of individual entry/fusion proteins and identification of cell receptors.

Moss, Bernard [Laboratory of Viral Diseases, National Institute of Allergy and Infectious Diseases, National Institutes of Health, Bethesda, MD 20892-0445 (United States)]. E-mail: bmoss@nih.gov

2006-01-05

305

Numerical Study on Glow Discharge of IEC Fusion  

SciTech Connect

An inertial electrostatic confinement (IEC) fusion device is possibly used for the neutron source that has the ability to produce the neutrons of 10{sup 5}-10{sup 8}/s by the glow discharge. It works more efficiently at the condition of the high voltage and the low pressure. It, however, is difficult to keep the continuous operation at the low-pressure because the glow discharge is apt to be unstable. We have made the three-dimensional Monte Carlo PIC code including atomic processes to investigate the glow discharge. The study reveals the spatial position where the ionization occurs and numerically reproduces the discharge called 'star mode'.

Osawa, Hodaka; Tabata, Takehiro; Ohnishi, Masami [Kansai University (Japan)

2005-05-15

306

Electrospray device  

NASA Technical Reports Server (NTRS)

An electrospray device includes an electrospray emitter adapted to receive electrospray fluid; an extractor plate spaced from the electrospray emitter and having at least one aperture; and a power supply for applying a first voltage between the extractor plate and emitter for generating at least one Taylor cone emission through the aperture to create an electrospray plume from the electrospray fluid, the extractor plate as well as accelerator and shaping plates may include a porous, conductive medium for transporting and storing excess, accumulated electrospray fluid away from the aperture.

Demmons, Nathaniel (Inventor); Martin, Roy (Inventor); Hruby, Vladimir (Inventor); Roy, Thomas (Inventor); Spence, Douglas (Inventor); Ehrbar, Eric (Inventor); Zwahlen, Jurg (Inventor)

2011-01-01

307

Current Status of IEC (Inertial Electrostatic Confinement) Fusion Neutron\\/Proton Source Study  

Microsoft Academic Search

A compact fusion neutron\\/proton source, i.e., IEC (Inertial Electrostatic Confinement) fusion device is introduced with its principle, function, application and research history. 1. What is IEC? An IECF (Inertial-Electrostatic Confinement fusion) device is an extremely compact, and simple configuration device as is shown in Fig. 1, running by electrical discharge on D-D\\/D- T\\/D-3He fuel gases. It basically consists of a

Kiyoshi Yoshikawa; Ken Takiyama; Yasushi Yamamoto; Kai Masuda; Hisayuki Toku; Takahiro Koyama; Kenji Taruya; Hirofumi Hashimoto; Masami Ohnishi; Hiroshi Horiike; Nobuyuki Inoue

308

Articulating feedstock delivery device  

DOEpatents

A fully articulable feedstock delivery device that is designed to operate at pressure and temperature extremes. The device incorporates an articulating ball assembly which allows for more accurate delivery of the feedstock to a target location. The device is suitable for a variety of applications including, but not limited to, delivery of feedstock to a high-pressure reaction chamber or process zone.

Jordan, Kevin

2013-11-05

309

MIT Plasma Science and Fusion Center Fusion Technology & Engineering Division  

E-print Network

MIT Plasma Science and Fusion Center Fusion Technology & Engineering Division Fusion Magnets Peer Technology & Engineering Division Fusion Magnets Peer Review, MIT Plasma Science and Fusion Center; April 10 Science and Fusion Center Fusion Technology & Engineering Division Fusion Magnets Peer Review, MIT Plasma

310

The Future of Fusion Jiangang Li (j_li@ipp.ac.cn)  

E-print Network

things more simple or more complicated It is time from the Era of Fusion Science to Fusion Energy #12 operability of a fusion energy facility, including plasma control, reliability of components, availability

311

78 FR 11612 - Medical Devices; Pediatric Uses of Devices; Requirement for Submission of Information on...  

Federal Register 2010, 2011, 2012, 2013

...FDA-2009-N-0458] RIN 0910-AG29 Medical Devices; Pediatric Uses of Devices...the regulations on premarket approval of medical devices to include requirements relating...Act requires persons who submit certain medical device applications to include, if...

2013-02-19

312

data fusion 15 June 2012  

E-print Network

real world data fusion Fred Daum 15 June 2012 data fusion Copyright © 2012 Raytheon Company. All fusion fusion of measurements performance fusion of tracks interesting parameter 3 #12;real world multi-sensor data fusion fusion of tracks performance fusion of measurements interesting parameter 4 #12;real world

Dobigeon, Nicolas

313

and INTERNATIONAL ATOMIC ENERGY AGENCYIOP PUBLISHING NUCLEAR FUSION Nucl. Fusion 48 (2008) 024016 (13pp) doi:10.1088/0029-5515/48/2/024016  

E-print Network

and INTERNATIONAL ATOMIC ENERGY AGENCYIOP PUBLISHING NUCLEAR FUSION Nucl. Fusion 48 (2008) 024016 devices Milan Rajkovi´c1 , Milos Skori´c2 , Knut Sølna3 and Ghassan Antar4 1 Institute of Nuclear Sciences Vinca, Belgrade, Serbia 2 National Institute for Fusion Science, 322-6 Oroshi-cho, Toki 509-5292, Gifu

Solna, Knut

314

INSTITUTE OF PHYSICS PUBLISHING PLASMA PHYSICS AND CONTROLLED FUSION Plasma Phys. Control. Fusion 46 (2004) 121 PII: S0741-3335(04)82842-2  

E-print Network

INSTITUTE OF PHYSICS PUBLISHING PLASMA PHYSICS AND CONTROLLED FUSION Plasma Phys. Control. Fusion.1088/0741-3335/46/1/. . . Abstract Hydrogenic fast-ion populations are common in toroidal magnetic fusion AQ1 devices, especially compared with the signals from the injected neutrals, the warm (halo) neutrals and the cold edge neutrals

Heidbrink, William W.

315

Multisensor Images Fusion Based on Feature-Level  

E-print Network

Until now, of highest relevance for remote sensing data processing and analysis have been techniques for pixel level image fusion. So, This paper attempts to undertake the study of Feature-Level based image fusion. For this purpose, feature based fusion techniques, which are usually based on empirical or heuristic rules, are employed. Hence, in this paper we consider feature extraction (FE) for fusion. It aims at finding a transformation of the original space that would produce such new features, which preserve or improve as much as possible. This study introduces three different types of Image fusion techniques including Principal Component Analysis based Feature Fusion (PCA), Segment Fusion (SF) and Edge fusion (EF). This paper also devotes to concentrate on the analytical techniques for evaluating the quality of image fusion (F) by using various methods including (SD), (En), (CC), (SNR), (NRMSE) and (DI) to estimate the quality and degree of information improvement of a fused image quantitatively.

Al-Wassai, Firouz Abdullah; Al-Zaky, Ali A

2011-01-01

316

Alternate Applications of Fusion - Production of Radioisotopes  

SciTech Connect

A major effort to find near-term, non-electric applications of fusion energy has shown that the production of radioisotopes is attractive. The use of the D{sup 3}He fusion reaction to produce Positron Emission Tomography (PET) isotopes is described. An Inertial Electrostatic Confinement (IEC) device is particularly well suited to produce low levels of high-energy (14.7 MeV) protons, which in turn, can produce short-lived PET isotopes. The IEC device at University of Wisconsin has been modified to investigate the potential of this process to be commercially attractive.

Kulcinski, G.L.; Weidner, J.; Cipiti, B.; Ashley, R.P.; Santarius, J.F.; Murali, S.K.; Piefer, G.; Radel, R. [University of Wisconsin-Madison (United States)

2003-09-15

317

Fusion breeder: its potential role and prospects  

SciTech Connect

The fusion breeder is a concept that utilizes 14 MeV neutrons from D + T ..-->.. n(14.1 MeV) + ..cap alpha..(3.5 MeV) fusion reactions to produce more fuel than the tritium (T) needed to sustain the fusion process. This excess fuel production capacity is used to produce fissile material (Pu-239 or U-233) for subsequent use in fission reactors. We are concentrating on a class of blankets we call fission suppressed. The blanket is the region surrounding the fusion plasma in which fusion neutrons interact to produce fuel and heat. The fission-suppressed blanket uses non-fission reactions (mainly (n,2n) or (n,n't)) to generate excess neutrons for the production of net fuel. This is in contrast to the fast fission class of blankets which use (n,fiss) reactions to generate excess neutrons. Fusion reactors with fast fission blankets are commony known as fusion-fission hybrids because they combine fusion and fission in the same device.

Lee, J.D.

1981-01-01

318

Spherical Tokamak Plasma Science and Fusion Energy Component Testing  

SciTech Connect

Recent progress(1) in plasma science of the Spherical Tokamak (or Spherical Torus, ST)(2) has indicated relatively robust plasma conditions in a broad number of topical area including strong shaping, stability limits, energy confinement, self-driven current, and sustainment. This progress has enabled an extensive update of the plasma science and fusion engineering conditions of a Component Test Facility (CTF)(3), which is potentially a necessary step in the development of practical fusion energy. The chamber systems testing conditions in a CTF are characterized by high fusion neutron fluxes n > 4.4 1013 n/s/cm2, over sizescale > 105 cm2 and depth-scale > 50 cm, delivering > 3 accumulated displacement per atom (dpa) per year(4). Such chamber conditions are calculated to be achievable in a CTF with R0 = 1.2 m, A = 1.5, elongation ~ 3, Ip ~ 9 MA, BT ~ 2.5 T, producing a driven fusion burn using 36 MW of combined neutral beam and RF power. The ST CTF will test the life time of single-turn, copper alloy center leg for the toroidal field coil without an induction solenoid and neutron shielding, and require physics data on solenoid-free plasma current initiation, ramp-up, and sustainment to multiple MA level. A new systems code that combines the key required plasma and engineering science conditions of CTF has been prepared and utilized as part of this study. The results show high potential for a family of relatively low cost CTF devices to suit a range of fusion engineering science test missions.

Peng, Yueng Kay Martin [ORNL

2005-01-01

319

Physics of plasma-wall interactions in controlled fusion  

Microsoft Academic Search

In the areas of plasma physics, atomic physics, surface physics, bulk material properties and fusion experiments and theory, the following topics are presented: the plasma sheath; plasma flow in the sheath and presheath of a scrape-off layer; probes for plasma edge diagnostics in magnetic confinement fusion devices; atomic and molecular collisions in the plasma boundary; physical sputtering of solids at

D. E. Post; R. Behrisch

1984-01-01

320

Condensed matter nuclear science (cold fusion): an update  

Microsoft Academic Search

Seventeen years after the announcement by Professors Stanley Pons and Martin Fleischmann of the discovery of cold fusion in March 1989, the scientific community does not acknowledge this field as a genuine scientific research theme. However, the scientific demonstration of cold fusion was made long ago by showing the evidence of excess heat production in electrolytic cells and other devices.

Jean-Paul Biberian

2007-01-01

321

A Coherent Laser Radar (CLR) Device for Remote Metrology, Insspection, and Motion Detection of Plasma Facing Components (PFCs)  

Microsoft Academic Search

A frequency modulated CLR device, designed for remote metrology and inspection of PFCs in fusion devices, is described. The device, developed for ITER application, would be useful for studying plasma interaction on PFCs in any fusion experiment. The device designed for ITER measures ranges up to 22 m with better than 0.1mm accuracy. An array of range data, obtained by

M. M. Menon; R. E. Barry; A. Slotwinski; P. T. Spampinato

1998-01-01

322

Fusion Plasmas Martin Greenwald  

E-print Network

of controlled fusion energy into a practical reality (1-3). In fusion reactions, nuclei of light elements join to form heavier elements releasing enormous quantities of energy. Nuclear fusion powers the sun and other of protons and neutrons. The advantages of fusion energy seem clear enough; it offers the prospect

Greenwald, Martin

323

Two-Stream Stability of the Virtual Cathode in an Inertial Electrostatic Confinement Device  

Microsoft Academic Search

The small size and high mass power density of inertial electrostatic confinement (IEC)-based fusion devices make them well-suited to both fusion power generation and other fusion-based applications. However, due to their low central ion density, IEC devices require a density enhancement scheme to achieve useful fusion rates. One method of enhancing ion density is the Periodically Oscillating Plasma Sphere (POPS),

S. Stange; R. A. Nebel

2004-01-01

324

Human Sensing Fusion Project for Safety and Health Society  

NASA Astrophysics Data System (ADS)

This paper introduces objectives and status of “Human sensing fusion project” in the Exploratory Research for Advanced Technology (ERATO) scheme produced by Japan Science and Technology Agency (JST). This project was started in December 2007 and the laboratory with 11 members opened on April 2008. The aim of this project is to realize a human activity-monitoring device with many kinds of sensors in ultimate small size so that the device can be pasted or patched to the human body, and to establish the algorism for understanding human condition including both physical and mental conditions from obtained data. This system can be used towards the prevention of the danger of accidents and the maintenance of health. The actual research has just begun and preparations for project are well under way.

Maenaka, Kazusuke

325

Signaling Mechanisms in Mammalian Myoblast Fusion  

NSDL National Science Digital Library

Skeletal muscles are formed by the fusion of multiple myoblasts during development. Myoblast fusion is also essential for the growth and repair of injured myofibers. Recent investigations have shown that the process of myoblast fusion involves the activation of several cell signaling pathways, including those mediated by nuclear factor κB, mitogen-activated protein kinases, Wnt, calcineurin–nuclear factor of activated T cells c2, transforming growth factor–β–Smad4, and the Rho guanosine triphosphatases. In this Review, which contains 2 figures and 84 references, we summarize the mechanisms by which the activation of these signaling pathways stimulates myoblast fusion.

Ashok Kumar (University of Louisville;School of Medicine REV); Sajedah M. Hindi (University of Louisville;School of Medicine REV); Marjan M. Tajrishi (University of Louisville;School of Medicine REV)

2013-04-23

326

Portable data collection device  

DOEpatents

The present invention provides a portable data collection device that has a variety of sensors that are interchangeable with a variety of input ports in the device. The various sensors include a data identification feature that provides information to the device regarding the type of physical data produced by each sensor and therefore the type of sensor itself. The data identification feature enables the device to locate the input port where the sensor is connected and self adjust when a sensor is removed or replaced. The device is able to collect physical data, whether or not a function of a time. 7 figs.

French, P.D.

1996-06-11

327

Portable data collection device  

DOEpatents

The present invention provides a portable data collection device that has a variety of sensors that are interchangeable with a variety of input ports in the device. The various sensors include a data identification feature that provides information to the device regarding the type of physical data produced by each sensor and therefore the type of sensor itself. The data identification feature enables the device to locate the input port where the sensor is connected and self adjust when a sensor is removed or replaced. The device is able to collect physical data, whether or not a function of a time.

