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1

Magnetic Confinement Fusion Science Status and Challenges  

E-Print Network (OSTI)

Magnetic Confinement Fusion Science Status and Challenges S. Prager University of Wisconsin February, 2005 #12;Two approaches to fusion Inertial confinement extremely dense, short-lived Magnetic ·Control plasma disruptions ·Develop new magnetic configurations ·Control the plasma-wall interaction

2

Magnetic confinement of fusion plasmas  

Science Journals Connector (OSTI)

Starting with the Lorentz force law the basic physics involved in magnetic confinement in thermonuclear reactors is reviewed. Among the topics covered are magnetic bottles tokamaks tandem mirrors and energy balance considerations.(AIP)

George Patrick Lasche

1981-01-01T23:59:59.000Z

3

Magnetic-compression/magnetized-target fusion (MAGO/MTF): A marriage of inertial and magnetic confinement  

SciTech Connect

Intermediate between magnetic confinement (MFE) and inertial confinement (ICF) in time and density scales is an area of research now known in the US as magnetized target fusion (MTF) and in Russian as MAGO (MAGnitnoye Obzhatiye--magnetic compression). MAGO/MTF uses a magnetic field and preheated, wall-confined plasma fusion fuel within an implodable fusion target. The magnetic field suppresses thermal conduction losses in the fuel during the target implosion and hydrodynamic compression heating process. In contrast to direct, hydrodynamic compression of initially ambient-temperature fuel (i.e., ICF), MAGO/MTF involves two steps: (a) formation of a warm (e.g., 100 eV or higher), magnetized (e.g., 100 kG) plasma within a fusion target prior to implosion; (b) subsequent quasi-adiabatic compression by an imploding pusher, of which a magnetically driven imploding liner is one example. In this paper, the authors present ongoing activities and potential future activities in this relatively unexplored area of controlled thermonuclear fusion.

Lindemuth, I.R.; Ekdahl, C.A.; Kirkpatrick, R.C. [and others

1996-12-31T23:59:59.000Z

4

Passive Spectroscopic Diagnostics for Magnetically-confined Fusion Plasmas  

SciTech Connect

Spectroscopy of radiation emitted by impurities and hydrogen isotopes plays an important role in the study of magnetically-confined fusion plasmas, both in determining the effects of impurities on plasma behavior and in measurements of plasma parameters such as electron and ion temperatures and densities, particle transport, and particle influx rates. This paper reviews spectroscopic diagnostics of plasma radiation that are excited by collisional processes in the plasma, which are termed 'passive' spectroscopic diagnostics to distinguish them from 'active' spectroscopic diagnostics involving injected particle and laser beams. A brief overview of the ionization balance in hot plasmas and the relevant line and continuum radiation excitation mechanisms is given. Instrumentation in the soft X-ray, vacuum ultraviolet, ultraviolet, visible, and near-infrared regions of the spectrum is described and examples of measurements are given. Paths for further development of these measurements and issues for their implementation in a burning plasma environment are discussed.

B.C. Stratton, M. Bitter, K.W. Hill, D.L. Hillis, and J.T. Hogan

2007-07-18T23:59:59.000Z

5

Plasma-materials interactions and impurity control in magnetically confined thermonuclear fusion machines  

Science Journals Connector (OSTI)

Progress achieved in plasma heating and magnetic confinement during the past decade has brought to the fore a number of problems which have to be solved if controlled thermonuclear fusion is to become an economic...

Dieter M. Gruen; Stanislav Vep?ek; Randy B. Wright

1980-01-01T23:59:59.000Z

6

The roadmap to magnetic confinement fusion Cutaway of the ITER tokamak. ( ITER)  

E-Print Network (OSTI)

The roadmap to magnetic confinement fusion Cutaway of the ITER tokamak. (© ITER) There are two ways "tokamak" configuration invented by Tamm and Sakharov in 1950 and declassified in 1957 [1] . Over 198 tokamaks have been built [2] . Four large tokamak projects were built in the 1980s. Two of these

Hampshire, Damian

7

Atomic Collision Processes in Magnetic Confinement Controlled Thermonuclear Fusion Research  

Science Journals Connector (OSTI)

This NATO Advanced Study Institute is concerned with atomic and molecular processes in controlled thermonuclear fusion research. Most of our attention will be ... and planned tokamaks, since this approach to fusion

M. R. C. McDowell

1980-01-01T23:59:59.000Z

8

Bifurcation theory for the L-H transition in magnetically confined fusion plasmas  

SciTech Connect

The mathematical field of bifurcation theory is extended to be applicable to 1-dimensionally resolved systems of nonlinear partial differential equations, aimed at the determination of a certain specific bifurcation. This extension is needed to be able to properly analyze the bifurcations of the radial transport in magnetically confined fusion plasmas. This is of special interest when describing the transition from the low-energy-confinement state to the high-energy-confinement state of the radial transport in fusion plasmas (i.e., the L-H transition), because the nonlinear dynamical behavior during the transition corresponds to the dynamical behavior of a system containing such a specific bifurcation. This bifurcation determines how the three types (sharp, smooth, and oscillating) of observed L-H transitions are organized as function of all the parameters contained in the model.

Weymiens, W.; Blank, H. J. de; Hogeweij, G. M. D.; Valenca, J. C. de [FOM Institute DIFFER-Dutch Institute for Fundamental Energy Research, Association EURATOM-FOM, Trilateral Euregio Cluster, P.O. Box 1207, Nieuwegein (Netherlands)

2012-07-15T23:59:59.000Z

9

The mitigating effect of magnetic fields on Rayleigh-Taylor unstable inertial confinement fusion plasmas  

SciTech Connect

Rayleigh-Taylor (RT) instabilities at interfaces of disparate mass densities have long been known to generate magnetic fields during inertial confinement fusion implosions. An externally applied magnetic field can also be efficiently amplified by RT instabilities. The focus here is on magnetic field generation and amplification at the gas-ice interface which is RT unstable during the deceleration phase of the implosion. RT instabilities lead to undesirable mix of hot and cold plasmas which enhances thermal energy loss and tends to produce a more massive warm-spot instead of a hot-spot. Two mechanisms are shown here to mitigate the thermal energy loss from the hot-spot. The first mechanism is the reduction of electron thermal conductivity with interface-aligned magnetic fields. This can occur through self-generated magnetic fields via the Biermann battery effect as well as through externally applied magnetic fields that undergo an exponential growth via the stretch-and-fold magnetohydrodynamic dynamo. Self-generated magnetic fields during RT evolution can result in a factor of 2?10 decrease in the electron thermal conductivity at the gas-ice interface, while externally applied magnetic fields that are compressed to 61000 T at the onset of deceleration (corresponding to pre-implosion external fields of 0.0610 T) could result in a factor of 2500 reduction in electron thermal conductivity at the gas-ice interface. The second mechanism to mitigate thermal energy loss from the hot-spot is to decrease the interface mixing area between the hot and cold plasmas. This is achieved through large external magnetic fields of 1000 T at the onset of deceleration which damp short-wavelength RT modes and long-wavelength Kelvin-Helmholtz modes thus significantly slowing the RT growth and reducing mix.

Srinivasan, Bhuvana; Tang, Xian-Zhu [Theoretical Division, Los Alamos National Laboratory, Los Alamos, New Mexico 87545 (United States)] [Theoretical Division, Los Alamos National Laboratory, Los Alamos, New Mexico 87545 (United States)

2013-05-15T23:59:59.000Z

10

Evidence for a new path to the self-sustainment of thermonuclear fusion in magnetically confined plasmas  

Science Journals Connector (OSTI)

In this work we provide the first explanation for observations made in 1997 on the Joint European Torus of unexpected ion heating with fusion-born alpha particles occurring over time scales much shorter than those theoretically foreseen. We demonstrate that non-thermal alpha particles above a critical concentration stabilize ion-drift-wave turbulence, therefore significantly reducing one of the main energy loss channels for thermal ions. As such ion heating occurs over times scales much shorter than those classically predicted, this mechanism opens new prospects on additional paths for the self-sustainment of thermonuclear fusion reactions in magnetically confined plasmas.

D. Testa; M. Albergante

2012-01-01T23:59:59.000Z

11

Elliptical magnetic mirror generated via resistivity gradients for fast ignition inertial confinement fusion  

SciTech Connect

The elliptical magnetic mirror scheme for guiding fast electrons for Fast Ignition proposed by Schmitz et al. (Plasma Phys. Controlled Fusion 54, 085016 (2012)) is studied for conditions on the multi-kJ scale which are much closer to full-scale Fast Ignition. When scaled up, the elliptical mirror scheme is still highly beneficial to Fast Ignition. An increase in the coupling efficiency by a factor of 34 is found over a wide range of fast electron divergence half-angles.

Robinson, A. P. L.; Schmitz, H. [Central Laser Facility, STFC Rutherford-Appleton Laboratory, Didcot OX11 0QX (United Kingdom)] [Central Laser Facility, STFC Rutherford-Appleton Laboratory, Didcot OX11 0QX (United Kingdom)

2013-06-15T23:59:59.000Z

12

LDRD final report on confinement of cluster fusion plasmas with magnetic fields.  

SciTech Connect

Two versions of a current driver for single-turn, single-use 1-cm diameter magnetic field coils have been built and tested at the Sandia National Laboratories for use with cluster fusion experiments at the University of Texas in Austin. These coils are used to provide axial magnetic fields to slow radial loss of electrons from laser-produced deuterium plasmas. Typical peak field strength achievable for the two-capacitor system is 50 T, and 200 T for the ten-capacitor system. Current rise time for both systems is about 1.7 {mu}s, with peak current of 500 kA and 2 MA, respectively. Because the coil must be brought to the laser, the driver needs to be portable and drive currents in vacuum. The drivers are complete but laser-plasma experiments are still in progress. Therefore, in this report, we focus on system design, initial tests, and performance characteristics of the two-capacitor and ten-capacitors systems. The questions of whether a 200 T magnetic field can retard the breakup of a cluster-fusion plasma, and whether this field can enhance neutron production have not yet been answered. However, tools have been developed that will enable producing the magnetic fields needed to answer these questions. These are a two-capacitor, 400-kA system that was delivered to the University of Texas in 2010, and a 2-MA ten-capacitor system delivered this year. The first system allowed initial testing, and the second system will be able to produce the 200 T magnetic fields needed for cluster fusion experiments with a petawatt laser. The prototype 400-kA magnetic field driver system was designed and built to test the design concept for the system, and to verify that a portable driver system could be built that delivers current to a magnetic field coil in vacuum. This system was built copying a design from a fixed-facility, high-field machine at LANL, but made to be portable and to use a Z-machine-like vacuum insulator and vacuum transmission line. This system was sent to the University of Texas in Austin where magnetic fields up to 50 T have been produced in vacuum. Peak charge voltage and current for this system have been 100 kV and 490 kA. It was used this last year to verify injection of deuterium and surrogate clusters into these small, single-turn coils without shorting the coil. Initial test confirmed the need to insulate the inner surface of the coil, which requires that the clusters must be injected through small holes in an insulator. Tests with a low power laser confirmed that it is possible to inject clusters into the magnetic field coils through these holes without destroying the clusters. The university team also learned the necessity of maintaining good vacuum to avoid insulator, transmission line, and coil shorting. A 200-T, 2 MA system was also constructed using the experience from the first design to make the pulsed-power system more robust. This machine is a copy of the prototype design, but with ten 100-kV capacitors versus the two used in the prototype. It has additional inductance in the switch/capacitor unit to avoid breakdown seen in the prototype design. It also has slightly more inductance at the cable connection to the vacuum chamber. With this design we have been able to demonstrate 1 MA current into a 1 cm diameter coil with the vacuum chamber at air pressure. Circuit code simulations, including the additional inductance with the new design, agree well with the measured current at a charge voltage of 40 kV with a short circuit load, and at 50 kV with a coil. The code also predicts that with a charge voltage of 97 kV we will be able to get 2 MA into a 1 cm diameter coil, which will be sufficient for 200 T fields. Smaller diameter or multiple-turn coils will be able to achieve even higher fields, or be able to achieve 200-T fields with lower charge voltage. Work is now proceeding at the university under separate funding to verify operation at the 2-MA level, and to address issues of debris mitigation, measurement of the magnetic field, and operation in vacuum. We anticipate operation at full current with single

Argo, Jeffrey W.; Kellogg, Jeffrey W.; Headley, Daniel Ignacio; Stoltzfus, Brian Scott; Waugh, Caleb J.; Lewis, Sean M.; Porter, John Larry, Jr.; Wisher, Matthew; Struve, Kenneth William; Savage, Mark Edward; Quevedo, Hernan J.; Bengtson, Roger

2011-11-01T23:59:59.000Z

13

An important challenge in magnetic fusion research is to obtain high energy confinement in a stationary plasma that will be co  

NLE Websites -- All DOE Office Websites (Extended Search)

Ways to reduce your tokamak heating bill: Gaining control of edge transport Ways to reduce your tokamak heating bill: Gaining control of edge transport barriers on Alcator C-Mod A crucial challenge in magnetic fusion is to obtain high energy confinement in a stationary plasma that is compatible with the engineering requirements of a fusion reactor. The triggering of edge transport barriers at the boundary of confined plasma is a common approach to obtaining high energy confinement, in a regime known as H-mode, which extrapolates to high performance in ITER and other burning plasma devices. However, barriers to energy transport can sometimes be self-defeating, since they also provide a strong barrier to particle transport. This can lead to enhanced confinement of impurities in the plasma core, excessive radiated power and deterioration of performance for a given

14

Performance test of personal RF monitor for area monitoring at magnetic confinement fusion facility  

Science Journals Connector (OSTI)

......fusion test facilities. INTRODUCTION For the realisation of a nuclear fusion reactor, high-temperature, high-density plasma must...range Up to 1 GHz Impedance 50 omega10 % Maximum allowable input power 200 W Uniformity of electric field distribution 4 dB......

Masahiro Tanaka; Tatsuhiko Uda; Jianqing Wang; Osamu Fujiwara

2012-02-01T23:59:59.000Z

16

Method and system to directly produce electrical power within the lithium blanket region of a magnetically confined, deuterium-tritium (DT) fueled, thermonuclear fusion reactor  

DOE Patents (OSTI)

A method for integrating liquid metal magnetohydrodynamic power generation with fusion blanket technology to produce electrical power from a thermonuclear fusion reactor located within a confining magnetic field and within a toroidal structure. A hot liquid metal flows from a liquid metal blanket region into a pump duct of an electromagnetic pump which moves the liquid metal to a mixer where a gas of predetermined pressure is mixed with the pressurized liquid metal to form a Froth mixture. Electrical power is generated by flowing the Froth mixture between electrodes in a generator duct. When the Froth mixture exits the generator the gas is separated from the liquid metal and both are recycled.

Woolley, Robert D. (Belle Mead, NJ)

1999-01-01T23:59:59.000Z

17

Multishell inertial confinement fusion target  

DOE Patents (OSTI)

A method of fabricating multishell fuel targets for inertial confinement fusion usage. Sacrificial hemispherical molds encapsulate a concentric fuel pellet which is positioned by fiber nets stretched tautly across each hemispherical mold section. The fiber ends of the net protrude outwardly beyond the mold surfaces. The joint between the sacrificial hemispheres is smoothed. A ceramic or glass cover is then deposited about the finished mold surfaces to produce an inner spherical surface having continuously smooth surface configuration. The sacrificial mold is removed by gaseous reaction accomplished through the porous ceramic cover prior to enclosing of the outer sphere by addition of an outer coating. The multishell target comprises the inner fuel pellet concentrically arranged within a surrounding coated cover or shell by fiber nets imbedded within the cover material.

Holland, James R. (Butler, PA); Del Vecchio, Robert M. (Vandergrift, PA)

1984-01-01T23:59:59.000Z

18

Multishell inertial confinement fusion target  

DOE Patents (OSTI)

A method of fabricating multishell fuel targets for inertial confinement fusion usage. Sacrificial hemispherical molds encapsulate a concentric fuel pellet which is positioned by fiber nets stretched tautly across each hemispherical mold section. The fiber ends of the net protrude outwardly beyond the mold surfaces. The joint between the sacrificial hemispheres is smoothed. A ceramic or glass cover is then deposited about the finished mold surfaces to produce an inner spherical surface having continuously smooth surface configuration. The sacrificial mold is removed by gaseous reactions accomplished through the porous ceramic cover prior to enclosing of the outer sphere by addition of an outer coating. The multishell target comprises the inner fuel pellet concentrically arranged within a surrounding coated cover or shell by fiber nets imbedded within the cover material.

Holland, James R. (Butler, PA); Del Vecchio, Robert M. (Vandergrift, PA)

1987-01-01T23:59:59.000Z

19

Neutron imaging with bubble chambers for inertial confinement fusion.  

E-Print Network (OSTI)

??One of the main methods to obtain energy from controlled thermonuclear fusion is inertial confinement fusion (ICF), a process where nuclear fusion reactions are initiated (more)

Ghilea, Marian Constantin (1973 - ); Meyerhofer, David D.

2011-01-01T23:59:59.000Z

20

Magnetically Confined Plasmas  

Science Journals Connector (OSTI)

The propagation of high-velocity shock waves in an axial magnetic field generated by single-turn coils connected in parallel to a condenser bank is investigated. Time-resolved photographs show that the plasma behind the shock front is driven away from the tube walls by the magnetic pressure. This compression heats the ionized gas and maintains a high shock velocity during the transit of the front through the coil. The compressed plasma appears to be stable and undergoes radial oscillations that follow the current oscillations. The interpretation and significance of these observations in controlled thermonuclear fusion research are discussed.