French, Patrick D. (Aurora, CO)

1996-01-01

328

Active cleaning technique device  

NASA Technical Reports Server (NTRS)

The objective of this program was to develop a laboratory demonstration model of an active cleaning technique (ACT) device. The principle of this device is based primarily on the technique for removing contaminants from optical surfaces. This active cleaning technique involves exposing contaminated surfaces to a plasma containing atomic oxygen or combinations of other reactive gases. The ACT device laboratory demonstration model incorporates, in addition to plasma cleaning, the means to operate the device as an ion source for sputtering experiments. The overall ACT device includes a plasma generation tube, an ion accelerator, a gas supply system, a RF power supply and a high voltage dc power supply.

Shannon, R. L.; Gillette, R. B.

1973-01-01

329

Electron cyclotron wave sources and applications for fusion  

NASA Astrophysics Data System (ADS)

Advances in magnetic fusion research have come as often from the use of new technologies as from the invention of ideas and discovery of phenomena that are then applied to new experiments. The technologies needed for plasma production, heating, confinement, and control have largely been developed and are a major factor in the success of our current experiments. These include high vacuum techniques, normal and superconducting magnets, particle beams, pellet fueling devices, and rf sources in the ion cylotron and lower hybrid range of frequencies. One area where development is especially required, and where the potential impact on fusion research is large, is that of electron cyclotron wave (ECW) sources in the 100-600 GHz range. This journal issue is devoted to methods for ECW generation and transmission, and to applications including heating, current drive, profile shaping, and instability control. To help focus these articles the requirements(1) for a system to heat the Compact Ignition Tokamak (CIT) were used to define the necessary technology. Somewhat lower frequencies, but similar power, is anticipated(2) for the International Thermonuclear Experimental Reactor (ITER), and for future large devices of that class, should they use ECW sources in them.

Thomassen, K. I.

1990-03-01

330

Gasdynamic Mirror Fusion Propulsion Experiment  

NASA Technical Reports Server (NTRS)

A gasdynamic mirror (GDM) fusion propulsion experiment is currently being constructed at the NASA Marshall Space Flight Center (MSFC) to test the feasibility of this particular type of fusion device. Because of the open magnetic field line configuration of mirror fusion devices, they are particularly well suited for propulsion system applications since they allow for the easy ejection of thrust producing plasma. Currently, the MSFC GDM is constructed in three segments. The vacuum chamber mirror segment, the plasma injector mirror segment, and the main plasma chamber segment. Enough magnets are currently available to construct up to three main plasma chamber segments. The mirror segments are also segmented such that they can be expanded to accommodate new end plugging strategies with out requiring the disassembly of the entire mirror segment. The plasma for the experiment is generated in a microwave cavity located between the main magnets and the mirror magnets. Ion heating is accomplished through ambipolar diffusion. The objective of the experiment is to investigate the stability characteristics of the gasdynamic mirror and to map a region of parameter space within which the plasma can be confined in a stable steady state configuration. The mirror ratio, plasma density, and plasma "b" will be varied over a range of values and measurements subsequently taken to determine the degree of plasma stability.

Emrich, Bill; Rodgers, Stephen L. (Technical Monitor)

2000-01-01

331

Optimization of fusion power density in the two-energy-component tokamak reactor  

Microsoft Academic Search

Optimal plasma conditions are determined for maximizing fusion power density in the two-energy-component (TCT) tokamak, in order to optimize the total neutron flux for a device of given size. The minimum value of fusion power multiplication (Q) required for economic operation as a fissile breeder is discussed. The ideal maximum fusion power density increases monotonically with decreasing electron temperature, but

D. L. Jassby

1975-01-01

332

The Role of Controls in Nuclear Fusion  

Microsoft Academic Search

The need for new sources of energy is expected to become a critical problem within the next few decades. Although controlled fusion is a very challenging technology, a fusion power reactor would offer significant advantages over existing energy sources, including no air pollution or greenhouse gases, no risk of nuclear accident, no generation of material for nuclear weapons, low-level radioactive

Eugenio Schuster; Marco Ariola

2006-01-01

333

Socio-economic Aspects of Fusion  

SciTech Connect

Fusion power systems, if developed and deployed, would have many attractive features including power production not dependant on weather or solar conditions, flexible siting, and minimal carbon dioxide production. In this paper, we quantify the benefit of these features. In addition, fusion deployment scenarios are developed for the last half of this century and these scenarios are analyzed for resource requirements and waste production.

J.A. Schmidt

2004-10-21

334

Working with Fusion in Lesbian Couples.  

ERIC Educational Resources Information Center

The phenomena of fusion within a lesbian relationship is described in a six-phased model. Fusion in relationships is defined as two incomplete people coming together in an attempt to make one more complete whole, the merging of two ego boundaries. The six phases discussed include ecstacy, getting married, the routine, depression/withdrawal,…

Roth, Nicki F.

335

Ch. 37, Inertial Fusion Energy Technology  

Microsoft Academic Search

Nuclear fission, nuclear fusion, and renewable energy (including biofuels) are the only energy sources capable of satisfying the Earth's need for power for the next century and beyond without the negative environmental impacts of fossil fuels. Substantially increasing the use of nuclear fission and renewable energy now could help reduce dependency on fossil fuels, but nuclear fusion has the potential

Moses

2010-01-01

336

The Columbus device  

NASA Astrophysics Data System (ADS)

The Columbus device [1] is proposed as one component of a spectrum of experiments needed to explore the physics of fusion burning plasmas. Columbus has a larger volume than Ignitor by about 50%, lower current densities in the magnet systems and capability to sustain longer plasma pulses. The machine preserves the ability to confine, under macroscopically stable conditions, plasmas with peak pressures exceeding 3 MPa, corresponding to ignition at central plasma densities around 10^21 nuclei/m^3 and to reach this regime by ohmic heating alone. The presence of an ICRH system will expand the capabilities of the device. In our opinion, a spectrum of ``Science First'' devices is the only viable path to an efficient fusion program development and plasma ignition is an important milestone to be achieved before undertaking the construction of a Demo reactor requiring minimization of the external heating power. The Iter design envisages that about one third of its heating power be supplied from the outside in order to maintain its plasma pressure at the desired values. The Columbus program is proposed as a U.S. counterpart to the Ignitor project conducted in Italy and to be complementary to it. The machine costs can be minimized by incorporating the main engineering solutions devised for Ignitor. [1] Coppi,B. and Salvetti,M.,``Highlights of the Columbus Concept'', M.I.T. Report, PTP02/06 (2002).

Salvetti, Matteo

2005-10-01

337

High efficiency photovoltaic device  

DOEpatents

An N-I-P type photovoltaic device includes a multi-layered body of N-doped semiconductor material which has an amorphous, N doped layer in contact with the amorphous body of intrinsic semiconductor material, and a microcrystalline, N doped layer overlying the amorphous, N doped material. A tandem device comprising stacked N-I-P cells may further include a second amorphous, N doped layer interposed between the microcrystalline, N doped layer and a microcrystalline P doped layer. Photovoltaic devices thus configured manifest improved performance, particularly when configured as tandem devices.

Guha, Subhendu (Troy, MI); Yang, Chi C. (Troy, MI); Xu, Xi Xiang (Findlay, OH)

1999-11-02

338

Fabrication of the Toroidal Field Superconducting Coils for the EAST Device  

Microsoft Academic Search

EAST (HT-7U) is a large fusion experimental device being built at IPP, Hefei, China. Its superconducting magnet system consists of sixteen Toroidal Field (TF) coils and fourteen Poloidal Field (PF) coils. The TF coil includes the winding pack with a square cable-in-conduit (CIC) type superconductor in NbTi cooled by a force flow of supercritical helium, the welded case structure, the

Wenge Chen; Yannian Pan; Songtao Wu; Peide Weng; Daming Gao; Jing Wei; Jie Yu; Siyue Chen

2006-01-01

339

Massachusetts Institute of Technology, Plasma Fusion Center, 1984-1985. Report to the President  

NASA Astrophysics Data System (ADS)

During the past year, technical progress has been made in all Plasma Fusion Center (PFC) research programs. The Plasma Fusion Center is recognized as one of the leading university research laboratories in the physics and engineering aspects of magnetic confinement fusion. Its research programs have produced significant results on four fronts: (1) the basic physics of high-temperature plasmas (plasma theory, rf heating, free electron lasers, development of advanced diagnostics and small-scale experiments on the Versator tokamak and Constance mirror devices); (2) major confinement results on the Alcator C tokamak, including pioneering investigations of the stability, heating, and confinement properties of plasmas at high densities, temperatures and magnetic fields; (3) development of an innovative design for axisymmetric tandem mirrors with inboard thermal barriers, with initial operation of the TARA tandem mirror experiment beginning in 1984; and (4) a broad program of fusion technology and engineering development that addresses problems in several critical subsystem areas (e.g., magnet systems, superconducting materials development, environmental and safety studies, advanced millimeter wave source development, and system studies of fusion reactor design, operation, and technology requirements). A review of these programs is given.

1985-07-01

340

Technical Issues on the Control of Plasma-Wall Interactions in Steady-State Magnetic Fusion Devices 3.Innovation Concepts for Plasma-Facing Components 3.2 A New Cooling Concept of Free Surface Flow Balanced with Surface Tension  

NASA Astrophysics Data System (ADS)

A new cooling concept of free surface flow is proposed as an alternative candidate for the first wall of the self-cooling molten-salt Flibe blanket in the helical-type fusion reactor FFHR. Numerical analyses on capillary flow show that a free surface balanced between surface tension and the forces of wall shear stress and gravity is feasible even in helical systems, where a spiral flow is formed and drastically enhances the heat transfer from the coolant channel wall.

Kunugi, Tomoaki; Sagara, Akio

341

Gasdynamic Mirror (GDM) Fusion Propulsion Engine Experiment  

NASA Technical Reports Server (NTRS)

The Gasdynamic Mirror, or GDM, is an example of a magnetic mirror-based fusion propulsion system. Its design is primarily consisting of a long slender solenoid surrounding a vacuum chamber that contains plasma. The bulk of the fusion plasma is confined by magnetic field generated by a series of toroidal-shaped magnets in the center section of the device. the purpose of the GDM Fusion Propulsion Experiment is to confirm the feasibility of the concept and to demonstrate many of the operational characteristics of a full-size plasma can be confined within the desired physical configuration and still reman stable. This image shows an engineer from Propulsion Research Technologies Division at Marshall Space Flight Center inspecting solenoid magnets-A, an integrate part of the Gasdynamic Mirror Fusion Propulsion Engine Experiment.

1999-01-01

342

77 FR 40735 - Unique Device Identification System  

Federal Register 2010, 2011, 2012, 2013

...Regulatory Hearing Before the Food and Drug Administration We...to clarify that the device history record is to include any UDI...already requires the device history record to include...inspection, that the device history record...

2012-07-10

343

Fusion reactor pumped laser  

DOEpatents

A nuclear pumped laser capable of producing long pulses of very high power laser radiation is provided. A toroidal fusion reactor provides energetic neutrons which are slowed down by a moderator. The moderated neutrons are converted to energetic particles capable of pumping a lasing medium. The lasing medium is housed in an annular cell surrounding the reactor. The cell includes an annular reflecting mirror at the bottom and an annular output window at the top. A neutron reflector is disposed around the cell to reflect escaping neutrons back into the cell. The laser radiation from the annular window is focused onto a beam compactor which generates a single coherent output laser beam.

Jassby, Daniel L. (Princeton, NJ)

1988-01-01

344

High Energy Space Propulsion based on Magnetized Target Fusion  

Microsoft Academic Search

Magnetized Target Fusion (MTF) is a new entry into the fusion propulsion arena that promises low-cost development and rapid deployment using existing facilities and technology. Plasma-jet driven MTF has a number of features which make it attractive as a space propulsion system. These features include, low system mass and volume, high Isp and thrust, and efficient fusion drivers leading to

F. Thio

1999-01-01

345

2002 Fusion Summer Study Development Pathway Subgroup (E 4)  

E-print Network

2002 Fusion Summer Study Development Pathway Subgroup (E 4) Final Report July 25, 2002 #12;6. Development Path Scenarios The development path to realize fusion as a practical energy source must include performance, steady-state operation; 4) Development of low-activation materials and fusion technologies

346

Bemerkungen zur "kalten Fusion"  

E-print Network

Steven Jones et al. reported to have observed nuclear fusion at room temperature. They observed this "cold fusion" by electrolyzing heavy water. Later experiments confirmed these observations. These experiments confirmed the generation of strong electric fields within the deuterided metals. These electric fields accelerate the deuterons to keV energies and allow the observed nuclear fusion. Roman Sioda and I suggested a theoretical description of this nuclear fusion. Our "extended micro hot fusion" scenario explains how nuclear fusion can be generated over a long time within deuterided metals. Moreover we predicted the explosion of large pieces of deuterided metals. This article reviews the "cold fusion" work of Steven Jones et al. and discusses the fracto-fusion scenario. I show that the extended micro hot fusion scenario can explain the observed neutron emissions, neutron bursts, and heat bursts.

Rainer W. Kuehne

2006-04-14

347

Bemerkungen zur "kalten Fusion"  

E-print Network

Steven Jones et al. reported to have observed nuclear fusion at room temperature. They observed this "cold fusion" by electrolyzing heavy water. Later experiments confirmed these observations. These experiments confirmed the generation of strong electric fields within the deuterided metals. These electric fields accelerate the deuterons to keV energies and allow the observed nuclear fusion. Roman Sioda and I suggested a theoretical description of this nuclear fusion. Our "extended micro hot fusion" scenario explains how nuclear fusion can be generated over a long time within deuterided metals. Moreover we predicted the explosion of large pieces of deuterided metals. This article reviews the "cold fusion" work of Steven Jones et al. and discusses the fracto-fusion scenario. I show that the extended micro hot fusion scenario can explain the observed neutron emissions, neutron bursts, and heat bursts.