A. C. Kolb

1958-10-15T23:59:59.000Z

Note: This page contains sample records for the topic "magnetic confinement fusion" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


21

Discovery Research in Magnetic Fusion Energy  

E-Print Network (OSTI)

magnetic tori? � Fundamental study � Confinement science, heating, sustainment, heat flux to boundariesDiscovery Research in Magnetic Fusion Energy or "How we learn about magnetic containment the shape of the magnetic field � What can we learn by changing magnetic topology? Examples... � Stellarator

Mauel, Michael E.

22

Princeton Plasma Physics Lab - Inertial confinement fusion  

NLE Websites -- All DOE Office Websites (Extended Search)

inertial-confinement-fusion An inertial-confinement-fusion An experimental process that uses lasers to compress plasma to sufficiently high temperatures and densities for fusion to occur. Such experiments are carried out in places such as the National Ignition Facility at the Lawrence Livermore National Laboratory in Livermore, California. en Fusion through the eyes of a veteran science journalist http://www.pppl.gov/news/2013/07/fusion-through-eyes-veteran-science-journalist-1

Author Daniel Clery recently published "A Piece of the Sun," a 320-page narrative of the history of fusion research and the

23

Current state of magnetic-fusion energy research  

SciTech Connect

With the improved understanding of plasma physics, progress is being made on several approaches to magnetic confinement for controlled thermonuclear fusion.

Johnson, J.L.; Weimer, K.E.

1983-02-01T23:59:59.000Z

24

Method and apparatus to produce and maintain a thick, flowing, liquid lithium first wall for toroidal magnetic confinement DT fusion reactors  

DOE Patents (OSTI)

A system for forming a thick flowing liquid metal, in this case lithium, layer on the inside wall of a toroid containing the plasma of a deuterium-tritium fusion reactor. The presence of the liquid metal layer or first wall serves to prevent neutron damage to the walls of the toroid. A poloidal current in the liquid metal layer is oriented so that it flows in the same direction as the current in a series of external magnets used to confine the plasma. This current alignment results in the liquid metal being forced against the wall of the toroid. After the liquid metal exits the toroid it is pumped to a heat extraction and power conversion device prior to being reentering the toroid.

Woolley, Robert D. (Hillsborough, NJ)

2002-01-01T23:59:59.000Z

25

Driven Reconnection in Magnetic Fusion Experiments  

E-Print Network (OSTI)

.g. Reversed Field Pinches, Stellerators, etc.). #12;toroidal field coil toroidal magnetic field lines Figure 1.e. small non-axisymmetric perturbations of the magnetic field due to coil misalignments, etc.) are a fact of life in magnetic fusion experiments. What effects do error fields have on plasma confinement? How can

Fitzpatrick, Richard

26

Simulation of transition dynamics to high confinement in fusion plasmas  

E-Print Network (OSTI)

The transition dynamics from the low (L) to the high (H) confinement mode in magnetically confined plasmas is investigated using a first-principles four-field fluid model. Numerical results are in close agreement with measurements from the Experimental Advanced Superconducting Tokamak - EAST. Particularly, the slow transition with an intermediate dithering phase is well reproduced by the numerical solutions. Additionally, the model reproduces the experimentally determined L-H transition power threshold scaling that the ion power threshold increases with increasing particle density. The results hold promise for developing predictive models of the transition, essential for understanding and optimizing future fusion power reactors.

Nielsen, A H; Madsen, J; Naulin, V; Rasmussen, J Juul; Wan, B N

2014-01-01T23:59:59.000Z

27

Office of Inertial Confinement Fusion | National Nuclear Security  

NLE Websites -- All DOE Office Websites (Extended Search)

Inertial Confinement Fusion | National Nuclear Security Inertial Confinement Fusion | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Inertial Confinement Fusion Office of Inertial Confinement Fusion Home > About Us > Our Programs > Defense Programs > Office of Research, Development, Test, and Evaluation > Office of Inertial Confinement Fusion

28

Fusion-A Potential Power Source  

Science Journals Connector (OSTI)

Fusion-A Potential Power Source ... Nuclear energy, fusion reactions, magnetic confinement, and tokamaks. ...

Torkil H. Jensen

1994-01-01T23:59:59.000Z

29

Review of implicit methods for the magnetohydrodynamic description of magnetically confined plasmas  

Science Journals Connector (OSTI)

Implicit algorithms are essential for predicting the slow growth and saturation of global instabilities in today's magnetically confined fusion plasma experiments. Present day algorithms for obtaining implicit solutions to the magnetohydrodynamic (MHD) ... Keywords: Fusion, Implicit methods, Magnetohydrodynamics, Plasma physics

S. C. Jardin

2012-02-01T23:59:59.000Z

30

High Energy Electron Confinement in a Magnetic Cusp Configuration  

E-Print Network (OSTI)

We report experimental results validating the concept that plasma confinement is enhanced in a magnetic cusp configuration when beta (plasma pressure/magnetic field pressure) is order of unity. This enhancement is required for a fusion power reactor based on cusp confinement to be feasible. The magnetic cusp configuration possesses a critical advantage: the plasma is stable to large scale perturbations. However, early work indicated that plasma loss rates in a reactor based on a cusp configuration were too large for net power production. Grad and others theorized that at high beta a sharp boundary would form between the plasma and the magnetic field, leading to substantially smaller loss rates. The current experiment validates this theoretical conjecture for the first time and represents critical progress toward the Polywell fusion concept which combines a high beta cusp configuration with an electrostatic fusion for a compact, economical, power-producing nuclear fusion reactor.

Park, Jaeyoung; Sieck, Paul E; Offermann, Dustin T; Skillicorn, Michael; Sanchez, Andrew; Davis, Kevin; Alderson, Eric; Lapenta, Giovanni

2014-01-01T23:59:59.000Z

31

Magnetically catalyzed fusion  

Science Journals Connector (OSTI)

We calculate the reaction cross sections for the fusion of hydrogen and deuterium in strong magnetic fields as are believed to exist in the atmospheres of neutron stars. We find that in the presence of a strong magnetic field (B?1012 G), the reaction rates are many orders of magnitude higher than in the unmagnetized case. The fusion of both protons and deuterons is important over a neutron stars lifetime for ultrastrong magnetic fields (B?1016 G). The enhancement may have dramatic effects on thermonuclear runaways and bursts on the surfaces of neutron stars. 1996 The American Physical Society.

Jeremy S. Heyl and Lars Hernquist

1996-11-01T23:59:59.000Z

32

Species separation in inertial confinement fusion fuels  

SciTech Connect

It is shown by means of multi-fluid particle-in-cell simulations that convergence of the spherical shock wave that propagates through the inner gas of inertial confinement fusion-relevant experiments is accompanied by a separation of deuterium (D) and tritium (T) ions across the shock front. Deuterons run ahead of the tritons due to their lower mass and higher charge-to-mass ratio and can reach the center several tens of picoseconds before the tritons. The rising edge of the DD and TT fusion rate is also temporally separated by the same amount, which should be an observable in experiments and would be a direct proof of the 'stratification conjecture' on the shock front [Amendt et al., Phys. Plasmas 18, 056308 (2011)]. Moreover, dephasing of the D and T shock components in terms of density and temperature leads to a degradation of the DT fusion yield as the converging shock first rebounds from the fuel center (shock yield). For the parameters of this study, the second peak in the fusion yield (compression yield) is strongly dependent on the choice of the flux limiter.

Bellei, C.; Amendt, P. A.; Wilks, S. C. [Lawrence Livermore National Laboratory, 7000 East Avenue, Livermore, California 94550 (United States); Haines, M. G. [Blackett Laboratory, Imperial College, London SW7 2AZ (United Kingdom); Casey, D. T. [Lawrence Livermore National Laboratory, 7000 East Avenue, Livermore, California 94550 (United States); Plasma Science and Fusion Center, Massachusetts Institute of Technology, Cambridge, Massachusetts 02139 (United States); Li, C. K.; Petrasso, R. [Plasma Science and Fusion Center, Massachusetts Institute of Technology, Cambridge, Massachusetts 02139 (United States); Welch, D. R. [Voss Scientic, Albuquerque, New Mexico 87108 (United States)

2013-01-15T23:59:59.000Z

33

Two-dimensional simulations of thermonuclear burn in ignition-scale inertial confinement fusion targets under compressed axial magnetic fields  

SciTech Connect

We report for the first time on full 2-D radiation-hydrodynamic implosion simulations that explore the impact of highly compressed imposed magnetic fields on the ignition and burn of perturbed spherical implosions of ignition-scale cryogenic capsules. Using perturbations that highly convolute the cold fuel boundary of the hotspot and prevent ignition without applied fields, we impose initial axial seed fields of 20100 T (potentially attainable using present experimental methods) that compress to greater than 4 10{sup 4} T (400 MG) under implosion, thereby relaxing hotspot areal densities and pressures required for ignition and propagating burn by ?50%. The compressed field is high enough to suppress transverse electron heat conduction, and to allow alphas to couple energy into the hotspot even when highly deformed by large low-mode amplitudes. This might permit the recovery of ignition, or at least significant alpha particle heating, in submarginal capsules that would otherwise fail because of adverse hydrodynamic instabilities.