Kuehne, R W

2006-01-01

348

Engineering scaling and quantification of the test requirements for fusion nuclear technology  

Microsoft Academic Search

For integrated testing of fusion nuclear components, it is likely that the test device parameters will not match the device parameters of a full scale fusion reactor because of cost constraints. This will result in changes in the behavior of the test module and limit the ability of the test to resolve key nuclear issues. However, it may be possible

P. Gierszewski; M. Abdou; G. Bell; M. Billone; J. Blanchard; J. Garner; H. Madarame; G. Orient; K. Shin; K. Taghavi

1985-01-01

349

Altered lipid content inhibits autophagic vesicular fusion  

PubMed Central

The autophagic/lysosomal system includes a variety of vesicular compartments that undergo dynamic fusion events. However, the characteristics and factors modulating these interactions remain, for the most part, unknown. To gain insights on the properties that govern lysosomal fusion events, we have established an in vitro fusion assay using different lysosomal/autophagic compartments isolated from mouse liver. We have found that autophagosome/lysosome fusion is a temperature-dependent process (fusion increment of 0.2±0.01%/°C), which requires ATP (1–3 mM), GTP (1–2 mM), Ca2+ (0.2–2 mM), and an acidic lysosomal pH (pH 5.2). Furthermore, changes in membrane lipid composition, induced either in vitro, by treatment with 25 mM methyl-?-cyclodextrin, or in vivo, by subjecting animals to a high-fat-diet challenge (60% kcal in fat) reduce autophagosome/lysosome fusion up to 70% of that observed in untreated fractions or from animals under a normal regular diet. These findings reveal a novel role for lipids in autophagic fusion and provide a mechanism for the reduced macroautophagic rates observed during exposure to a chronic lipid challenge. Changes in the intracellular lipid content (i.e., metabolic disorders) may thus have pronounced effects on the fusion step of macroautophagy and affect the overall activity of this intracellular proteolytic pathway.—Koga, H., Kaushik, S., Cuervo, A. M. Altered lipid content inhibits autophagic vesicular fusion. PMID:20375270

Koga, Hiroshi; Kaushik, Susmita; Cuervo, Ana Maria

2010-01-01

350

Observation of nuclear fusion driven by a pyroelectric crystal  

Microsoft Academic Search

While progress in fusion research continues with magnetic and inertial confinement, alternative approaches-such as Coulomb explosions of deuterium clusters and ultrafast laser-plasma interactions-also provide insight into basic processes and technological applications. However, attempts to produce fusion in a room temperature solid-state setting, including `cold' fusion and `bubble' fusion, have met with deep scepticism. Here we report that gently heating a

B. Naranjo; J. K. Gimzewski; S. Putterman

2005-01-01

351

Review of fusion synfuels  

SciTech Connect

Thermonuclear fusion offers an inexhaustible source of energy for the production of hydrogen from water. Depending on design, electric generation efficiencies of approx. 40 to 60% and hydrogen production efficiencies by high-temperature electrolysis of approx. 50 to 65% are projected for fusion reactors using high-temperatures blankets. Fusion/coal symbiotic systems appear economically promising for the first generation of commercial fusion synfuels plants. Coal production requirements and the environmental effects of large-scale coal usage would be greatly reduced by a fusion/coal system. In the long term, there could be a gradual transition to an inexhaustible energy system based solely on fusion.

Fillo, J.A.

1980-01-01

352

University Fusion Association General Meeting  

E-print Network

, UCSD #12;UFA Activity for 2007 Expect a new FESAC charge to develop a plan for the US fusion program President OFES Program Steve Eckstrand, DOE/OFES NRC/NAS Plasma 2010 Study Update Steven Cowley, UCLA US over the next ten-years prior to ITER operation including identification of possible major new

353

Inertial confinement fusion (ICF) review  

SciTech Connect

During its 1996 winter study JASON reviewed the DOE Inertial Confinement Fusion (ICF) program. This included the National Ignition Facility (NIF) and proposed studies. The result of the review was to comment on the role of the ICF program in support of the DOE Science Based Stockpile Stewardship program.

Hammer, D.; Dyson, F.; Fortson, N.; Novick, B.; Panofsky, W.; Rosenbluth, M.; Treiman, S.; York, H.

1996-03-01

354

EDITORIAL: Safety aspects of fusion power plants  

NASA Astrophysics Data System (ADS)

This special issue of Nuclear Fusion contains 13 informative papers that were initially presented at the 8th IAEA Technical Meeting on Fusion Power Plant Safety held in Vienna, Austria, 10-13 July 2006. Following recommendation from the International Fusion Research Council, the IAEA organizes Technical Meetings on Fusion Safety with the aim to bring together experts to discuss the ongoing work, share new ideas and outline general guidance and recommendations on different issues related to safety and environmental (S&E) aspects of fusion research and power facilities. Previous meetings in this series were held in Vienna, Austria (1980), Ispra, Italy (1983), Culham, UK (1986), Jackson Hole, USA (1989), Toronto, Canada (1993), Naka, Japan (1996) and Cannes, France (2000). The recognized progress in fusion research and technology over the last quarter of a century has boosted the awareness of the potential of fusion to be a practically inexhaustible and clean source of energy. The decision to construct the International Thermonuclear Experimental Reactor (ITER) represents a landmark in the path to fusion power engineering. Ongoing activities to license ITER in France look for an adequate balance between technological and scientific deliverables and complying with safety requirements. Actually, this is the first instance of licensing a representative fusion machine, and it will very likely shape the way in which a more common basis for establishing safety standards and policies for licensing future fusion power plants will be developed. Now that ITER licensing activities are underway, it is becoming clear that the international fusion community should strengthen its efforts in the area of designing the next generations of fusion power plants—demonstrational and commercial. Therefore, the 8th IAEA Technical Meeting on Fusion Safety focused on the safety aspects of power facilities. Some ITER-related safety issues were reported and discussed owing to their potential importance for the fusion power plant research programmes. The objective of this Technical Meeting was to examine in an integrated way all the safety aspects anticipated to be relevant to the first fusion power plant prototype expected to become operational by the middle of the century, leading to the first generation of economically viable fusion power plants with attractive S&E features. After screening by guest editors and consideration by referees, 13 (out of 28) papers were accepted for publication. They are devoted to the following safety topics: power plant safety; fusion specific operational safety approaches; test blanket modules; accident analysis; tritium safety and inventories; decommissioning and waste. The paper `Main safety issues at the transition from ITER to fusion power plants' by W. Gulden et al (EU) highlights the differences between ITER and future fusion power plants with magnetic confinement (off-site dose acceptance criteria, consequences of accidents inside and outside the design basis, occupational radiation exposure, and waste management, including recycling and/or final disposal in repositories) on the basis of the most recent European fusion power plant conceptual study. Ongoing S&E studies within the US inertial fusion energy (IFE) community are focusing on two design concepts. These are the high average power laser (HAPL) programme for development of a dry-wall, laser-driven IFE power plant, and the Z-pinch IFE programme for the production of an economically-attractive power plant using high-yield Z-pinch-driven targets. The main safety issues related to these programmes are reviewed in the paper `Status of IFE safety and environmental activities in the US' by S. Reyes et al (USA). The authors propose future directions of research in the IFE S&E area. In the paper `Recent accomplishments and future directions in the US Fusion Safety & Environmental Program' D. Petti et al (USA) state that the US fusion programme has long recognized that the S&E potential of fusion can be attained by prudent materials selecti

Kolbasov, B. N.

2007-07-01

355

Lithium As Plasma Facing Component for Magnetic Fusion Research  

SciTech Connect

The use of lithium in magnetic fusion confinement experiments started in the 1990's in order to improve tokamak plasma performance as a low-recycling plasma-facing component (PFC). Lithium is the lightest alkali metal and it is highly chemically reactive with relevant ion species in fusion plasmas including hydrogen, deuterium, tritium, carbon, and oxygen. Because of the reactive properties, lithium can provide strong pumping for those ions. It was indeed a spectacular success in TFTR where a very small amount (~ 0.02 gram) of lithium coating of the PFCs resulted in the fusion power output to improve by nearly a factor of two. The plasma confinement also improved by a factor of two. This success was attributed to the reduced recycling of cold gas surrounding the fusion plasma due to highly reactive lithium on the wall. The plasma confinement and performance improvements have since been confirmed in a large number of fusion devices with various magnetic configurations including CDX-U/LTX (US), CPD (Japan), HT-7 (China), EAST (China), FTU (Italy), NSTX (US), T-10, T-11M (Russia), TJ-II (Spain), and RFX (Italy). Additionally, lithium was shown to broaden the plasma pressure profile in NSTX, which is advantageous in achieving high performance H-mode operation for tokamak reactors. It is also noted that even with significant applications (up to 1,000 grams in NSTX) of lithium on PFCs, very little contamination (< 0.1%) of lithium fraction in main fusion plasma core was observed even during high confinement modes. The lithium therefore appears to be a highly desirable material to be used as a plasma PFC material from the magnetic fusion plasma performance and operational point of view. An exciting development in recent years is the growing realization of lithium as a potential solution to solve the exceptionally challenging need to handle the fusion reactor divertor heat flux, which could reach 60 MW/m2 . By placing the liquid lithium (LL) surface in the path of the main divertor heat flux (divertor strike point), the lithium is evaporated from the surface. The evaporated lithium is quickly ionized by the plasma and the ionized lithium ions can provide a strongly radiative layer of plasma ("radiative mantle"), thus could significantly reduce the heat flux to the divertor strike point surfaces, thus protecting the divertor surface. The protective effects of LL have been observed in many experiments and test stands. As a possible reactor divertor candidate, a closed LL divertor system is described. Finally, it is noted that the lithium applications as a PFC can be quite flexible and broad. The lithium application should be quite compatible with various divertor configurations, and it can be also applied to protecting the presently envisioned tungsten based solid PFC surfaces such as the ones for ITER. Lithium based PFCs therefore have the exciting prospect of providing a cost effective flexible means to improve the fusion reactor performance, while providing a practical solution to the highly challenging divertor heat handling issue confronting the steadystate magnetic fusion reactors.

Masayuki Ono

2012-09-10

356

Daydreaming Devices  

E-print Network

Daydreaming Devices is a project on aspects of daydream and the design of convertible furniture within the context of art. This thesis addresses the concepts and the design of two daydreaming devices developed during my ...

Da Ponte, Ana Sofia Lopes

2008-01-01

357

Including users with disabilities  

Microsoft Academic Search

This SIG will begin the information exchange on designing for disabilities for professionals who have not formally considered disabled communities as part of their user\\/subject base before. Until recently, only professionals working in the area of assistive technologies\\/devices focused on design for people with disabilities. However, more applications, software, products and services that have typically been targeted at the general

Lea T. Adams

2000-01-01

358

Fusion Power Associates, 2012 Annual Meeting 1 General Fusion  

E-print Network

Fusion Power Associates, 2012 Annual Meeting 1 General Fusion #12;Fusion Power Associates, 2012 Annual Meeting 2 General Fusion Making affordable fusion power a reality. · Founded in 2002, based to demonstrate the first fusion system capable of "net gain" 3 years after proof · Validated by leading experts

359

Fusion Power Associates, 2011 Annual Meeting 1 General Fusion  

E-print Network

Fusion Power Associates, 2011 Annual Meeting 1 General Fusion #12;Fusion Power Associates, 2011 Annual Meeting 2 General Fusion Making commercially viable fusion power a reality. · Founded in 2002, based in Vancouver, Canada · Plan to demonstrate a fusion system capable of "net gain" within 3 years

360

MIT Plasma Science and Fusion Center Fusion Technology & Engineering Division  

E-print Network

MIT Plasma Science and Fusion Center Fusion Technology & Engineering Division J.H. Schultz M Point Studies #12;MIT Plasma Science and Fusion Center Fusion Technology & Engineering Division A New on assumed p*/E #12;MIT Plasma Science and Fusion Center Fusion Technology & Engineering Division Calibration

361

MIT Plasma Science and Fusion Center Fusion Technology & Engineering Division  

E-print Network

MIT Plasma Science and Fusion Center Fusion Technology & Engineering Division J.H. Schultz, P close #12;MIT Plasma Science and Fusion Center Fusion Technology & Engineering Division Dimensionally No , Yes No #12;MIT Plasma Science and Fusion Center Fusion Technology & Engineering Division Ip

362

Fusion power for space propulsion.  

NASA Technical Reports Server (NTRS)

Principles of operation, interplanetary orbit-to-orbit mission capabilities, technical problems, and environmental safeguards are examined for thermonuclear fusion propulsion systems. Two systems examined include (1) a fusion-electric concept in which kinetic energy of charged particles from the plasma is converted into electric power (for accelerating the propellant in an electrostatic thrustor) by the van de Graaf generator principle and (2) the direct fusion rocket in which energetic plasma lost from the reactor has a suitable amount of added propellant to obtain the optimum exhaust velocity. The deuterium-tritium and the deuterium/helium-3 reactions are considered as suitable candidates, and attention is given to problems of cryogenic refrigeration systems, magnet shielding, and high-energy particle extraction and guidance.

Roth, R.; Rayle, W.; Reinmann, J.

1972-01-01

363

Unconventional Quantum Computing Devices  

E-print Network

This paper investigates a variety of unconventional quantum computation devices, including fermionic quantum computers and computers that exploit nonlinear quantum mechanics. It is shown that unconventional quantum computing devices can in principle compute some quantities more rapidly than `conventional' quantum computers.

Seth Lloyd

2000-03-31

364

Capillary interconnect device  

DOEpatents

An interconnecting device for connecting a plurality of first fluid-bearing conduits to a corresponding plurality of second fluid-bearing conduits thereby providing fluid communication between the first fluid-bearing conduits and the second fluid-bearing conduits. The device includes a manifold and one or two ferrule plates that are held by compressive axial forces.

Renzi, Ronald F

2013-11-19

365

Fusion Energy Sciences Program Mission  

E-print Network

Fusion Energy Sciences Program Mission The Fusion Energy Sciences (FES) program leads the national research effort to advance plasma science, fusion science, and fusion technology--the knowledge base needed for an economically and environmentally attractive fusion energy source. The National Energy Policy states that fusion

366

Nonimaging radiant energy direction device  

DOEpatents

A raidant energy nonimaging light direction device is provided. The device includes an energy transducer and a reflective wall whose contour is particularly determined with respect to the geometrical vector flux of a field associated with the transducer.

Winston, Roland (Chicago, IL)

1980-01-01

367

Electronic Computers and Analog Devices.  

National Technical Information Service (NTIS)

The handbook presents a classification of electronic and analog computers and analog devices, including descriptions, basic technical features and fields of application of domestically-manufactured universal digital computers, digital control devices, dig...

V. I. Grubov, V. S. Kirdan

1971-01-01

368

Towards cognitive image fusion  

Microsoft Academic Search

The increasing availability and deployment of imaging sensors operating in multiple spectral bands has led to a large research effort in image fusion, resulting in a plethora of pixel-level image fusion algorithms. However, the cognitive aspects of multisensor image fusion have not received much attention in the development of these methods. In this study we investigate how humans interpret visual

Alexander Toet; Maarten A. Hogervorst; Stavri G. Nikolov; John J. Lewis; Timothy D. Dixon; David R. Bull; Cedric Nishan Canagarajah

2010-01-01

369

Investigations of image fusion  

Microsoft Academic Search

The objective of image fusion is to combine information from multiple images of the same scene. The result of image fusion is a single image which is more suitable for the purpose of human visual perception or further image processing tasks. In this thesis, a region-based fusion algorithm using the wavelet transform is proposed. The identification of important features in

Zhong Zhang

1999-01-01

370

About sponsorship Fusion power  

E-print Network

project to build a nuclear-fusion reactor came a step closer to reality when politicians agreed it should proving step before a commercial fusion reactor is built. It would demonstrate that power can be generated into those alternatives. ITER Part of the reason why commercial fusion reactors have always been 30 years

371

75 FR 448 - In the Matter of: Certain Authentication Systems, Including Software and Handheld Electronic...  

Federal Register 2010, 2011, 2012, 2013

...Certain Authentication Systems, Including Software and Handheld Electronic Devices; Notice...certain authentication systems, including software and handheld electronic devices, by...of authentication systems, including software and handheld electronic devices,...

2010-01-05

372

Energetic Particle Physics In Fusion Research In Preparation For Burning Plasma Experiments  

SciTech Connect

The area of energetic particle (EP) physics of fusion research has been actively and extensively researched in recent decades. The progress achieved in advancing and understanding EP physics has been substantial since the last comprehensive review on this topic by W.W. Heidbrink and G.J. Sadler [1]. That review coincided with the start of deuterium-tritium (DT) experiments on Tokamak Fusion Test reactor (TFTR) and full scale fusion alphas physics studies. Fusion research in recent years has been influenced by EP physics in many ways including the limitations imposed by the "sea" of Alfven eigenmodes (AE) in particular by the toroidicityinduced AEs (TAE) modes and reversed shear Alfven (RSAE). In present paper we attempt a broad review of EP physics progress in tokamaks and spherical tori since the first DT experiments on TFTR and JET (Joint European Torus) including helical/stellarator devices. Introductory discussions on basic ingredients of EP physics, i.e. particle orbits in STs, fundamental diagnostic techniques of EPs and instabilities, wave particle resonances and others are given to help understanding the advanced topics of EP physics. At the end we cover important and interesting physics issues toward the burning plasma experiments such as ITER (International Thermonuclear Experimental Reactor).

Gorelenkov, Nikolai N [PPPL

2013-06-01

373

Advances in data representation for hard/soft information fusion  

NASA Astrophysics Data System (ADS)

Information fusion is becoming increasingly human-centric. While past systems typically relegated humans to the role of analyzing a finished fusion product, current systems are exploring the role of humans as integral elements in a modular and extensible distributed framework where many tasks can be accomplished by either human or machine performers. For example, "participatory sensing" campaigns give humans the role of "soft sensors" by uploading their direct observations or as "soft sensor platforms" by using mobile devices to record human-annotated, GPS-encoded high quality photographs, video, or audio. Additionally, the role of "human-in-the-loop", in which individuals or teams using advanced human computer interface (HCI) tools such as stereoscopic 3D visualization, haptic interfaces, or aural "sonification" interfaces can help to effectively engage the innate human capability to perform pattern matching, anomaly identification, and semantic-based contextual reasoning to interpret an evolving situation. The Pennsylvania State University is participating in a Multi-disciplinary University Research Initiative (MURI) program funded by the U.S. Army Research Office to investigate fusion of hard and soft data in counterinsurgency (COIN) situations. In addition to the importance of this research for Intelligence Preparation of the Battlefield (IPB), many of the same challenges and techniques apply to health and medical informatics, crisis management, crowd-sourced "citizen science", and monitoring environmental concerns. One of the key challenges that we have encountered is the development of data formats, protocols, and methodologies to establish an information architecture and framework for the effective capture, representation, transmission, and storage of the vastly heterogeneous data and accompanying metadata -- including capabilities and characteristics of human observers, uncertainty of human observations, "soft" contextual data, and information pedigree. This paper describes our findings and offers insights into the role of data representation in hard/soft fusion.

Rimland, Jeffrey C.; Coughlin, Dan; Hall, David L.; Graham, Jacob L.

2012-06-01

374

Magnetized Target Fusion in Advanced Propulsion Research  

NASA Technical Reports Server (NTRS)

The Magnetized Target Fusion (MTF) Propulsion lab at NASA Marshall Space Flight Center in Huntsville, Alabama has a program in place that has adopted to attempt to create a faster, lower cost and more reliable deep space transportation system. In this deep space travel the physics and development of high velocity plasma jets must be understood. The MTF Propulsion lab is also in attempt to open up the solar system for human exploration and commercial use. Fusion, as compared to fission, is just the opposite. Fusion involves the light atomic nuclei combination to produce denser nuclei. In the process, the energy is created by destroying the mass according to the distinguished equation: E = mc2 . Fusion energy development is being pursued worldwide as a very sustainable form of energy that is environmentally friendly. For the purposes of space exploration fusion reactions considered include the isotopes of hydrogen-deuterium (D2) and tritium (T3). Nuclei have an electrostatic repulsion between them and in order for the nuclei to fuse this repulsion must be overcome. One technique to bypass repulsion is to heat the nuclei to very high temperatures. The temperatures vary according to the type of reactions. For D-D reactions, one billion degrees Celsius is required, and for D-T reactions, one hundred million degrees is sufficient. There has to be energy input for useful output to be obtained form the fusion To make fusion propulsion practical, the mass, the volume, and the cost of the equipment to produce the reactions (generally called the reactor) need to be reduced by an order of magnitude or two from the state-of-the-art fusion machines. Innovations in fusion schemes are therefore required, especially for obtaining thrust for propulsive applications. Magnetized target fusion (MTF) is one of the innovative fusion concepts that have emerged over the last several years. MSFC is working with Los Alamos National Laboratory and other research groups in studying the underlying principles involved in MTF. Magnetized Target Fusion is an attempt to combine MCF (magnetic confinement fusion) for energy confinement and ICF (inertial confinement fusion) for efficient compression heating and wall free containment of the fusing plasma. It also seeks to combine the best features to these two main commonplace approaches to fusion.

Cylar, Rashad

2003-01-01

375

Ch. 37, Inertial Fusion Energy Technology  

SciTech Connect

Nuclear fission, nuclear fusion, and renewable energy (including biofuels) are the only energy sources capable of satisfying the Earth's need for power for the next century and beyond without the negative environmental impacts of fossil fuels. Substantially increasing the use of nuclear fission and renewable energy now could help reduce dependency on fossil fuels, but nuclear fusion has the potential of becoming the ultimate base-load energy source. Fusion is an attractive fuel source because it is virtually inexhaustible, widely available, and lacks proliferation concerns. It also has a greatly reduced waste impact, and no danger of runaway reactions or meltdowns. The substantial environmental, commercial, and security benefits of fusion continue to motivate the research needed to make fusion power a reality. Replicating the fusion reactions that power the sun and stars to meet Earth's energy needs has been a long-sought scientific and engineering challenge. In fact, this technological challenge is arguably the most difficult ever undertaken. Even after roughly 60 years of worldwide research, much more remains to be learned. the magnitude of the task has caused some to declare that fusion is 20 years away, and always will be. This glib criticism ignores the enormous progress that has occurred during those decades, progress inboth scientific understanding and essential technologies that has enabled experiments producing significant amounts of fusion energy. For example, more than 15 megawatts of fusion power was produced in a pulse of about half a second. Practical fusion power plants will need to produce higher powers averaged over much longer periods of time. In addition, the most efficient experiments to date have required using about 50% more energy than the resulting fusion reaction generated. That is, there was no net energy gain, which is essential if fusion energy is to be a viable source of electricity. The simplest fusion fuels, the heavy isotopes of hydrogen (deuterium and tritium), are derived from water and the metal lithium, a relatively abundant resource. The fuels are virtually inexhaustible and they are available worldwide. Deuterium from one gallon of seawater would provide the equivalent energy of 300 gallons of gasoline, or over a half ton of coal. This energy is released when deuterium and tritium nuclei are fused together to form a helium nucleus and a neutron. The neutron is used to breed tritium from lithium. The energy released is carried by the helium nucleus (3.5 MeV) and the neutron (14 MeV). The energetic helium nucleus heats the fuel, helping to sustain the fusion reaction. Once the helium cools, it is collected and becomes a useful byproduct. A fusion power plant would produce no climate-changing gases.

Moses, E

2010-06-09

376

Device for cutting protrusions  

DOEpatents

An apparatus for clipping a protrusion of material is provided. The protrusion may, for example, be a bolt head, a nut, a rivet, a weld bead, or a temporary assembly alignment tab protruding from a substrate surface of assembled components. The apparatus typically includes a cleaver having a cleaving edge and a cutting blade having a cutting edge. Generally, a mounting structure configured to confine the cleaver and the cutting blade and permit a range of relative movement between the cleaving edge and the cutting edge is provided. Also typically included is a power device coupled to the cutting blade. The power device is configured to move the cutting edge toward the cleaving edge. In some embodiments the power device is activated by a momentary switch. A retraction device is also generally provided, where the retraction device is configured to move the cutting edge away from the cleaving edge.

Bzorgi, Fariborz M. (Knoxville, TN)

2011-07-05

377

Inertial-Electrostatic Confinement (IEC) Fusion for Space Propulsion  

NASA Technical Reports Server (NTRS)

An Inertial-Electrostatic Confinement (IEC) device was assembled at the Marshall Space Flight Center (MSFC) Propulsion Research Center (PRC) to study the possibility of using EEC technology for deep space propulsion and power. Inertial-Electrostatic Confinement is capable of containing a nuclear fusion plasma in a series of virtual potential wells. These wells would substantially increase plasma confinement, possibly leading towards a high-gain, breakthrough fusion device. A one-foot in diameter IEC vessel was borrowed from the Fusion Studies Laboratory at the University of Illinois@Urbana-Champaign for the summer. This device was used in initial parameterization studies in order to design a larger, actively cooled device for permanent use at the PRC.

Nadler, Jon

1999-01-01

378

Inertial-Electrostatic Confinement (IEC) Fusion For Space Propulsion  

NASA Technical Reports Server (NTRS)

An Inertial-Electrostatic Confinement (IEC) device was assembled at the Marshall Space Flight Center (MSFC) Propulsion Research Center (PRC) to study the possibility of using IEC technology for deep space propulsion and power. Inertial-Electrostatic Confinement is capable of containing a nuclear fusion plasma in a series of virtual potential wells. These wells would substantially increase plasma confinement, possibly leading towards a high-gain, breakthrough fusion device. A one-foot in diameter IEC vessel was borrowed from the Fusion Studies Laboratory at the University of Illinois @ Urbana-Champaign for the summer. This device was used in initial parameterization studies in order to design a larger, actively cooled device for permanent use at the PRC.

Nadler, Jon

1999-01-01

379

Utility requirements for fusion  

SciTech Connect

This report describes work done and results obtained during performance of Task 1 of a study of Utility Requirements and Criteria for Fusion Options. The work consisted of developing a list of utility requirements for fusion optics containing definition of the requirements and showing their relative importance to the utility industry. The project team members developed a preliminary list which was refined by discussions and literature searches. The refined list was recast as a questionnaire which was sent to a substantial portion of the utility industry in this country. Forty-three questionnaire recipients responded including thirty-two utilities. A workshop was held to develop a revised requirements list using the survey responses as a major input. The list prepared by the workshop was further refined by a panel consisting of vice presidents of the three project team firms. The results of the study indicate that in addition to considering the cost of energy for a power plant, utilities consider twenty-three other requirements. Four of the requirements were judged to be vital to plant acceptability: Plant Capital Cost, Financial Liability, Plant Safety and Licensability.

Vondrasek, R.J.

1982-02-01

380

Magnetized target fusion and fusion propulsion.  

SciTech Connect

Magnetized target fusion (MTF) is a thermonuclear fusion concept that is intermediate between the two mainline approaches, magnetic confinement and inertial confinement fusion (MCF and ICF). MTF incorporates some aspects of each and offers advantages over each of the mainline approaches. First, it provides a means of reducing the driver power requirements, thereby admitting a wider range of drivers than ICF. Second, the magnetic field is only used for insulation, not confinement, and the plasma is wall confined, so that plasma instabilities are traded in for hydrodynamic instabilities. However, the degree of compression required to reach fusion conditions is lower than for ICF, so that hydrodynamic instabilities are much less threatening. The standoff driver innovation proposes to dynamically form the target plasma and a gaseous shell that compresses and confines the target plasma. Therefore, fusion target fabrication is traded in for a multiplicity of plasma guns, which must work in synchrony. The standoff driver embodiment of MTF leads to a fusion propulsion system concept that is potentially compact and lightweight. We will discuss the underlying physics of MTF and some of the details of the fusion propulsion concept using the standoff driver approach. We discuss here the optimization of an MTF target design for space propulsion.

Kirkpatrick, R. C. (Ronald C.)

2001-01-01

381

IEC Device Core Physics Explorations* John F. Santarius and Gilbert A. Emmert  

E-print Network

). · N.A. Krall, "The PolywellTM: a Spherically Convergent Ion Focus Concept," Fusion Technology 22, 42IEC Device Core Physics Explorations* John F. Santarius and Gilbert A. Emmert Fusion Technology Institute University of Wisconsin 14th US-Japan Workshop on Inertial Electrostatic Confinement Fusion

382

Proton Detector Calibration in a Gridded Inertial Electrostatic Confinement Device  

Microsoft Academic Search

Recent work [S. Krupakar Murali, J. F. Santarius, and G. L. Kulcinski, Phys. Plasmas, 15, 122702, (2008)] indicates that fusion reactions in an inertial electrostatic confinement (IEC) device primarily occur in microchannels. Since microchannels form discretely all around the cathode, the proton calibration procedure necessitated the estimation of fusion reactivity within the microchannels. Unlike neutron detectors that see a point

S. Krupakar Murali; John F. Santarius; Gerald L. Kulcinski

2010-01-01

383

The future of fusion power comes into focus  

NASA Astrophysics Data System (ADS)

Experimental studies of plasma behavior from the five large tokamaks and one mirror which began operations in 1978-79 are briefly surveyed, and the progress of the Mirror Fusion Test Facility and the Tokamak Fusion Test Reactor is noted as part of an outline of the U.S. fusion power program. The advanced designs described include the Engineering Test Facility, The International Tokamak Reactor, and the Commercial Tokamak study. Department of Energy policies and recent changes in government fusion organization are discussed, and industry participation and the economics of fusion are addressed. Experimental facilities and projects under development which do not utilize a research reactor are also discussed.

Briggs, W. B.