Perkins, L. J.; Logan, B. G.; Zimmerman, G. B.; Werner, C. J. [Lawrence Livermore National Laboratory, Livermore, California 94550 (United States)] [Lawrence Livermore National Laboratory, Livermore, California 94550 (United States)

2013-07-15T23:59:59.000Z

34

Apparatus for magnetic and electrostatic confinement of plasma  

DOE Patents (OSTI)

An apparatus and method for containing plasma and forming a Field Reversed Configuration (FRC) magnetic topology are described in which plasma ions are contained magnetically in stable, non-adiabatic orbits in the FRC. Further, the electrons are contained electrostatically in a deep energy well, created by tuning an externally applied magnetic field. The simultaneous electrostatic confinement of electrons and magnetic confinement of ions avoids anomalous transport and facilitates classical containment of both electrons and ions. In this configuration, ions and electrons may have adequate density and temperature so that upon collisions ions are fused together by nuclear force, thus releasing fusion energy. Moreover, the fusion fuel plasmas that can be used with the present confinement system and method are not limited to neutronic fuels only, but also advantageously include advanced fuels.

Rostoker, Norman; Binderbauer, Michl

2013-06-11T23:59:59.000Z

35

An important challenge in magnetic fusion research is to obtain...  

NLE Websites -- All DOE Office Websites (Extended Search)

Ways to reduce your tokamak heating bill: Gaining control of edge transport barriers on Alcator C-Mod A crucial challenge in magnetic fusion is to obtain high energy confinement in...

36

Thermomagnetic burn control for magnetic fusion reactor  

DOE Patents (OSTI)

Apparatus is provided for controlling the plasma energy production rate of a magnetic-confinement fusion reactor, by controlling the magnetic field ripple. The apparatus includes a group of shield sectors (30a, 30b, etc.) formed of ferromagnetic material which has a temperature-dependent saturation magnetization, with each shield lying between the plasma (12) and a toroidal field coil (18). A mechanism (60) for controlling the temperature of the magnetic shields, as by controlling the flow of cooling water therethrough, thereby controls the saturation magnetization of the shields and therefore the amount of ripple in the magnetic field that confines the plasma, to thereby control the amount of heat loss from the plasma. This heat loss in turn determines the plasma state and thus the rate of energy production.

Rawls, John M. (Del Mar, CA); Peuron, Unto A. (Solana Beach, CA)

1982-01-01T23:59:59.000Z

37

Thermomagnetic burn control for magnetic fusion reactor  

DOE Patents (OSTI)

Apparatus is provided for controlling the plasma energy production rate of a magnetic-confinement fusion reactor, by controlling the magnetic field ripple. The apparatus includes a group of shield sectors formed of ferromagnetic material which has a temperature-dependent saturation magnetization, with each shield lying between the plasma and a toroidal field coil. A mechanism for controlling the temperature of the magnetic shields, as by controlling the flow of cooling water therethrough, thereby controls the saturation magnetization of the shields and therefore the amount of ripple in the magnetic field that confines the plasma, to thereby control the amount of heat loss from the plasma. This heat loss in turn determines the plasma state and thus the rate of energy production.

Rawls, J.M.; Peuron, A.U.

1980-07-01T23:59:59.000Z

38

Nuclear Fusion for Bose Nuclei Confined in Ion Traps  

SciTech Connect

Nuclear fusion of integer spin nuclei confined in an isotropic ion trap is investigated. Solutions of the ground state for charged bosons trapped in the isotropic harmonic oscillator potential are calculated using the equivalent linear two-body method for many-body problems, which is based on an approximate reduction of the many-body Schroedinger equation by the use of a variational principle. Using the ground-state wave function, theoretical estimates of probabilities and rates for nuclear fusion for Bose nuclei confined in ion traps are obtained. Numerical estimates for fusion rates are presented for the case of deuteron-deuteron fusion.

Kim, Yeong E.; Zubarev, Alexander L. [Purdue University (United States)

2000-03-15T23:59:59.000Z

39

Fast ignition of inertial confinement fusion targets  

SciTech Connect

Results of studies on fast ignition of inertial confinement fusion (ICF) targets are reviewed. The aspects of the fast ignition concept, which consists in the separation of the processes of target ignition and compression due to the synchronized action of different energy drivers, are considered. Criteria for the compression ratio and heating rate of a fast ignition target, the energy balance, and the thermonuclear gain are discussed. The results of experimental and theoretical studies of the heating of a compressed target by various types of igniting drivers, namely, beams of fast electrons and light ions produced under the action of a petawatt laser pulse on the target, a heavy-ion beam generated in the accelerator, an X-ray pulse, and a hydrodynamic flow of laser-accelerated matter, are analyzed. Requirements to the igniting-driver parameters that depend on the fast ignition criteria under the conditions of specific target heating mechanisms, as well as possibilities of practical implementation of these requirements, are discussed. The experimental programs of various laboratories and the prospects of practical implementation of fast ignition of ICF targets are reviewed. To date, fast ignition is the most promising method for decreasing the ignition energy and increasing the thermonuclear gain of an ICF plasma. A large number of publications have been devoted to investigations of this method and adjacent problems of the physics of igniting drivers and their interaction with plasma. This review presents results of only some of these studies that, in the author's opinion, allow one to discuss in detail the main physical aspects of the fast ignition concept and understand the current state and prospects of studies in this direction.

Gus'kov, S. Yu., E-mail: guskov@sci.lebedev.ru [Russian Academy of Sciences, Lebedev Physical Institute (Russian Federation)

2013-01-15T23:59:59.000Z

40

Inertial-confinement fusion with fast ignition  

Science Journals Connector (OSTI)

...achieve ignition and thermonuclear burn. For a fusion power plant, gains...the ratio of the thermonuclear energy to the initial...released by the thermonuclear burn in unit mass...compressed spherical fusion fuel. Higher gain...

1999-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "magnetic confinement fusion" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


41

LANL | Physics | Inertial Confinement Fusion and High Energy Density  

NLE Websites -- All DOE Office Websites (Extended Search)

Inertial confinement and high density Inertial confinement and high density plasma physics Using the world's most powerful lasers, Physics Division scientists are aiming to create thermonuclear burn in the laboratory. The experimental research of the Physics Division's Inertial Confinement Fusion program is conducted at the National Ignition Facility at Lawrence Livermore National Laboratory, the OMEGA Laser Facility at the University of Rochester, and the Trident Laser Facility at Los Alamos. Within inertial confinement fusion and the high energy density area, Los Alamos specializes in hohlraum energetics, symmetry tuning, warm dense matter physics, and hydrodynamics in ultra-extreme conditions. When complete, this research will enable the exploitation of fusion as an energy resource and will enable advanced research in stockpile stewardship

42

Inertial confinement fusion | Princeton Plasma Physics Lab  

NLE Websites -- All DOE Office Websites (Extended Search)

the Lawrence Livermore National Laboratory with the goal of igniting a propagating thermonuclear burn wave in DT fuel leading to energy gain (defined as fusion yieldinput laser...

43

Symmetry Constraints on the Dynamics of Magnetically Confined Plasma  

SciTech Connect

In respect of their symmetry properties, toroidal magnetically confined plasmas have much in common with the Taylor-Couette flow. A symmetry-based analysis (equivalent bifurction theory) has proved very powerful in the analysis of the latter problem. This Letter discusses the applicability of the method to nuclear fusion experiments such as tokamaks and pinches. The likely behavior of the simplest models of rotationally symmetric tokamaks is described, and found to be potentially consistent with observation.

Arter, Wayne [EURATOM/UKAEA Fusion Association, Culham Science Centre, Abingdon, OX14 3DB (United Kingdom)

2009-05-15T23:59:59.000Z

44

Ion Rings for Magnetic Fusion  

SciTech Connect

This Final Technical Report presents the results of the program, Ion Rings for Magnetic Fusion, which was carried out under Department of Energy funding during the period August, 1993 to January, 2005. The central objective of the program was to study the properties of field-reversed configurations formed by ion rings. In order to reach this objective, our experimental program, called the Field-reversed Ion Ring Experiment, FIREX, undertook to develop an efficient, economical technology for the production of field-reversed ion rings. A field-reversed configuration (FRC) in which the azimuthal (field-reversing) current is carried by ions with gyro-radius comparable to the magnetic separatrix radius is called a field-reversed ion ring. A background plasma is required for charge neutralization of the ring, and this plasma will be confined within the ring's closed magnetic flux. Ion rings have long been of interest as the basis of compact magnetic fusion reactors, as the basis for a high-power accelerator for an inertial fusion driver, and for other applications of high power ion beams or plasmas of high energy density. Specifically, the FIREX program was intended to address the longstanding question of the contribution of large-orbit ions to the observed stability of experimental FRCs to the MHD tilt mode. Typical experimental FRCs with s {approx} 2-4, where s is the ratio of separatrix radius to ion gyro-radius, have been stable to tilting, but desired values for a fusion reactor, s > 20, should be unstable. The FIREX ring would consist of a plasma with large s for the background ions, but with s {approx} 1 for the ring ions. By varying the proportions of these two populations, the minimum proportion of large-orbit ions necessary for stability could be determined. The incorporation of large-orbit ions, perhaps by neutral-beam injection, into an FRC has been advanced for the purpose of stabilizing, heating, controlling angular momentum, and aiding the formation of a reactor-scale FRC, and the FIREX program was intended to test the ideas behind this approach. We will describe in this report the technological development path and advances in physics understanding that allowed FIREX to reach a regime in which ion rings were reproducibly created with up to about half the current necessary to produce field reversal. Unfortunately, the experiments were limited to this level by a fundamental, unanticipated aspect of the physics of strong ion rings in plasma. The FIREX ring is a strongly anisotropic, current-carrying population of ions moving faster than the Alfven speed in the background plasma. The rapidly changing ring current excites very large-amplitude Alfven waves in the plasma, and these waves strongly affect the ring, causing rapid energy loss in a way that is not compatible with the success of the ring trapping scenario around which FIREX was designed. The result was that FIREX rings were always very short-lived. We will discuss the implication of these results for possible future use of large-orbit ions in FRCs. In short, it appears that a certain range of the parameters characterizing the ring Alfven mach number and distribution function must be avoided to allow the existence of a long-lived energetic ion component in an FRC. This report will explain why FIREX experimental results cannot be directly scaled to quantitatively predict this range for a particular FRC configuration. This will require accurate, three-dimensional simulations. FIREX results do constitute a very good dataset for validating such a code, and simulations already carried out during this program provide a guide to the important physics involved.

Greenly, John, B.

2005-07-31T23:59:59.000Z

45

Hydrodynamic stability theory of double ablation front structures in inertial confinement fusion.  

E-Print Network (OSTI)

??The aim of inertial confinement fusion is the production of energy by the fusion of thermonuclear fuel (deuterium-tritium) enclosed in a spherical target due to (more)

Yez Vico, Carlos

2012-01-01T23:59:59.000Z

46

Kilotesla Magnetic Assisted Fast Laser Ignited Boron-11 Hydrogen Fusion with Nonlinear Force Driven Ultrahigh Accelerated Plasma Blocks  

Science Journals Connector (OSTI)

Nuclear fusion with confinement by available kilotesla magnetic fields ... combination of this approach with the established ultrahigh laser acceleration of plasma blocks driven by nonlinear (ponderomotive) forc...

P. Lalousis; S. Moustaizis; H. Hora; G. H. Miley

2014-09-01T23:59:59.000Z

47

System and method for generating steady state confining current for a toroidal plasma fusion reactor  

DOE Patents (OSTI)

A system for generating steady state confining current for a toroidal plasma fusion reactor providing steady-state generation of the thermonuclear power. A dense, hot toroidal plasma is initially prepared with a confining magnetic field with toroidal and poloidal components. Continuous wave RF energy is injected into said plasma to establish a spectrum of traveling waves in the plasma, where the traveling waves have momentum components substantially either all parallel, or all anti-parallel to the confining magnetic field. The injected RF energy is phased to couple to said traveling waves with both a phase velocity component and a wave momentum component in the direction of the plasma traveling wave components. The injected RF energy has a predetermined spectrum selected so that said traveling waves couple to plasma electrons having velocities in a predetermined range .DELTA.. The velocities in the range are substantially greater than the thermal electron velocity of the plasma. In addition, the range is sufficiently broad to produce a raised plateau having width .DELTA. in the plasma electron velocity distribution so that the plateau electrons provide steady-state current to generate a poloidal magnetic field component sufficient for confining the plasma. In steady state operation of the fusion reactor, the fusion power density in the plasma exceeds the power dissipated in the plasma.

Fisch, Nathaniel J. (Cambridge, MA)

1981-01-01T23:59:59.000Z

48

System and method for generating steady state confining current for a toroidal plasma fusion reactor  

DOE Patents (OSTI)

A system for generating steady state confining current for a toroidal plasma fusion reactor providing steady-state generation of the thermonuclear power. A dense, hot toroidal plasma is initially prepared with a confining magnetic field with toroidal and poloidal components. Continuous wave RF energy is injected into said plasma to estalish a spectrum of traveling waves in the plasma, where the traveling waves have momentum components substantially either all parallel, or all anti-parallel to the confining magnetic field. The injected RF energy is phased to couple to said traveling waves with both a phase velocity component and a wave momentum component in the direction of the plasma traveling wave components. The injected RF energy has a predetermined spectrum selected so that said traveling waves couple to plasma electrons having velocities in a predetermined range .DELTA.. The velocities in the range are substantially greater than the thermal electron velocity of the plasma. In addition, the range is sufficiently broad to produce a raised plateau having width .DELTA. in the plasma electron velocity distribution so that the plateau electrons provide steady-state current to generate a poloidal magnetic field component sufficient for confining the plasma. In steady state operation of the fusion reactor, the fusion power density in the plasma exceeds the power dissipated inthe plasma.

Bers, Abraham (Arlington, MA)

1981-01-01T23:59:59.000Z

49

VISUALIZATION OF MAGNETICALLY CONFINED PLASMAS  

E-Print Network (OSTI)

developments in experimental and theoretical fu- sion energy research towards more geometric details such a source of energy is the mission of the fusion energy research community. There is presently a great, Princeton Plasma Physics Laboratory Princeton NJ 08543, USA November 30, 1999 Abstract With the rapid

50

Inertial confinement fusion method producing line source radiation fluence  

DOE Patents (OSTI)

An inertial confinement fusion method in which target pellets are imploded in sequence by laser light beams or other energy beams at an implosion site which is variable between pellet implosions along a line. The effect of the variability in position of the implosion site along a line is to distribute the radiation fluence in surrounding reactor components as a line source of radiation would do, thereby permitting the utilization of cylindrical geometry in the design of the reactor and internal components.

Rose, Ronald P. (Peters Township, Washington County, PA)

1984-01-01T23:59:59.000Z

51

tTOURflAL DE PHYSIQUE Colloque C7, suppliment au n07, Tome 40, J u i l l e t 1979, page C7-775 DIAGNOSTICSPROGRAM FOR A MAGNETICALLY INSULATED ION DIODE FOR INERTIAL CONFINEMENT FUSION  

E-Print Network (OSTI)

, Albuquerque, flew Mexico, 87185. Inertial confinement fusion (ICF) schemes 2 require an ion power density of 1 the focused proton and carbon beam profiles via induced atomic excitation and thermal emission from targets exposure times of less than five nanoseconds. The resulting electron images were transported along a 2 k

Paris-Sud XI, Université de

52

Damage production and accumulation in SiC structures in inertial and magnetic fusion systems  

E-Print Network (OSTI)

Damage production and accumulation in SiC structures in inertial and magnetic fusion systems M wall in an IFE system is $10% lower than in an MFE system, while gas production and burnup rates magnetic (MFE) and inertial (IFE) confinement fusion systems. Variations in the geometry, neutron energy

Ghoniem, Nasr M.