384

INTRODUCTION: Status report on fusion research  

NASA Astrophysics Data System (ADS)

A major milestone on the path to fusion energy was reached in June 2005 on the occasion of the signing of the joint declaration of all parties to the ITER negotiations, agreeing on future arrangements and on the construction site at Cadarache in France. The International Atomic Energy Agency has been promoting fusion activities since the late 1950s; it took over the auspices of the ITER Conceptual Design Activities in 1988, and of the ITER Engineering and Design Activities in 1992. The Agency continues its support to Member States through the organization of consultancies, workshops and technical meetings, the most prominent being the series of International Fusion Energy Conferences (formerly called the International Conference on Plasma Physics and Controlled Nuclear Fusion Research). The meetings serve as a platform for experts from all Member States to have open discussions on their latest accomplishments as well as on their problems and eventual solutions. The papers presented at the meetings and conferences are routinely published, many being sent to the journal it Nuclear Fusion, co-published monthly by Institute of Physics Publishing, Bristol, UK. The journal's reputation is reflected in the fact that it is a world-renowned publication, and the International Fusion Research Council has used it for the publication of a Status Report on Controlled Thermonuclear Fusion in 1978 and 1990. This present report marks the conclusion of the preparatory phases of ITER activities. It provides background information on the progress of fusion research within the last 15 years. The International Fusion Research Council (IFRC), which initiated the report, was fully aware of the complexities of including all scientific results in just one paper, and so decided to provide an overview and extensive references for the interested reader who need not necessarily be a fusion specialist. Professor Predhiman K. Kaw, Chairman, prepared the report on behalf of the IFRC, reflecting members' personal views on the latest achievements in fusion research, including magnetic and inertial confinement scenarios. The report describes fusion fundamentals and progress in fusion science and technology, with ITER as a possible partner in the realization of self-sustainable burning plasma. The importance of the socio-economic aspects of energy production using fusion power plants is also covered. Noting that applications of plasma science are of broad interest to the Member States, the report addresses the topic of plasma physics to assist in understanding the achievements of better coatings, cheaper light sources, improved heat-resistant materials and other high-technology materials. Nuclear fusion energy production is intrinsically safe, but for ITER the full range of hazards will need to be addressed, including minimising radiation exposure, to accomplish the goal of a sustainable and environmentally acceptable production of energy. We anticipate that the role of the Agency will in future evolve from supporting scientific projects and fostering information exchange to the preparation of safety principles and guidelines for the operation of burning fusion plasmas with a Q > 1. Technical progress in inertial and magnetic confinement, as well as in alternative concepts, will lead to a further increase in international cooperation. New means of communication will be needed, utilizing the best resources of modern information technology to advance interest in fusion. However, today the basis of scientific progress is still through journal publications and, with this in mind, we trust that this report will find an interested readership. We acknowledge with thanks the support of the members of the IFRC as an advisory body to the Agency. Seven chairmen have presided over the IFRC since its first meeting in 1971 in Madison, USA, ensuring that the IAEA fusion efforts were based on the best professional advice possible, and that information on fusion developments has been widely and expertly disseminated. We further acknowledge the efforts of the Chairman of

Burkart, Werner

2005-10-01

385

Investigation into Fusion Feasibility of a Magnetized Target Fusion Reactor  

E-print Network

Investigation into Fusion Feasibility of a Magnetized Target Fusion Reactor Michael Lindstrom fusion en- ergy known as a magnetized target fusion reactor, in which an intense pressure wave the fusion reactor design we have chosen to model. In section 2, we present a simplified model and set

Wetton, Brian

386

Fusion reactor pumped laser  

DOEpatents

A nuclear pumped laser capable of producing long pulses of very high power laser radiation is provided. A toroidal fusion reactor provides energetic neutrons which are slowed down by a moderator. The moderated neutrons are converted to energetic particles capable of pumping a lasing medium. The lasing medium is housed in an annular cell surrounding the reactor. The cell includes an annular reflecting mirror at the bottom and an annular output window at the top. A neutron reflector is disposed around the cell to reflect escaping neutrons back into the cell. The laser radiation from the annular window is focused onto a beam compactor which generates a single coherent output laser beam. 10 figs.

Jassby, D.L.

1987-09-04

387

Electrochromic devices  

DOEpatents

An electrochromic device is disclosed having a selective ion transport layer which separates an electrochemically active material from an electrolyte containing a redox active material. The devices are particularly useful as large area architectural and automotive glazings due to there reduced back reaction.

Allemand, Pierre M. (Tucson, AZ); Grimes, Randall F. (Ann Arbor, MI); Ingle, Andrew R. (Tucson, AZ); Cronin, John P. (Tucson, AZ); Kennedy, Steve R. (Tuscon, AZ); Agrawal, Anoop (Tucson, AZ); Boulton, Jonathan M. (Tucson, AZ)

2001-01-01

388

Sensor fusion II: Human and machine strategies; Proceedings of the Meeting, Philadelphia, PA, Nov. 6-9, 1989  

NASA Technical Reports Server (NTRS)

Various papers on human and machine strategies in sensor fusion are presented. The general topics addressed include: active vision, measurement and analysis of visual motion, decision models for sensor fusion, implementation of sensor fusion algorithms, applying sensor fusion to image analysis, perceptual modules and their fusion, perceptual organization and object recognition, planning and the integration of high-level knowledge with perception, using prior knowledge and context in sensor fusion.

Schenker, Paul S. (editor)

1990-01-01

389

Fusion tritium program in the United States  

SciTech Connect

The fusion technology development program for tritium in the US is centered around the Tritium Systems Test Assembly (TSTA) at Los Alamos National Labortory. Objectives of this project are to develop and demonstrate the fuel cycle for processing the reactor exhaust gas (unburned deuterium and tritium plus impurities), and the necessary personnel and environemntal protection systems for the next generation of fusion devices. The TSTA is a full-scale system for an INTOR/ITER sized machine. That is, TSTA has the capacity to process tritium in a closed loop mode at the rate of 1 kg per day, requiring a tritium inventory of about 100 g. The TSTA program also interacts with all other tritium-related fusion technology programs in the US and all major programs abroad. This report is a summary of the results and interactions of the TSTA program since a previous summary was published and an overview of related tritium programs.

Anderson, J.L.; Bartlit, J.R.

1988-01-01

390

Development progresses of radio frequency ion source for neutral beam injector in fusion devicesa)  

NASA Astrophysics Data System (ADS)

A large-area RF (radio frequency)-driven ion source is being developed in Germany for the heating and current drive of an ITER device. Negative hydrogen ion sources are the major components of neutral beam injection systems in future large-scale fusion experiments such as ITER and DEMO. RF ion sources for the production of positive hydrogen (deuterium) ions have been successfully developed for the neutral beam heating systems at IPP (Max-Planck-Institute for Plasma Physics) in Germany. The first long-pulse ion source has been developed successfully with a magnetic bucket plasma generator including a filament heating structure for the first NBI system of the KSTAR tokamak. There is a development plan for an RF ion source at KAERI to extract the positive ions, which can be applied for the KSTAR NBI system and to extract the negative ions for future fusion devices such as the Fusion Neutron Source and Korea-DEMO. The characteristics of RF-driven plasmas and the uniformity of the plasma parameters in the test-RF ion source were investigated initially using an electrostatic probe.

Chang, D. H.; Jeong, S. H.; Kim, T. S.; Park, M.; Lee, K. W.; In, S. R.

2014-02-01

391

A Smartphone-Based Driver Safety Monitoring System Using Data Fusion  

PubMed Central

This paper proposes a method for monitoring driver safety levels using a data fusion approach based on several discrete data types: eye features, bio-signal variation, in-vehicle temperature, and vehicle speed. The driver safety monitoring system was developed in practice in the form of an application for an Android-based smartphone device, where measuring safety-related data requires no extra monetary expenditure or equipment. Moreover, the system provides high resolution and flexibility. The safety monitoring process involves the fusion of attributes gathered from different sensors, including video, electrocardiography, photoplethysmography, temperature, and a three-axis accelerometer, that are assigned as input variables to an inference analysis framework. A Fuzzy Bayesian framework is designed to indicate the driver’s capability level and is updated continuously in real-time. The sensory data are transmitted via Bluetooth communication to the smartphone device. A fake incoming call warning service alerts the driver if his or her safety level is suspiciously compromised. Realistic testing of the system demonstrates the practical benefits of multiple features and their fusion in providing a more authentic and effective driver safety monitoring. PMID:23247416

Lee, Boon-Giin; Chung, Wan-Young

2012-01-01

392

Planar electrochemical device assembly  

DOEpatents

A pre-fabricated electrochemical device having a dense electrolyte disposed between an anode and a cathode preferably deposited as thin films is bonded to a porous electrically conductive support. A second porous electrically conductive support may be bonded to a counter electrode of the electrochemical device. Multiple electrochemical devices may be bonded in parallel to a single porous support, such as a perforated sheet to provide a planar array. Planar arrays may be arranged in a stacked interconnected array. A method of making a supported electrochemical device is disclosed wherein the method includes a step of bonding a pre-fabricated electrochemical device layer to an existing porous metal or porous metal alloy layer.

Jacobson; Craig P. (Lafayette, CA), Visco; Steven J. (Berkeley, CA), De Jonghe; Lutgard C. (Lafayette, CA)

2010-11-09

393

Multisensor data fusion in an integrated tracking system for endoscopic surgery.  

PubMed

Surgical planning and navigation systems are vital for minimally invasive endoscopic surgeries but it is challenging to track the position and orientation of intrabody surgical instruments in these procedures. In order to address this problem, we propose a tracking system including multiple-sensor integration and data fusion. The proposed tracking approach is free of the constraints of line-of-sight, less subject to environmental distortion, and with higher update rate. By incorporating electromagnetic and inertial sensors, the system yields continuous 6-DOF information. Based on a system dynamic model and estimation theories, a new multisensor fusion algorithm, cascade orientation and position-estimation algorithm, is proposed for the integrated tracking device. The experimental results show that the proposed algorithms achieve accurate orientation and position tracking with robustness. PMID:21827975

Ren, Hongliang; Rank, Denis; Merdes, Martin; Stallkamp, Jan; Kazanzides, Peter

2012-01-01

394

Visualize Your Data with Google Fusion Tables  

NASA Astrophysics Data System (ADS)

Google Fusion Tables is a modern data management platform that makes it easy to host, manage, collaborate on, visualize, and publish tabular data online. Fusion Tables allows users to upload their own data to the Google cloud, which they can then use to create compelling and interactive visualizations with the data. Users can view data on a Google Map, plot data in a line chart, or display data along a timeline. Users can share these visualizations with others to explore and discover interesting trends about various types of data, including scientific data such as invasive species or global trends in disease. Fusion Tables has been used by many organizations to visualize a variety of scientific data. One example is the California Redistricting Map created by the LA Times: http://goo.gl/gwZt5 The Pacific Institute and Circle of Blue have used Fusion Tables to map the quality of water around the world: http://goo.gl/T4SX8 The World Resources Institute mapped the threat level of coral reefs using Fusion Tables: http://goo.gl/cdqe8 What attendees will learn in this session: This session will cover all the steps necessary to use Fusion Tables to create a variety of interactive visualizations. Attendees will begin by learning about the various options for uploading data into Fusion Tables, including Shapefile, KML file, and CSV file import. Attendees will then learn how to use Fusion Tables to manage their data by merging it with other data and controlling the permissions of the data. Finally, the session will cover how to create a customized visualization from the data, and share that visualization with others using both Fusion Tables and the Google Maps API.

Brisbin, K. E.

2011-12-01

395

Internship Contract (Includes Practicum)  

E-print Network

Internship Contract (Includes Practicum) Student's name-mail: _________________________________________ Internship Agency Contact Agency Name: ____________________________________ Address-mail: __________________________________________ Location of Internship, if different from Agency: ________________________________________________ Copies

Thaxton, Christopher S.

396

An introduction to multisensor data fusion  

Microsoft Academic Search

Multisensor data fusion is an emerging technology applied to Department of Defense {(DoD)} areas such as automated target recognition, battlefield surveillance, and guidance and control of autonomous vehicles, and to {non-DoD} applications such as monitoring of complex machinery, medical diagnosis, and smart buildings. Techniques for multisensor data fusion are drawn from a wide range of areas including artificial intelligence, pattern

DAVID L. HALL; JAMES LLINAS

1997-01-01

397

Laser driven instabilities in inertial confinement fusion  

SciTech Connect

Parametric instabilities excited by an intense electromagnetic wave in a plasma is a fundamental topic relevant to many applications. These applications include laser fusion, heating of magnetically-confined plasmas, ionospheric modification, and even particle acceleration for high energy physics. In laser fusion, these instabilities have proven to play an essential role in the choice of laser wavelength. Characterization and control of the instabilities is an ongoing priority in laser plasma experiments. Recent progress and some important trends will be discussed. 8 figs.

Kruer, W.L.

1990-06-04

398

Inertial confinement fusion-review series  

SciTech Connect

This paper discusses three articles that deal with the detailed target physics phenomena and the underlying science of driver development. The articles provide perspective for future articles on reactor implications and program plans. Specifically, the articles deal with the target requirements for a laser fusion reactor with consideration of the direct illumination approach, the issue of ion beam propagation and focusing, and high power laser for fusion applications including the Nova glass laser and Antares CO/sub 2/ laser now under construction.

Lidsky, L.M.

1981-07-01

399

Identification of Targetable FGFR Gene Fusions in Diverse Cancers  

PubMed Central

Through a prospective clinical sequencing program for advanced cancers, four index cases were identified which harbor gene rearrangements of FGFR2 including patients with cholangiocarcinoma, breast cancer, and prostate cancer. After extending our assessment of FGFR rearrangements across multiple tumor cohorts, we identified additional FGFR gene fusions with intact kinase domains in lung squamous cell cancer, bladder cancer, thyroid cancer, oral cancer, glioblastoma, and head and neck squamous cell cancer. All FGFR fusion partners tested exhibit oligomerization capability, suggesting a shared mode of kinase activation. Overexpression of FGFR fusion proteins induced cell proliferation. Two bladder cancer cell lines that harbor FGFR3 fusion proteins exhibited enhanced susceptibility to pharmacologic inhibition in vitro and in vivo. Due to the combinatorial possibilities of FGFR family fusion to a variety of oligomerization partners, clinical sequencing efforts which incorporate transcriptome analysis for gene fusions are poised to identify rare, targetable FGFR fusions across diverse cancer types. PMID:23558953

Wu, Yi-Mi; Su, Fengyun; Kalyana-Sundaram, Shanker; Khazanov, Nick; Ateeq, Bushra; Cao, Xuhong; Lonigro, Robert J.; Vats, Pankaj; Wang, Rui; Lin, Su-Fang; Cheng, Ann-Joy; Kunju, Lakshmi P.; Siddiqui, Javed; Tomlins, Scott A.; Wyngaard, Peter; Sadis, Seth; Roychowdhury, Sameek; Hussain, Maha H.; Feng, Felix Y.; Zalupski, Mark M.; Talpaz, Moshe; Pienta, Kenneth J.; Rhodes, Daniel R.; Robinson, Dan R.; Chinnaiyan, Arul M.

2013-01-01

400

Chamber Design for the Laser Inertial Fusion Energy (LIFE) Engine  

SciTech Connect

The Laser Inertial Fusion Energy (LIFE) concept is being designed to operate as either a pure fusion or hybrid fusion-fission system. The present work focuses on the pure fusion option. A key component of a LIFE engine is the fusion chamber subsystem. It must absorb the fusion energy, produce fusion fuel to replace that burned in previous targets, and enable both target and laser beam transport to the ignition point. The chamber system also must mitigate target emissions, including ions, x-rays and neutrons and reset itself to enable operation at 10-15 Hz. Finally, the chamber must offer a high level of availability, which implies both a reasonable lifetime and the ability to rapidly replace damaged components. An integrated design that meets all of these requirements is described herein.