53

The Dipole Fusion Confinement Concept: A White Paper for the Fusion Community  

E-Print Network (OSTI)

. Bromberg MIT Plasma Science and Fusion Center Cambridge, MA 02139 M. Mauel and D. Garnier Department Angeles, CA 90024 April 6, 1998 1 Introduction The dipole magnetic field is the simplest and most common magnetic field configuration in the universe. It is the magnetic far-field of a single, circular current

54

Magnetized Target Fusion Collaboration. Final report  

SciTech Connect

Nuclear fusion has the potential to satisfy the prodigious power that the world will demand in the future, but it has yet to be harnessed as a practical energy source. The entry of fusion as a viable, competitive source of power has been stymied by the challenge of finding an economical way to provide for the confinement and heating of the plasma fuel. It is the contention here that a simpler path to fusion can be achieved by creating fusion conditions in a different regime at small scale (~ a few cm). One such program now under study, referred to as Magnetized Target Fusion (MTF), is directed at obtaining fusion in this high energy density regime by rapidly compressing a compact toroidal plasmoid commonly referred to as a Field Reversed Configuration (FRC). To make fusion practical at this smaller scale, an efficient method for compressing the FRC to fusion gain conditions is required. In one variant of MTF a conducting metal shell is imploded electrically. This radially compresses and heats the FRC plasmoid to fusion conditions. The closed magnetic field in the target plasmoid suppresses the thermal transport to the confining shell, thus lowering the imploding power needed to compress the target. The undertaking described in this report was to provide a suitable target FRC, as well as a simple and robust method for inserting and stopping the FRC within the imploding liner. The FRC must also survive during the time it takes for the metal liner to compress the FRC target. The initial work at the UW was focused on developing adequate preionization and flux trapping that were found to be essential in past experiments for obtaining the density, flux and most critically, FRC lifetime required for MTF. The timescale for testing and development of such a source can be rapidly accelerated by taking advantage of a new facility funded by the Department of Energy. At this facility, two inductive plasma accelerators (IPA) were constructed and tested. Recent experiments with these IPAs have demonstrated the ability to rapidly form, accelerate and merge two hypervelocity FRCs into a compression chamber. The resultant FRC that was formed was hot (T{sub ion} ~ 400 eV), stationary, and stable with a configuration lifetime several times that necessary for the MTF liner experiments. The accelerator length was less than 1 meter, and the time from the initiation of formation to the establishment of the final equilibrium was less than 10 microseconds. With some modification, each accelerator can be made capable of producing FRCs suitable for the production of the target plasma for the MTF liner experiment. Based on the initial FRC merging/compression results, the design and methodology for an experimental realization of the target plasma for the MTF liner experiment can now be defined. The construction and testing of the key components for the formation of the target plasma at the Air Force Research Laboratory (AFRL) will be performed on the IPA experiment, now at MSNW. A high density FRC plasmoid will be formed and accelerated out of each IPA into a merging/compression chamber similar to the imploding liner at AFRL. The properties of the resultant FRC plasma (size, temperature, density, flux, lifetime) will be obtained. The process will be optimized, and a final design for implementation at AFRL will be carried out. When implemented at AFRL it is anticipated that the colliding/merging FRCs will then be compressed by the liner. In this manner it is hoped that ultimately a plasma with ion temperatures reaching the 10 keV range and fusion gain near unity can be obtained.

John Slough

2012-04-18T23:59:59.000Z

55

Magnetic and electrostatic confinement of plasma with tuning of electrostatic field  

DOE Patents (OSTI)

A system and method for containing plasma and forming a Field Reversed Configuration (FRC) magnetic topology are described in which plasma ions are contained magnetically in stable, non-adiabatic orbits in the FRC. Further, the electrons are contained electrostatically in a deep energy well, created by tuning an externally applied magnetic field. The simultaneous electrostatic confinement of electrons and magnetic confinement of ions avoids anomalous transport and facilitates classical containment of both electrons and ions. In this configuration, ions and electrons may have adequate density and temperature so that upon collisions they are fused together by nuclear force, thus releasing fusion energy. Moreover, the fusion fuel plasmas that can be used with the present confinement system and method are not limited to neutronic fuels only, but also advantageously include advanced fuels.

Rostoker, Norman (Irvine, CA); Binderbauer, Michl (Irvine, CA); Qerushi, Artan (Irvine, CA); Tahsiri, Hooshang (Irvine, CA)

2008-10-21T23:59:59.000Z

56

Transmission Line MTF: Magnetized Target Fusion  

E-Print Network (OSTI)

Transmission Line MTF: Magnetized Target Fusion Initial target: preheated & magnetized Subsequent for the FRC. Abstract Block Diagram theta coil transmission line Bias cap. bank maincapacitor inductor PI cap compression to fusion conditions Magnetic field of at least 5 T in a closed-field line topology Density ~ 1017

57

Perspective on the Role of Negative Ions and Ion-Ion Plasmas in Heavy Ion Fusion Science, Magnetic Fusion Energy, and Related Fields  

E-Print Network (OSTI)

in Heavy Ion Fusion Science, Magnetic Fusion Energy, andin Heavy Ion Fusion Science, Magnetic Fusion Energy, and

Kwan, J.W.

2008-01-01T23:59:59.000Z

58

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

DOE Patents (OSTI)

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.

1981-10-26T23:59:59.000Z

59

System and method of operating toroidal magnetic confinement devices  

DOE Patents (OSTI)

This invention pertains to methods and arrangements for attaining high beta values in plasma confinement devices. More specifically, this invention pertains to methods for accessing the second stability region of operation in toroidal magnetic confinement devices.

Chance, M.S.; Jardin, S.C.; Stix, T.H.; Grimm, R.C.; Manickam, J.; Okabayashi, M.

1984-08-30T23:59:59.000Z

60

FPEOS: A First-Principles Equation of State Table of Deuterium for Inertial Confinement Fusion Applications  

E-Print Network (OSTI)

FPEOS: A First-Principles Equation of State Table of Deuterium for Inertial Confinement Fusion) Understanding and designing inertial confinement fusion (ICF) implosions through radiation- hydrodynamics. To minimize the drive energy for ignition, the imploding shell of DT- fuel needs to be kept as cold

Militzer, Burkhard

Note: This page contains sample records for the topic "magnetic confinement fusion" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


61

A compact neutron spectrometer for characterizing inertial confinement fusion implosions at OMEGA and the NIF  

E-Print Network (OSTI)

A compact neutron spectrometer for characterizing inertial confinement fusion implosions at OMEGA-resolution spectroscopy used to measure inertial confinement fusion neutron spectra on Omega (invited)a) Rev. Sci. Instrum. 83, 10D919 (2012); 10.1063/1.4742926 Neutron spectrometry--An essential tool for diagnosing

62

Initial experiments on the shock-ignition inertial confinement fusion concepta...  

E-Print Network (OSTI)

ignition is a concept for direct-drive laser inertial confinement fusion ICF Refs. 1­3 that was recently for conven- tional ignition to occur. Then a strong shock wave launched at the end of the laser pulseInitial experiments on the shock-ignition inertial confinement fusion concepta... W. Theobald,1,b R

63

Superconducting magnets for toroidal fusion reactors  

SciTech Connect

Fusion reactors will soon be employing superconducting magnets to confine plasma in which deuterium and tritium (D-T) are fused to produce usable energy. At present there is one small confinement experiment with superconducting toroidal field (TF) coils: Tokamak 7 (T-7), in the USSR, which operates at 4 T. By 1983, six different 2.5 x 3.5-m D-shaped coils from six manufacturers in four countries will be assembled in a toroidal array in the Large Coil Test Facility (LCTF) at Oak Ridge National Laboratory (ORNL) for testing at fields up to 8 T. Soon afterwards ELMO Bumpy Torus (EBT-P) will begin operation at Oak Ridge with superconducting TF coils. At the same time there will be tokamaks with superconducting TF coils 2 to 3 m in diameter in the USSR and France. Toroidal field strength in these machines will range from 6 to 9 T. NbTi and Nb/sub 3/Sn, bath cooling and forced flow, cryostable and metastable - various designs are being tried in this period when this new application of superconductivity is growing and maturing.

Haubenreich, P.N.

1980-01-01T23:59:59.000Z

64

Energy confinement and magnetic field generation in the SSPX spheromaka)  

Science Journals Connector (OSTI)

The Sustained Spheromak Physics Experiment (SSPX) [Hooper et al. Nuclear Fusion39 863 (1999)] explores the physics of efficient magnetic field buildup and energy confinement both essential parts of advancing the spheromak concept. Extending the spheromak formation phase increases the efficiency of magnetic field generation with the maximum edge magnetic field for a given injector current ( B ? I ) from 0.65 T ? MA previously to 0.9 T ? MA . We have achieved the highest electron temperatures ( T e ) recorded for a spheromak with T e > 500 eV toroidalmagnetic field ? 1 T and toroidal current ( ? 1 MA ) [Wood et al. Improved magnetic field generation efficiency and higher temperaturespheromakplasmas Phys. Rev. Lett. (submitted)]. Extending the sustainment phase to > 8 ms extends the period of low magnetic fluctuations ( input power and dominantly collisional majority ion heating. The evolution of electron temperature shows a distinct and robust feature of spheromak formation: A hollow-to-peaked T e ( r ) associated with q ? 1 ? 2 .