Latkowski, J F; Abbott, R P; Aceves, S; Anklam, T; Badders, D; Cook, A W; DeMuth, J; Divol, L; El-Dasher, B; Farmer, J C; Flowers, D; Fratoni, M; ONeil, R G; Heltemes, T; Kane, J; Kramer, K J; Kramer, R; Lafuente, A; Loosmore, G A; Morris, K R; Moses, G A; Olson, B; Pantano, C; Reyes, S; Rhodes, M; Roe, K; Sawicki, R; Scott, H; Spaeth, M; Tabak, M; Wilks, S

2010-11-30

401

Include folders ! Classic black  

E-print Network

credit card number and fax 24 hours a day. If faxing please do not mail the order. By Mail: Fill out.35% By Phone: 978-851-5924 - Please have credit card ready. By Fax: 978-851-8992 Fill out information, include the form, include payment by check or credit card (MasterCard, Visa, Discover or American Express) How

402

Viral membrane fusion  

Microsoft Academic Search

Infection by viruses having lipid-bilayer envelopes proceeds through fusion of the viral membrane with a membrane of the target cell. Viral 'fusion proteins' facilitate this process. They vary greatly in structure, but all seem to have a common mechanism of action, in which a ligand-triggered, large-scale conformational change in the fusion protein is coupled to apposition and merger of the

Stephen C Harrison

2008-01-01

403

The fusion breeder  

Microsoft Academic Search

The fusion breeder is a fusion reactor designed with special blankets to maximize the transmutation by 14 MeV neutrons of uranium-238 to plutonium or thorium to uranium-233 for use as a fuel for fission reactors. Breeding fissile fuels has not been a goal of the U.S. fusion energy program. This paper suggests it is time for a policy change to

Ralph W. Moir

1982-01-01

404

EPICS GPIB device support  

SciTech Connect

A GPIB device support module is used to provide access to the operating parameters of a GPIB device. GPIB devices may be accessed via National Instruments 1014 cards or via Bitbus Universal Gateways. GPIB devices typically have many parameters, each of which may be thought of in terms of the standard types of database records available in EPICS. It is the job of the device support module designer to decide how the mapping of these parameters will be made to the available record types. Once this mapping is complete, the device support module may be written. The writing of the device support module consists primarily of the construction of a parameter table. This table is used to associate the database record types with the operating parameters of the GPIB instrument. Other aspects of module design include the handling of SRQ events and errors. SRQ events are made available to the device support module if so desired. The processing of an SRQ event is completely up to the designer of the module. They may be ignored, tied to event based record processing, or anything else the designer wishes. Error conditions may be handled in a similar fashion.

Winans, J.

1993-09-24

405

ACE Mission - Fusion and Nucleosynthesis  

NSDL National Science Digital Library

This educational brief explains the idea that nuclear fusion is thought to be the mechanism by which virtually all of the elements around us are created. Topics include the proton-proton cycle, the carbon-nitrogen-oxygen cycle, and endothermic reactions in supernova explosions. There is also a discussion of the Advanced Composition Explorer (ACE), a spacecraft intended to study the origin and evolution of the elements produced by our Sun.

406

Fusion Power: A Strategic Choice for the Future Energy Provision. Why is So Much Time Wasted for Decision Making?  

SciTech Connect

From a general analysis of the world energy issue, it is argued that an affordable, clean and reliable energy supply will have to consist of a portfolio of primary energy sources, a large fraction of which will be converted to a secondary carrier in large baseload plants. Because of all future uncertainties, it would be irresponsible not to include thermonuclear fusion as one of the future possibilities for electricity generation.The author tries to understand why nuclear-fusion research is not considered of strategic importance by the major world powers. The fusion programs of the USA and Europe are taken as prime examples to illustrate the 'hesitation'. Europe is now advocating a socalled 'fast-track' approach, thereby seemingly abandoning the 'classic' time frame towards fusion that it has projected for many years. The US 'oscillatory' attitude towards ITER in relation to its domestic program is a second case study that is looked at.From the real history of the ITER design and the 'siting' issue, one can try to understand how important fusion is considered by these world powers. Not words are important, but deeds. Fast tracks are nice to talk about, but timely decisions need to be taken and sufficient money is to be provided. More fundamental understanding of fusion plasma physics is important, but in the end, real hardware devices must be constructed to move along the path of power plant implementation.The author tries to make a balance of where fusion power research is at this moment, and where, according to his views, it should be going.

D'haeseleer, William D

2005-04-15

407

Magnetic fusion reactor economics  

SciTech Connect

An almost primordial trend in the conversion and use of energy is an increased complexity and cost of conversion systems designed to utilize cheaper and more-abundant fuels; this trend is exemplified by the progression fossil fission {yields} fusion. The present projections of the latter indicate that capital costs of the fusion ``burner`` far exceed any commensurate savings associated with the cheapest and most-abundant of fuels. These projections suggest competitive fusion power only if internal costs associate with the use of fossil or fission fuels emerge to make them either uneconomic, unacceptable, or both with respect to expensive fusion systems. This ``implementation-by-default`` plan for fusion is re-examined by identifying in general terms fusion power-plant embodiments that might compete favorably under conditions where internal costs (both economic and environmental) of fossil and/or fission are not as great as is needed to justify the contemporary vision for fusion power. Competitive fusion power in this context will require a significant broadening of an overly focused program to explore the physics and simbiotic technologies leading to more compact, simplified, and efficient plasma-confinement configurations that reside at the heart of an attractive fusion power plant.

Krakowski, R.A.

1995-12-01

408

Establishment of an Institute for Fusion Studies  

SciTech Connect

The Institute for Fusion Studies is a national center for theoretical fusion plasma physics research. Its purposes are: (1) to conduct research on theoretical questions concerning the achievement of controlled fusion energy by means of magnetic confinement--including both fundamental problems of long-range significance, as well as shorter-term issues; (2) to serve as a center for information exchange, nationally and internationally, by hosting exchange visits, conferences, and workshops; (3) and to train students and postdoctoral research personnel for the fusion energy program and plasma physics research areas. The theoretical research results that are obtained by the Institute contribute mainly to the progress of national and international efforts in nuclear fusion research, whose goal is the development of fusion power.as a basic energy source. In addition to its primary focus on fusion physics, the Institute is also involved with research in related fields, such as advanced computing techniques, nonlinear dynamics, plasma astrophysics, and accelerator physics. The work of EFS scientists continued to receive national and international recognition. Numerous invited papers were given during the past year at workshops, conferences, and scientific meetings. Last year IFS scientists published 95 scientific articles in technical journals and monographs.

Hazeltine, R.D.

1992-07-01

409

BOOK REVIEW: Advanced Diagnostics for Magnetic and Inertial Confinement Fusion  

NASA Astrophysics Data System (ADS)

This book is a collection of papers, written by specialists in the field, on advanced topics of nuclear fusion diagnostics. The 78 contributions were originally presented at the International Conference on Advanced Diagnostics for Magnetic and Inertial Fusion held at Villa Monastero, Italy in September 2001. Both magnetically confined and inertial fusion programmes are quite extensively covered, with more emphasis given to the former scheme. In the case of magnetic confinement, since the present international programme is strongly focused on next-step devices, particular attention is devoted to techniques and technologies viable in an environment with strong neutron fluxes. Indeed, in the first section, the various methods are considered in the perspective of performing the measurements of the relevant parameters in conditions approaching a burning plasma, mainly in the Tokamak configuration. The most demanding requirements, like the implications of the use of tritium and radiation resistance, are reviewed and the most challenging open issues, which require further research and development, are also clearly mentioned. The following three sections are devoted to some of the most recent developments in plasma diagnostics, which are grouped according to the following classification: `Neutron and particle diagnostics', `Optical and x-ray diagnostics' and `Interferometry, Polarimetry and Thomson Scattering'. In these chapters, several of the most recent results are given, covering measurements taken on the most advanced experiments around the world. Here the developments described deal more with the requirements imposed by the physical issues to be studied. They are therefore more focused on the approaches adopted to increase the spatial and time resolution of the diagnostics, on some methods to improve the characterisation of the turbulence and on fast particles. Good coverage is given to neutron diagnostics, which are assuming increasing relevance as the plasma parameters approach ignition. Spectroscopic systems and their recent developments are well represented, whereas edge diagnostics are somewhat thin on the ground. A dedicated section is devoted to the latest tests on radiation effects and technological issues. The problems of damage to optical components and the difficulties presented by the determination of the tritium inventory are described. In the last part, the new diagnostic systems of the most recent experiments (under construction or recently operated) are reported. Various aspects of some diagnostics not included in the three previous sections are also covered, with particular emphasis on microwaves and infrared diagnostics. The book is well suited for specialists and, more generally, for people involved in nuclear fusion, who need information about the most recent developments in the field of plasma diagnostics. The papers cover many aspects of the challenges and possible solutions for performing measurements in fusion machines approaching reactor conditions. On the other hand, the contributions are in general quite advanced and would be challenging for people without a significant background in plasma diagnostics and nuclear fusion. The quality of the paper is more than satisfactory both from the point of view of clarity and of graphics. Moreover, at the beginning of the book, several papers make a considerable effort to put diagnostic issues in the wider context of present day nuclear fusion research. For those topics, which are too involved to be completely described in a conference contribution, in general adequate references are provided for deeper investigation. A Murari Approximately one third of the papers included in this volume deal with diagnostics related to inertial confinement fusion plasmas (i.e., laser-produced plasmas and pulsed-power). These papers discuss recent developments in charged particle diagnostics, neutron diagnostics, optical and x-ray measurements along with laser and particle probing diagnostics. The resulting collection of papers is comprehensive and wide-ranging and all of th

Stott, PE; Wootton, A.; Gorini, G.; Sindoni, E.; Batani, D.

2003-02-01

410

Effects of chamber pressure variation on the grid temperature in an inertial electrostatic confinement device  

Microsoft Academic Search

Inertial electrostatic confinement fusion devices are compact sources of neutrons, protons, electrons, and x rays. Such sources have many applications. Improving the efficiency of the device also increases the applications of this device. Hence a thorough understanding of the operation of this device is needed. In this paper, we study the effect of chamber pressure on the temperature of the

S. Krupakar Murali; G. A. Emmert; J. F. Santarius; G. L. Kulcinski

2010-01-01

411

Automobile maneuvering device  

SciTech Connect

An automobile maneuvering device is described which consists of: a chassis comprising transport wheels for permitting movement of the device along the ground, a drive wheel operably rotatably connected to the chassis, and means for rotating the drive wheel, clamp means operably connected to the chassis and spaced from and opposed to the drive wheel, the chassis including means to move the clamp means to engage one portion of an automobile tire with the drive wheel engaged at another portion of the automobile tire, and means to actuate the rotating means, so that with rotation of the drive wheel the automobile tire is rotated and the automobile and device moved along the ground.

Ricciardi, R.

1987-08-18

412

Rain sampling device  

DOEpatents

The present invention constitutes a rain sampling device adapted for independent operation at locations remote from the user which allows rainfall to be sampled in accordance with any schedule desired by the user. The rain sampling device includes a mechanism for directing wet precipitation into a chamber, a chamber for temporarily holding the precipitation during the process of collection, a valve mechanism for controllably releasing samples of said precipitation from said chamber, a means for distributing the samples released from the holding chamber into vessels adapted for permanently retaining these samples, and an electrical mechanism for regulating the operation of the device.

Nelson, Danny A. (Richland, WA); Tomich, Stanley D. (Richland, WA); Glover, Donald W. (Prosser, WA); Allen, Errol V. (Benton City, WA); Hales, Jeremy M. (Kennewick, WA); Dana, Marshall T. (Richland, WA)

1991-01-01

413

Rain sampling device  

DOEpatents

The present invention constitutes a rain sampling device adapted for independent operation at locations remote from the user which allows rainfall to be sampled in accordance with any schedule desired by the user. The rain sampling device includes a mechanism for directing wet precipitation into a chamber, a chamber for temporarily holding the precipitation during the process of collection, a valve mechanism for controllably releasing samples of the precipitation from the chamber, a means for distributing the samples released from the holding chamber into vessels adapted for permanently retaining these samples, and an electrical mechanism for regulating the operation of the device. 11 figures.

Nelson, D.A.; Tomich, S.D.; Glover, D.W.; Allen, E.V.; Hales, J.M.; Dana, M.T.

1991-05-14

414

Radiation Shielding for Fusion Reactors  

SciTech Connect

Radiation shielding requirements for fusion reactors present different problems than those for fission reactors and accelerators. Fusion devices, particularly tokamak reactors, are complicated by geometry constraints that complicate disposition of fully effective shielding. This paper reviews some of these shielding issues and suggested solutions for optimizing the machine and biological shielding. Radiation transport calculations are essential for predicting and confirming the nuclear performance of the reactor and, as such, must be an essential part of the reactor design process. Development and optimization of reactor components from the first wall and primary shielding to the penetrations and containment shielding must be carried out in a sensible progression. Initial results from one-dimensional transport calculations are used for scoping studies and are followed by detailed two- and three-dimensional analyses to effectively characterize the overall radiation environment. These detail model calculations are essential for accounting for the radiation leakage through ports and other penetrations in the bulk shield. Careful analysis of component activation and radiation damage is cardinal for defining remote handling requirements, in-situ replacement of components, and personnel access at specific locations inside the reactor containment vessel. Radiation shielding requirements for fusion reactors present different problems than those for fission reactors and accelerators. Fusion devices, particularly tokamak reactors, are complicated by geometry constraints that complicate disposition of fully effective shielding. This paper reviews some of these shielding issues and suggested solutions for optimizing the machine and biological shielding. Radiation transport calculations are essential for predicting and confirming the nuclear performance of the reactor and, as such, must be an essential part of the reactor design process. Development and optimization of reactor components from the first wall and primary shielding to the penetrations and containment shielding must be carried out in a sensible progression. Initial results from one-dimensional transport calculations are used for scoping studies and are followed by detailed two- and three-dimensional analyses to effectively characterize the overall radiation environment. These detail model calculations are essential for accounting for the radiation leakage through ports and other penetrations in the bulk shield. Careful analysis of component activation and radiation damage is cardinal for defining remote handling requirements, in-situ replacement of components, and personnel access at specific locations inside the reactor containment vessel.

Santoro, R.T.

1999-10-01

415

Choice of coils for a fusion reactor.  

PubMed

In a fusion reactor a hot plasma of deuterium and tritium is confined by a strong magnetic field to produce helium ions and release energetic neutrons. The 3D geometry of a stellarator provides configurations for such a device that reduce net toroidal current that might lead to disruptions. We construct smooth coils generating an external magnetic field designed to prevent the plasma from deteriorating. PMID:17640879

Alexander, Romeo; Garabedian, Paul R

2007-07-24

416

The application of diagnostic equipment in the Tokamak fusion reaction  

NASA Astrophysics Data System (ADS)

This paper introduces the infrared optical system in the Tokamak fusion reaction device. In this optical system, the traditional optical structure can't meet the requirements, because the length of the infrared optical system in the Tokamak is very long. The design of optical system in the detection facility includes three parts:1.the combination of the concave aspheric mirror and flat mirror; 2.the Cassegrain system; 3.the relay group lenses. This paper describes the decrease of the modulation transfer function (MTF) when the temperature changes and how to compensate the decrease of the MTF in order to maintain the image quality in a high level. As a result, the image quality of this optical system can reach the requirements when the temperature changes.

Zhang, Bang-shuai; Chang, Jun; Gong, Xian-zu; Gan, Jia-fu; Feng, Shu-long

2011-11-01

417

Negative ion source development for fusion application (invited).  

PubMed

Giant negative ion sources, producing high-current of several tens amps with high energy of several hundreds keV to 1 MeV, are required for a neutral beam injector (NBI) in a fusion device. The giant negative ion sources are cesium-seeded plasma sources, in which the negative ions are produced on the cesium-covered surface. Their characteristic features are discussed with the views of large-volume plasma production, large-area beam acceleration, and high-voltage dc holding. The international thermonuclear experimental reactor NBI employs a 1 MeV-40 A of deuterium negative ion source, and intensive development programs for the rf-driven source plasma production and the multistage electrostatic acceleration are in progress, including the long pulse operation for 3600 s. Present status of the development, as well as the achievements of the giant negative ion sources in the working injectors, is also summarized. PMID:20192420

Takeiri, Yasuhiko

2010-02-01

418

4:03 Nitric oxide modulates recombinant human bone morphogenic protein–2–induced corticocancellous autograft incorporation in a rat intertransverse process fusion model  

Microsoft Academic Search

Purpose of study: Nitric oxide has important physiological functions, including the modulation of fracture healing. Recombinant human bone morphogenic protein (rhBMP)-2 enhances spinal fusion. With progression of fusion, there is a remodeling of the fusion mass bone accompanied with a decrease in the fusion mass size. It is not known whether nitric oxide has a role in spinal fusion or

Ashish D. Diwan; Safdar N. Khan; Deirdre Campbell; M. Ng; Russell Nord; Michael Peterkin; Stephen B. Doty; Frank P. Cammisa; Harvinder S. Sandhu

2002-01-01

419

Gripping device  

NASA Technical Reports Server (NTRS)

This invention relates to a gripping device, and more particularly to one with a large moment carrying capability for handling long workpieces of various diameters and which can be particularly used as an end effector on a robotic arm.

Parma, George F. (inventor)

1989-01-01

420

Device Performance  

SciTech Connect

In the Device Performance group, within the National Center for Photovoltaic's Measurements and Characterization Division, we measure the performance of PV cells and modules with respect to standard reporting conditions--defined as a reference temperature (25 C), total irradiance (1000 Wm-2), and spectral irradiance distribution (IEC standard 60904-3). Typically, these are ''global'' reference conditions, but we can measure with respect to any reference set. To determine device performance, we conduct two general categories of measurements: spectral responsivity (SR) and current versus voltage (I-V). We usually perform these measurements using standard procedures, but we develop new procedures when required by new technologies. We also serve as an independent facility for verifying device performance for the entire PV community. We help the PV community solve its special measurement problems, giving advice on solar simulation, instrumentation for I-V measurements, reference cells, measurement procedures, and anomalous results. And we collaborate with researchers to analyze devices and materials.

Not Available

2006-06-01

421

Soldier systems sensor fusion  

NASA Astrophysics Data System (ADS)

This paper addresses sensor fusion and its applications in emerging Soldier Systems integration and the unique challenges associated with the human platform. Technology that,provides the highest operational payoff in a lightweight warrior system must not only have enhanced capabilities, but have low power components resulting in order of magnitude reductions coupled with significant cost reductions. These reductions in power and cost will be achieved through partnership with industry and leveraging of commercial state of the art advancements in microelectronics and power sources. As new generation of full solution fire control systems (to include temperature, wind and range sensors) and target acquisition systems will accompany a new generation of individual combat weapons and upgrade existing weapon systems. Advanced lightweight thermal, IR, laser and video senors will be used for surveillance, target acquisition, imaging and combat identification applications. Multifunctional sensors will provide embedded training features in combat configurations allowing the soldier to 'train as he fights' without the traditional cost and weight penalties associated with separate systems. Personal status monitors (detecting pulse, respiration rate, muscle fatigue, core temperature, etc.) will provide commanders and highest echelons instantaneous medical data. Seamless integration of GPS and dead reckoning (compass and pedometer) and/or inertial sensors will aid navigation and increase position accuracy. Improved sensors and processing capability will provide earlier detection of battlefield hazards such as mines, enemy lasers and NBC (nuclear, biological, chemical) agents. Via the digitized network the situational awareness database will automatically be updated with weapon, medical, position and battlefield hazard data. Soldier Systems Sensor Fusion will ultimately establish each individual soldier as an individual sensor on the battlefield.

Brubaker, Kathryne M.

1998-08-01

422

Prospects for bubble fusion  

SciTech Connect

In this paper a new method for the realization of fusion energy is presented. This method is based on the superhigh compression of a gas bubble (deuterium or deuterium/thritium) in heavy water or another liquid. The superhigh compression of a gas bubble in a liquid is achieved through forced non-linear, non-periodic resonance oscillations using moderate amplitudes of forcing pressure. The key feature of this new method is a coordination of the forced liquid pressure change with the change of bubble volume. The corresponding regime of the bubble oscillation has been called {open_quotes}basketball dribbling (BD) regime{close_quotes}. The analytical solution describing this process for spherically symmetric bubble oscillations, neglecting dissipation and compressibility of the liquid, has been obtained. This solution shown no limitation on the supercompression of the bubble and the corresponding maximum temperature. The various dissipation mechanisms, including viscous, conductive and radiation heat losses have been considered. It is shown that in spite of these losses it is possible to achieve very high gas bubble temperatures. This because the time duration of the gas bubble supercompression becomes very short when increasing the intensity of compression, thus limiting the energy losses. Significantly, the calculated maximum gas temperatures have shown that nuclear fusion may be possible. First estimations of the affect of liquid compressibility have been made to determine possible limitations on gas bubble compression. The next step will be to investigate the role of interfacial instability and breaking down of the bubble, shock wave phenomena around and in the bubble and mutual diffusion of the gas and the liquid.

Nigmatulin, R.I. [Tyumen Institute of Mechanics of Multiphase Systems (TIMMS), Marx (Russian Federation); Lahey, R.T. Jr. [Rensselaer Polytechnic Institute, Troy, NY (United States)

1995-09-01

423

Inertial-electrostatic confinement (IEC) fusion for space power  

SciTech Connect

Fusion offers the potential for a very high specific power, providing a large specific impulse that can be traded-off with thrust for mission optimization. Thus fusion is a leading candidate for missions beyond the moon. Here we discuss a new approach for space fusion power, namely Inertial-Electrostatic Confinement (IEC). This method offers a high power density in a relatively small, simple device. It appears capable of burning aneutronic fuels which are most desirable for space applications and is well suited for direct energy conversion.

Miley, G.H.; Nadler, J.H.; Hochberg, T.K.; Barnouin, O.; Gu, Y. (Fusion Studies Laboratory, 103 S. Goodwin Avenue, University of Illinois, Urbana, Illinois 61801 (US))

1991-01-01

424

Fusion tritons and plasma-facing components in a fusion reactor  

NASA Astrophysics Data System (ADS)

We would like to discuss the role that 1 MeV tritons produced in deuterium-deuterium fusion reactions might play in a long-pulse or steady-state fusion reactor. Albeit a small minority in quantity compared to the fuel tritium, the fusion tritons have significantly longer penetration length in materials and can have detrimental consequences for the integrity of the components. Because deeply deposited atoms are not easily removed from the plasma-facing components, the fusion tritium inventory in a steady-state device is expected to be limited only by decay. Furthermore, unlike fuel tritium, it is not evenly distributed on the plasma-facing components. We conclude that, of the materials considered here, tungsten appears better than carbon or beryllium in this respect. Nonetheless, 1 MeV tritons from deuterium fusion should not be neglected when making material choices for ITER and, especially, for future fusion reactors. In particular, studies on the bulk effects of deeply penetrated tritium in tungsten are urgently needed if metal-wall reactors are considered for the future. This is an interdisciplinary problem needing the attention of material scientists and plasma physicists.

Kurki-Suonio, T.; Hynönen, V.; Ahlgren, T.; Nordlund, K.; Sugiyama, K.; Dux, R.

2007-06-01

425

Medical Device Reliability BIOMATERIALS  

E-print Network

of the U.S. healthcare industry, with annual sales exceeding $13 billion. In the past decade, nearly 3 Laboratory The iNEMI Medical Technology Integration Group, which includes NIST, has produced a number of documents that advance our long-term goal of better standards for medical device technology. These include

426

A brief overview of the Fusion and Astrophysics Data and Diagnostic Calibration Facility  

NASA Astrophysics Data System (ADS)

The Fusion and Astrophysics (FAST) Data and Diagnostic Calibration Facility located at the Lawrence Livermore National Laboratory is a state-of-the-art facility used to calibrate radiation based diagnostics and study atomic processes for investigating fusion and astrophysical plasmas. FAST has at its disposal a full suite of radiation generation and detection devices, including two electron beam ion traps: EBIT-I and SuperEBIT and an absolutely calibrated x-ray calorimeter spectrometer. FAST covers the energy range between 0.01 and 100 keV, and can thus be used to calibrate a variety of plasma diagnostics. Instrument parameters that can be calibrated include line profiles, transmission and reflection efficiencies, and the quantum efficiency of grating and crystal spectrometers and solid state detectors. FAST can be used to test fully integrated instrumentation, and is ideal for spectrometers and detectors to be flown on orbiting observatories, sounding rockets, used as ground support equipment to verify flight instrumentation, in laboratory astrophysics experiments, and to diagnose magnetic and inertial confinement fusion plasmas. Here we present an overview of the calibration capabilities of this facility including some results.

Brown, G. V.; Beiersdorfer, P.; Clementson, J.; Dunn, J.; Kelley, R. L.; Kilbourne, C. A.; Leutenegger, M.; Magee, E. W.; Park, J.; Porter, F. S.; Schneider, M.; Träbert, E.

2010-07-01

427

BOOK REVIEW: Stellarator and Heliotron Devices  

Microsoft Academic Search

Stellarators and tokamaks are the most advanced devices that have been developed for magnetic fusion applications. The two approaches have much in common; tokamaks have received the most attention because their axisymmetry justifies the use of simpler models and provides a more forgiving geometry. However, recent advances in treating more complicated three dimensional systems have made it possible to design

M. Wakatani

1999-01-01

428

Joint interpretation of geophysical data using Image Fusion techniques  

NASA Astrophysics Data System (ADS)

Joint interpretation of geophysical data produced from different methods is a challenging area of research in a wide range of applications. In this work we apply several image fusion approaches to combine maps of electrical resistivity, electromagnetic conductivity, vertical gradient of the magnetic field, magnetic susceptibility, and ground penetrating radar reflections, in order to detect archaeological relics. We utilize data gathered from Arkansas University, with the support of the U.S. Department of Defense, through the Strategic Environmental Research and Development Program (SERDP-CS1263). The area of investigation is the Army City, situated in Riley Country of Kansas, USA. The depth of the relics is estimated about 30 cm from the surface, yet the surface indications of its existence are limited. We initially register the images from the different methods to correct from random offsets due to the use of hand-held devices during the measurement procedure. Next, we apply four different image fusion approaches to create combined images, using fusion with mean values, wavelet decomposition, curvelet transform, and curvelet transform enhancing the images along specific angles. We create seven combinations of pairs between the available geophysical datasets. The combinations are such that for every pair at least one high-resolution method (resistivity or magnetic gradiometry) is included. Our results indicate that in almost every case the method of mean values produces satisfactory fused images that corporate the majority of the features of the initial images. However, the contrast of the final image is reduced, and in some cases the averaging process nearly eliminated features that are fade in the original images. Wavelet based fusion outputs also good results, providing additional control in selecting the feature wavelength. Curvelet based fusion is proved the most effective method in most of the cases. The ability of curvelet domain to unfold the image in terms of space, wavenumber, and orientation, provides important advantages compared with the rest of the methods by allowing the incorporation of a-priori information about the orientation of the potential targets.

Karamitrou, A.; Tsokas, G.; Petrou, M.

2013-12-01

429

Mechanisms of tissue fusion during development  

PubMed Central

Tissue fusion events during embryonic development are crucial for the correct formation and function of many organs and tissues, including the heart, neural tube, eyes, face and body wall. During tissue fusion, two opposing tissue components approach one another and integrate to form a continuous tissue; disruption of this process leads to a variety of human birth defects. Genetic studies, together with recent advances in the ability to culture developing tissues, have greatly enriched our knowledge of the mechanisms involved in tissue fusion. This review aims to bring together what is currently known about tissue fusion in several developing mammalian organs and highlights some of the questions that remain to be addressed. PMID:22510983

Ray, Heather J.; Niswander, Lee

2012-01-01

430

Fusion in the Sun!  

NSDL National Science Digital Library

This simulation illustrates the general conditions necessary to begin fusion in the sun and other stars. You can vary the amount of hydrogen and the temperature in order to start a reaction. Click the "Instructions" button in the top right hand corner for more information on fusion and what the simulation shows. Java is required to use this applet.

Scharein, Rob

2010-03-31

431

Image fusion across bands  

Microsoft Academic Search

The goal of image fusion is to integrate complementary information from multisensor data such that the new image is more suitable for the purpose of human perception and computer processing tasks such as segmentation, feature extraction and object recognition. In this paper, we present an image fusion technique using the concept of information across the bands. This algorithm is relevant

Mohd. Shahid; S. Gupta

2005-01-01

432

Status of Fusion Technology.  

National Technical Information Service (NTIS)

The current status of fusion technology is surveyed. Limited reserves of fossil fuel and dangers of proliferation from nuclear reactors have brought into focus the need to develop an optional energy source. Fusion is being looked upon as an optional energ...

A. Mohan

1978-01-01

433

Advances in Multi-Sensor Data Fusion: Algorithms and Applications  

PubMed Central

With the development of satellite and remote sensing techniques, more and more image data from airborne/satellite sensors have become available. Multi-sensor image fusion seeks to combine information from different images to obtain more inferences than can be derived from a single sensor. In image-based application fields, image fusion has emerged as a promising research area since the end of the last century. The paper presents an overview of recent advances in multi-sensor satellite image fusion. Firstly, the most popular existing fusion algorithms are introduced, with emphasis on their recent improvements. Advances in main applications fields in remote sensing, including object identification, classification, change detection and maneuvering targets tracking, are described. Both advantages and limitations of those applications are then discussed. Recommendations are addressed, including: (1) Improvements of fusion algorithms; (2) Development of “algorithm fusion” methods; (3) Establishment of an automatic quality assessment scheme. PMID:22408479

Dong, Jiang; Zhuang, Dafang; Huang, Yaohuan; Fu, Jingying

2009-01-01

434

Advances in multi-sensor data fusion: algorithms and applications.  