B. Hudson; R. D. Wood; H. S. McLean; E. B. Hooper; D. N. Hill; J. Jayakumar; J. Moller; D. Montez; C. A. Romero-Talams; T. A. Casper; J. A. Johnson III; L. L. LoDestro; E. Mezonlin; L. D. Pearlstein

2008-01-01T23:59:59.000Z

65

Nonideal magnetohydrodynamic instabilities and toroidal magnetic confinement  

SciTech Connect

The marked divergence of experimentally observed plasma instability phenomena from the predictions of ideal magnetohydrodynamics led in the early 1960s to the formulations of finite-resistivity stability theory. Beginning in the 1970s, advanced plasma diagnostics have served to establish a detailed correspondence between the predictions of the finite-resistivity theory and experimental plasma behavior - particularly in the case of the resistive kink mode and the tokamak plasma. Nonlinear resistive-kink phenomena have been found to govern the transport of magnetic flux and plasma energy in the reversed-field pinch. The other predicted finite-resistivity instability modes have been more difficult to identify directly and their implications for toroidal magnetic confinement are still unresolved.

Furth, H.P.

1985-05-01T23:59:59.000Z

66

Inertial confinement fusion based on the ion-bubble trigger  

SciTech Connect

Triggering the ion-bubble in an inertial confinement fusion, we have developed a novel scheme for the fast ignition. This scheme relies on the plasma cavitation by the wake of an intense laser pulse to generate an ion-bubble. The bubble acts both as an intense electron accelerator and as an electron wiggler. Consequently, the accelerated electrons trapped in the bubble can emit an intense tunable laser light. This light can be absorbed by an ablation layer on the outside surface of the ignition capsule, which subsequently drills it and thereby produces a guide channel in the pellet. Finally, the relativistic electron beam created in the bubble is guided through the channel to the high density core igniting the fusion fuel. The normalized beam intensity and beam energy required for triggering the ignition have been calculated when core is heated by the e-beam. In addition, through solving the momentum transfer, continuity and wave equations, a dispersion relation for the electromagnetic and space-charge waves has been analytically derived. The variations of growth rate with the ion-bubble density and electron beam energy have been illustrated. It is found that the growth rates of instability are significantly controlled by the ions concentration and the e-beam energy in the bubble.

Jafari, S., E-mail: SJafari@guilan.ac.ir; Nilkar, M.; Ghasemizad, A. [Department of Physics, University of Guilan, Rasht 41335-1914 (Iran, Islamic Republic of); Mehdian, H. [Department of Physics and Institute for Plasma Research, Tarbiat Moallem University, Tehran 15614 (Iran, Islamic Republic of)

2014-10-15T23:59:59.000Z

67

Direct-Drive Inertial Confinement Fusion Research at the Laboratory for Laser Energetics  

E-Print Network (OSTI)

-ray spectroscopy Main laser drive Rayleigh­Taylor and Bell­Plesset growth DT gas Fusion burn/ignition HotDirect-Drive Inertial Confinement Fusion Research at the Laboratory for Laser Energetics: Charting the Path to Thermonuclear Ignition 20th IAEA Fusion Energy Conference Vilamoura, Portugal 1­6 November 2004

68

PLASMA-PHYSICS-21 Heavy ion driven reactor-size double shell inertial fusion targets*  

E-Print Network (OSTI)

Inertial Confinement Fusion (ICF) is considered as an alternative to Magnetic Confinement Fusion to achieve controlled thermonuclear fusion. The main goal is to exploit the energy released from thermonuclear fusion reactions

M. C. Serna Moreno; N. A. Tahir; J. J. Lpez Cela; A. R. Piriz; D. H. H. Hoffmann

69

LiWall Fusion - The New Concept of Magnetic Fusion  

SciTech Connect

Utilization of the outstanding abilities of a liquid lithium layer in pumping hydrogen isotopes leads to a new approach to magnetic fusion, called the LiWall Fusion. It relies on innovative plasma regimes with low edge density and high temperature. The approach combines fueling the plasma by neutral injection beams with the best possible elimination of outside neutral gas sources, which cools down the plasma edge. Prevention of cooling the plasma edge suppresses the dominant, temperature gradient related turbulence in the core. Such an approach is much more suitable for controlled fusion than the present practice, relying on high heating power for compensating essentially unlimited turbulent energy losses.

L.E. Zakharov

2011-01-12T23:59:59.000Z

70

Application of spatially resolved high resolution crystal spectrometry to inertial confinement fusion plasmas  

SciTech Connect

High resolution ({lambda}/{Delta}{lambda}{approx} 10 000) 1D imaging x-ray spectroscopy using a spherically bent crystal and a 2D hybrid pixel array detector is used world wide for Doppler measurements of ion-temperature and plasma flow-velocity profiles in magnetic confinement fusion plasmas. Meter sized plasmas are diagnosed with cm spatial resolution and 10 ms time resolution. This concept can also be used as a diagnostic of small sources, such as inertial confinement fusion plasmas and targets on x-ray light source beam lines, with spatial resolution of micrometers, as demonstrated by laboratory experiments using a 250-{mu}m {sup 55}Fe source, and by ray-tracing calculations. Throughput calculations agree with measurements, and predict detector counts in the range 10{sup -8}-10{sup -6} times source x-rays, depending on crystal reflectivity and spectrometer geometry. Results of the lab demonstrations, application of the technique to the National Ignition Facility (NIF), and predictions of performance on NIF will be presented.

Hill, K. W.; Bitter, M.; Delgado-Aparacio, L.; Pablant, N. A. [Princeton Plasma Physics Laboratory, Princeton, New Jersey 08543 (United States); Beiersdorfer, P.; Schneider, M.; Widmann, K. [Physics Division, Lawrence Livermore National Laboratory, Livermore, California 94550 (United States); Sanchez del Rio, M. [European Synchrotron Radiation Facility, BP 220, 38043-Grenoble Cedex (France); Zhang, L. [Institute of Plasma Physics, Chinese Academy of Sciences, Hefei 230031 (China)

2012-10-15T23:59:59.000Z

71

Magnetic Field Lines in Fusion Plasmas  

Science Journals Connector (OSTI)

Study of mappings as a part of Hamiltonian dynamics of magnetic field lines in plasmas were initiated by the research...1.... Actually, a fusion research in early sixties gave a huge impact on the development of ...

Sadrilla S. Abdullaev

2006-01-01T23:59:59.000Z

72

SXR-XUV Diagnostics for Edge and Core of Magnetically Confined Plasmas  

SciTech Connect

The present report summarizes the results obtained during a one-year extension of DoE grant SXR-XUV Diagnostics for Edge and Core of Magnetically Confined Plasmas, at Johns Hopkins University, aimed at completing the development of a new type of magnetic fusion plasma diagnostic, the XUV Transmission Grating Imaging Radiometer (TGIR). The TGIR enables simultaneous spatially and spectrally resolved measurements of the XUV/VUV radiated power from impurities in fusion plasmas, with high speed. The instrument was successfully developed and qualified in the laboratory and in experiments on a tokamak. Its future applications will be diagnostic of the impurity content and transport in the divertor and edge of advanced magnetic fusion experiments, such as NSTX Upgrade.

Stutman, Dan [Johns Hopkins University

2014-09-10T23:59:59.000Z

73

Proton emission imaging of the nuclear burn in inertial confinement fusion experiments  

E-Print Network (OSTI)

A proton core imaging system has been developed and extensively used for measuring the nuclear burn regions of inertial confinement fusion implosions. These imaging cameras, mounted to the 60-beam OMEGA laser facility, use ...

DeCiantis, Joseph Loreto

2005-01-01T23:59:59.000Z

74

FusEdWeb | Fusion Education  

NLE Websites -- All DOE Office Websites (Extended Search)

Magnetic Confinement Fusion Magnetic Confinement Fusion FusEdWeb: Discover Fusion CPEP's Online Fusion Course Fusion FAQ Fusion and Plasma Glossary Plasma Dictionary Student and Teacher Resources Education and Outreach Ideas Other Fusion and Plasma Sites Great Sites Internet Plasma Physics EXperience GA's Fusion Energy Slide Show International Thermonuclear Experimental Reactor National Ignition Facility Search webby award honoree Webby Awards Honoree April 10, 2007 webby award honoree Links2Go - Fusion, November 9, 1998 FusEdWeb: Fusion Energy Education Our Sun | Other Stars and Galaxies | Inertial Confinement | Magnetic Confinement Fusion by Magnetic Confinement The image above is an artistic rendering of a tokamak, a donut-shaped magnetic vacuum chamber in which wispy vapors of fusion fuel are

75

Magnet operating experience review for fusion applications  

SciTech Connect

This report presents a review of magnet operating experiences for normal-conducting and superconducting magnets from fusion, particle accelerator, medical technology, and magnetohydrodynamics research areas. Safety relevant magnet operating experiences are presented to provide feedback on field performance of existing designs and to point out the operational safety concerns. Quantitative estimates of magnet component failure rates and accident event frequencies are also presented, based on field experience and on performance of similar components in other industries.

Cadwallader, L.C.

1991-11-01T23:59:59.000Z

76

PROGRESS TOWARD UNDERSTANDING MAGNETIZED TARGET FUSION (MTF).  