PubMed

With the development of satellite and remote sensing techniques, more and more image data from airborne/satellite sensors have become available. Multi-sensor image fusion seeks to combine information from different images to obtain more inferences than can be derived from a single sensor. In image-based application fields, image fusion has emerged as a promising research area since the end of the last century. The paper presents an overview of recent advances in multi-sensor satellite image fusion. Firstly, the most popular existing fusion algorithms are introduced, with emphasis on their recent improvements. Advances in main applications fields in remote sensing, including object identification, classification, change detection and maneuvering targets tracking, are described. Both advantages and limitations of those applications are then discussed. Recommendations are addressed, including: (1) Improvements of fusion algorithms; (2) Development of "algorithm fusion" methods; (3) Establishment of an automatic quality assessment scheme. PMID:22408479

Dong, Jiang; Zhuang, Dafang; Huang, Yaohuan; Fu, Jingying

2009-01-01

435

Visual programming environment for multisensor data fusion  

NASA Astrophysics Data System (ADS)

In recent years, numerous multisensor data fusion systems have been developed for a wide variety of applications. Defense related applications include; automatic target recognition systems, identification-friend-foe-neutral, automated situation assessment and threat assessment systems, and systems for smart weapons. Non-defense applications include; robotics, condition-based maintenance, environmental monitoring, and medical diagnostics. For each of these applications, multiple sensor data are combined to achieve inferences which are not generally possible using only a single sensor. Implementation of these data fusion systems often involves a significant amount of effort. In particular, software must be developed for components such as data base access, human computer interfaces and displays, communication software, and data fusion algorithms. While commercial software packages exist to assist development of data bases, communications, and human computer interfaces, there are no general purpose packages available to support the implementation of the data fusion algorithms. This paper describes a visual programming tool developed to assist in rapid prototyping of data fusion systems. This toolkit is modeled after the popular tool, Khoros, used by the image processing community. The tool described here is written in visual C, and provides the capability to rapidly implement and apply data fusion algorithms. An application to condition based maintenance is described.

Hall, David L.; Kasmala, Gerald

1996-06-01

436

Heavy ion fusion: Prospects and status  

SciTech Connect

The main purpose of this talk is to review the status of HIF as it was presented at Princeton, and also to try to deduce something about the prospects for HIF in particular, and fusion in general, from the world and US political scene. The status of the field is largely, though not entirely, expressed through presentations from the two leading HIF efforts: (1) the US program, centered at LBNL and LLNL, is primarily concerned with applying induction linac technology for HIF drivers; (2) the European program, centered at GSI, Darmstadt, but including several other laboratories, is primarily directed towards the rf linac approach using storage rings for energy compression. Several developments in the field of HIF should be noted: (1) progress towards construction of the National Ignition Facility (NIF) gives strength to the whole rational for developing a driver for Inertial Fusion Energy; (2) the field of accelerator science has matured far beyond the status that it had in 1976; (3) Heavy Ion Fusion has passed some more reviews, including one by the Fusion Energy Advisory Committee (FEAC), and has received the usual good marks; (5) as the budgets for Magnetic Fusion have fallen, the pressures on the Office of Fusion energy (OFE) have intensified, and a move is underway to shift the HIF program out of the IFE program and back into the ICF program in the Defense Programs (DP) side of the DOE.

Herrmannsfeldt, W.B.

1995-10-01

437

78 FR 60291 - Investigational Device Exemptions for Early Feasibility Medical Device Clinical Studies...  

Federal Register 2010, 2011, 2012, 2013

...Exemptions for Early Feasibility Medical Device Clinical Studies, Including Certain First...facilitate early feasibility studies of medical devices, using appropriate...practices for investigational medical device studies. Concurrent with the...

2013-10-01

438

75 FR 14170 - Medical Device Epidemiology Network: Developing Partnership Between the Center for Devices and...  

Federal Register 2010, 2011, 2012, 2013

...the methodology of studies for medical device performance...the performance of medical devices (including...comparative effectiveness studies). The centers participating...with an interest in medical device outcome and epidemiologic study methodology....

2010-03-24

439

Including Jews in Multiculturalism.  

ERIC Educational Resources Information Center

Discusses reasons for the lack of attention to Jews as an ethnic minority within multiculturalism both by Jews and non-Jews; why Jews and Jewish issues need to be included; and addresses some of the issues involved in the ethical treatment of Jewish clients. (Author)

Langman, Peter F.

1995-01-01

440

Wisconsin #include gcc  

E-print Network

above #include gcc ... ­lposix4 int sem_init(sem_t *sem, int pshared, unsigned int initial_value); initialize a semaphore (does not allocate memory) int sem_destroy(sem_t *sem); destroy a semaphore's state (does not free allocated memory) int sem_post(sem_t *sem); do an ``up'' or a ``V'' operation

Liblit, Ben

441

Controlled fusion of synthetic lipid membrane vesicles.  

PubMed

Lipid membrane fusion is a fundamental noncovalent transformation as well as a central process in biology. The complex and highly controlled biological machinery of fusion has been the subject of intense investigation. In contrast, fewer synthetic approaches that demonstrate selective membrane fusion have been developed. Artificial recapitulation of membrane fusion is an informative pursuit in that fundamental biophysical concepts of biomembrane merger may be generally tested in a controlled reductionist system. A key concept that has emerged from extensive studies on lipid biophysics and biological membrane fusion is that selective membrane fusion derives from the coupling of surface recognition with local membrane disruption, or strain. These observations from native systems have guided the development of de novo-designed biomimetic membrane fusion systems that have unequivocally established the generality of these concepts in noncovalent chemistry. In this Account, we discuss the function and limitations of the artificial membrane fusion systems that have been constructed to date and the insights gained from their study by our group and others. Overall, the synthetic systems are highly reductionist and chemically selective, though there remain aspects of membrane fusion that are not sufficiently understood to permit designed function. In particular, membrane fusion with efficient retention of vesicular contents within the membrane-bound compartments remains a challenge. We discuss examples in which lipid mixing and some degree of vesicle-contents mixing is achieved, but the determinants of aqueous-compartment mixing remain unclear and therefore are difficult to generally implement. The ability to fully design membrane fusogenic function requires a deeper understanding of the biophysical underpinnings of membrane fusion, which has not yet been achieved. Thus, it is critical that biological and synthetic studies continue to further elucidate this biologically important process. Examination of lipid membrane fusion from a synthetic perspective can also reveal the governing noncovalent principles that drive chemically determined release and controlled mixing within nanometer-scale compartments. These are processes that figure prominently in numerous biotechnological and chemical applications. A rough guide to the construction of a functional membrane fusion system may already be assembled from the existing studies: surface-directed membrane apposition may generally be elaborated into selective fusion by coupling to a membrane-disruptive element, as observed over a range of systems that include small-molecule, DNA, or peptide fusogens. Membrane disruption may take different forms, and we briefly describe our investigation of the sequence determinants of fusion and lysis in membrane-active viral fusion peptide variants. These findings set the stage for further investigation of the critical elements that enable efficient, fully functional fusion of both membrane and aqueous compartments and the application of these principles to unite synthetic and biological membranes in a directed fashion. Controlled fusion of artificial and living membranes remains a chemical challenge that is biomimetic of native chemical transport and has a direct impact on drug delivery approaches. PMID:23879805

Ma, Mingming; Bong, Dennis

2013-12-17

442

Solid State Devices: Course Materials  

NSDL National Science Digital Library

This course provided by eSyst describes solid state devices. An introduction explains the traditional view and systems view of this topic. The course includes numerous instructor presentations and student guides. Topics for these include power amplifier class comparison, device pathology, and the role of devices. A detailed course outline, student learning outcomes, and links to additional online resources are also provided. Users must create a free, quick login in order to download the materials.

2012-06-27

443

Fusion excitation function revisited  

E-print Network

We report on a comprehensive systematics of fusion-evaporation and/or fusion-fission cross sections for a very large variety of systems over an energy range 4-155 A.MeV. Scaled by the reaction cross sections, fusion cross sections do not show a universal behavior valid for all systems although a high degree of correlation is present when data are ordered by the system mass asymmetry.For the rather light and close to mass-symmetric systems the main characteristics of the complete and incomplete fusion excitation functions can be precisely determined. Despite an evident lack of data above 15A.MeV for all heavy systems the available data suggests that geometrical effects could explain the persistence of incomplete fusion at incident energies as high as 155A.MeV.

Ph. Eudes; Z. Basrak; F. Sébille; V. de la Mota; G. Royer; M. Zori?

2012-09-07

444

FUSION NUCLEAR SCIENCE FACILITY (FNSF) BEFORE UPGRADE TO COMPONENT TEST FACILITY (CTF)  

SciTech Connect

The compact (R0~1.2-1.3m) Fusion Nuclear Science Facility (FNSF) is aimed at providing a fully integrated, continuously driven fusion nuclear environment of copious fusion neutrons. This facility would be used to test, discover, and understand the complex challenges of fusion plasma material interactions, nuclear material interactions, tritium fuel management, and power extraction. Such a facility properly designed would provide, initially at the JET-level plasma pressure (~30%T2) and conditions (e.g., Hot-Ion H-Mode, Q<1)), an outboard fusion neutron flux of 0.25 MW/m2 while requiring a fusion power of ~19 MW. If and when this research is successful, its performance can be extended to 1 MW/m2 and ~76 MW by reaching for twice the JET plasma pressure and Q. High-safety factor q and moderate-plasmas are used to minimize or eliminate plasma-induced disruptions, to deliver reliably a neutron fluence of 1 MW-yr/m2 and a duty factor of 10% presently anticipated for the FNS research. Success of this research will depend on achieving time-efficient installation and replacement of all internal components using remote handling (RH). This in turn requires modular designs for the internal components, including the single-turn toroidal field coil center-post. These device goals would further dictate placement of support structures and vacuum weld seals behind the internal and shielding components. If these goals could be achieved, the FNSF would further provide a ready upgrade path to the Component Test Facility (CTF), which would aim to test, for 6 MW-yr/m2 and 30% duty cycle, the demanding fusion nuclear engineering and technologies for DEMO. This FNSF-CTF would thereby complement the ITER Program, and support and help mitigate the risks of an aggressive world fusion DEMO R&D Program. The key physics and technology research needed in the next decade to manage the potential risks of this FNSF are identified.

Peng, Yueng Kay Martin [ORNL; Canik, John [ORNL; Diem, Stephanie J [ORNL; Milora, Stanley L [ORNL; Park, J. M. [Oak Ridge National Laboratory (ORNL); Sontag, Aaron C [ORNL; Fogarty, P. J. [Oak Ridge National Laboratory (ORNL); Lumsdaine, Arnold [ORNL; Murakami, Masanori [ORNL; Burgess, Thomas W [ORNL; Cole, Michael J [ORNL; Katoh, Yutai [ORNL; Korsah, Kofi [ORNL; Patton, Bradley D [ORNL; Wagner, John C [ORNL; Yoder, III, Graydon L [ORNL

2011-01-01

445

Fusion Nuclear Science Facility (FNSF) before Upgrade to Component Test Facility (CTF)  

SciTech Connect

The compact (R0~1.2-1.3m) Fusion Nuclear Science Facility (FNSF) is aimed at providing a fully integrated, continuously driven fusion nuclear environment of copious fusion neutrons. This facility would be used to test, discover, understand, and innovate scientific and technical solutions for the challenges facing DEMO, by addressing the multi-scale synergistic interactions involving fusion plasma material interactions, tritium fuel cycle, power extraction, and the nuclear effects on materials. Such a facility properly designed would provide, initially at the JET-level plasma pressure (~30%T2) and conditions (e.g., Hot-Ion H-Mode), an outboard fusion neutron flux of 0.25 MW/m2 while requiring a fusion power of 19 MW. If and when this research operation is successful, its performance can be extended to 1 MW/m2 and 76 MW by reaching for twice the JET plasma pressure and Q. High-safety factor q and moderate- plasmas would minimize plasma-induced disruptions, helping to deliver reliably a neutron fluence of 1 MW-yr/m2 and a duty factor of 10% presently anticipated for the FNS research. Success of this research will depend on achieving time-efficient installation and replacement of all components using extensive remote handling (RH). This in turn requires modular designs for all internal components, including the single-turn toroidal field coil center-post with RH-compatible bi-directional sliding joints. Such device goals would further dictate placement of support structures and vacuum seal welds behind the internal and shielding components. If these further goals could be achieved, the FNSF would provide a ready upgrade path to the Component Test Facility (CTF), which would aim to test, at higher neutron fluence and duty cycle, the demanding fusion nuclear engineering and technologies for DEMO. This FNSF-CTF strategy would be complementary to the ITER and the Broader Approach programs, and thereby help mitigate the risks of an aggressive world fusion DEMO R&D Program. The key physics and technology research needed in the next decade to manage the potential risks of this FNSF are identified.

Peng, Yueng Kay Martin [ORNL] [ORNL

2010-01-01

446

Assessing the performance of multisensor fusion systems  

NASA Astrophysics Data System (ADS)

In recent years, numerous prototypical systems have been developed for multisensor data fusion. A typical data fusion process operates on sensor parametric data (e.g., data related to target position or attribute data) in order to develop an order of battle, provide an evaluation of tactical situations, or assess tactical threats. This model, developed by the Data Fusion Sub- panel (DFS) of the Joint Directors of Laboratories, partitions fusion processing into four conceptual levels. Ancillary functions in a fusion system include the human computer interface, data base management, source-preprocessing functions, and communications. Military applications for data fusion span a broad range including fusion of data on board a single platform for identifying other platforms (e.g., identification--friend or foe--neutral systems), threat warning systems, situation assessment, and threat assessment systems. Large scale systems such as the All-Source Analysis System (ASAS) or the Joint Surveillance, Targeting, and Reconnaissance System (JSTARS) provide for direction, coordination, and fusion of both ground-based and airborne sensors to aid in the effective management of a ground based battlefield environment. Such systems have become ever more sophisticated. Indeed, many of the prototypical systems utilize advanced identification techniques such as knowledge-based or expert systems. Dempster-Shafer interface techniques, adaptive neural networks, and sophisticated tracking algorithms. While much research is being performed to develop and apply new algorithms and techniques, little work has been performed to determine how well such methods work or to compare alternative methods against a common problem. The issues of system performance and system effectiveness are keys to establishing how well an algorithm, technique, or collection of techniques perform, and then the extent to which these techniques may be used to achieve success on an operational mission.

Llinas, James

1992-04-01

447

Barriers to medical device innovation  

PubMed Central

The US Food and Drug Administration (FDA) has defined a medical device as a health care product that does not achieve it’s purpose by chemical action or by being metabolized. This means that a vast number of products are considered medical devices. Such devices play an essential role in the practice of medicine. The FDA classifies medical devices in three classes, depending on the risk of the device. Since Class I and II devices</