SciTech Connect

Magnetized target fusion (MTF) takes advantage of (1) the reduction of the electron thermal conductivity in a plasma due to magnetization and (2) the efficient heating through bulk compression. MTF proposes to create a warm plasma with an embedded magnetic field and to compress it using an imploded liner or shell. The minimum energy required for fusion in an optimized target is directly proportional to the mass of the ignited fusion fuel. Simple theoretical arguments and parameter studies have demonstrated that MTF has the potential for significantly reducing the power and intensity of a target driver needed to achieve fusion. In order to acquire a comprehensive understanding of MTF and its potential applications it is prudent to develop more complete and reliable computational techniques. This paper briefly reviews the progress toward that goal.

Kirkpatrick, R. C. (Ronald C.); Lindemuth, I. R. (Irvin R.); Barnes, D. C. (Daniel C.); Faehl, R. J. (Rickey J.); Sheehey, P. T. (Peter T.); Knapp, C. E. (Charles E.)

2001-01-01T23:59:59.000Z

77

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

2012-09-10T23:59:59.000Z

78

Initial Confinement Studies of Ohmically Heated Plasmas in the Tokamak Fusion Test Reactor  

Science Journals Connector (OSTI)

Initial operation of the tokamak fusion test reactor has concentrated upon confinement studies of Ohmically heated hydrogen and deuterium plasmas. Total energy confinement times (?E) are 0.1-0.2 s for a line-average density range (ne) of (1-2.5)1019 m-3 with electron temperatures of Te(0)?1.2-2.2 keV, ion temperatures of Ti(0)?0.9-1.5 keV, and Zeff?3. A comparison of Princeton large torus, poloidal divertor experiment, and tokamak fusion test reactor plasma confinement supports a dimension-cubed scaling law.

P. C. Efthimion et al.

1984-04-23T23:59:59.000Z

79

Magnetic-mirror principle as applied to fusion research  

SciTech Connect

A tutorial account is given of the key physics issues in the confinement of high temperature plasma in magnetic mirror systems. The role of adiabatic invariants and particle drifts and their relationship to equilibrium and stability are discussed, in the context of the various forms of mirror field geometry. Collisional effects and the development and the control of ambipolar potentials are reviewed. The topic of microinstabilities is discussed together with the means for their control. The properties and advantages for fusion power purposes of various special embodiments of the mirror idea, including tandem mirrors, are discussed.

Post, R.F.

1983-08-11T23:59:59.000Z

80

Alternative approaches: concept improvements in magnetic fusion research  

Science Journals Connector (OSTI)

...providing a driver for inertial fusion. Keywords: stellarator...tricity generation using magnetic fusion. These are (a) pressing...e.g. the International Thermonuclear Experimen- tal Reactor (ITER...generation and/or for other fusion applications like testing prototype...

1999-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "magnetic confinement fusion" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


81

Course: FUSION SCIENCE AND ENGINEERING Universit degli Studi di Padova  

E-Print Network (OSTI)

the subject of controlled thermonuclear fusion in magnetically confined plasmas. Both fusion science of Controlled Thermonuclear Fusion, b) Engineering of a Magnetically Confined Fusion Reactor, c) ExperimentalCourse: FUSION SCIENCE AND ENGINEERING Università degli Studi di Padova in agreement

Cesare, Bernardo

82

Core magnetic islands and plasma confinement in the H-1NF heliac  

SciTech Connect

Plasma confinement in the vicinity of vacuum magnetic islands near the magnetic axis in the H-1NF heliac [S. M. Hamberger et al., Fusion Technol. 17, 123 (1990)] has been experimentally studied in a low temperature argon plasma. Experimental results indicate that, under favorable conditions, these low order (m=2) islands near the core of the plasma serve as 'pockets' of higher electron density. This results in significant profile modifications including enhancement of the core radial electric field to a large positive value, possibly through an electron-root ambipolar condition. The characteristics of islands are found to be dependent on the plasma collisionality and island width.

Kumar, Santhosh T. A.; Blackwell, Boyd D.; Howard, John; Harris, Jeffrey H. [Plasma Research Laboratory, Research School of Physical Sciences and Engineering, Australian National University, Canberra, ACT 0200 (Australia)

2010-08-15T23:59:59.000Z

83

COMMENTARIES ON CRITICISMS OF MAGNETIC FUSION  

E-Print Network (OSTI)

-level-radioactive waste for disposal by shallow land burial, or even for recycling. Projected costs of electricity from in magnetic confinement plasma physics research--the investigation of `burning' plasmas in which the vast by substantial technology R&D, has been developed for a tokamak experiment which would explore burning plasma

84

Compatibility of Physics and Engineering in Magnetic Fusion White Paper on Magnetic Fusion Priorities  

E-Print Network (OSTI)

the magnetic field lines within the plasma. In a fusion plasma, the last two of these are largely self magnetic fields, (2) the plasma pressure profile, and (3) the profile of the net current flowing along- determined, so the freedom of physics design is primarily in the externally produced magnetic field

85

Effect of magnetic confinement on manybody nonlinearities of Lorentzian excitons  

SciTech Connect

100-fs time- and frequency-resolved four-wave mixing in GaAs at T=1.6K under magnetic field, 0{<=}|{rvec B}|{<=}12T, is used for investigating how magnetic confinement modifies the processes that govern the manybody nonlinearities of the Lorentzian excitons.

Kner, P.; Bar-Ad, S.; Marquezini, M.V.; Chemla, D.S.

1995-11-01T23:59:59.000Z

86

The Path to Magnetic Fusion Energy  

E-Print Network (OSTI)

1 The Path to Magnetic Fusion Energy: Crossing the Next Frontier Rob Goldston, Jon Menard with contributions from J. Brooks, R. Doerner, D. Gates, J. Harris, G.-Y. Fu, N. Gorelenkov, R. Kaita, S. Kaye, M. Kotschenreuther, G. Kramer, H. Kugel, R. Maingi, R. Majeski, C. Neumeyer, R. Nygren, M. Ono, D. Ruzic, S. Sabbagh

Princeton Plasma Physics Laboratory

87

The Physics of Magnetic Fusion Rectors  

Science Journals Connector (OSTI)

23 April 1981 research-article The Physics of Magnetic Fusion Rectors K. V. Roberts Once ignition has been achieved the...phases. Efficient methods are required for extracting the thermonuclear energy which is deposited as heat within the plasma, for...

1981-01-01T23:59:59.000Z

88

ITER Physics and Exploring Magnetically-Confined  

E-Print Network (OSTI)

-time erosion, dust generation/transport, confined alphas · environmental issues (radiation, erosion, deposition-performance ­ current drive requirements for profiles and NTM stabilization ­ high density operation ­ high radiation-1998) · Europe, Japan, USSR and US conducted Conceptual Design Activity (CDA) · Engineering Design Activity (EDA

89

Deflagration-to-detonation transition in inertial-confinement-fusion baseline targets  

Science Journals Connector (OSTI)

By means of highly resolved one-dimensional hydrodynamics simulations, we provide an understanding of the burn process in inertial-confinement-fusion baseline targets. The cornerstone of the phenomenology of propagating burn in such laser-driven capsules is shown to be the transition from a slow unsteady reaction-diffusion regime of thermonuclear combustion (some sort of deflagration) to a fast detonative one. Remarkably, detonation initiation follows the slowing down of a shockless supersonic reaction wave driven by energy redeposition from the fusion products themselves. Such a route to detonation is specific to fusion plasmas.

P. Gauthier; F. Chaland; L. Masse

2004-11-11T23:59:59.000Z

90

Shock Ignition: A New Approach to High Gain Inertial Confinement Fusion on the National Ignition Facility  

Science Journals Connector (OSTI)

Shock ignition, an alternative concept for igniting thermonuclear fuel, is explored as a new approach to high gain, inertial confinement fusion targets for the National Ignition Facility (NIF). Results indicate thermonuclear yields of ?120250??MJ may be possible with laser drive energies of 11.6MJ, while gains of ?50 may still be achievable at only ?0.2??MJ drive energy. The scaling of NIF energy gain with laser energy is found to be G?126E??(MJ)0.510. This offers the potential for high-gain targets that may lead to smaller, more economic fusion power reactors and a cheaper fusion energy development path.

L. J. Perkins; R. Betti; K. N. LaFortune; W. H. Williams

2009-07-23T23:59:59.000Z

91

Inertial Confinement Fusion Ignition and High Yield Campaign  

E-Print Network (OSTI)

to redirect High Average Power Lasers to be synergistic with NIF ignition and other defense missions #12 · Predicted gains (fusion energy produced/laser energy input) have increased · Direct drive ignition shows) Project has begun · Will add two high-energy petawatt lasers for OMEGA for advanced backlighting and fast-ignition

92

Modeling of a confinement bypass accident with CONSEN, a fast-running code for safety analyses in fusion reactors  

Science Journals Connector (OSTI)

Abstract The CONSEN (CONServation of ENergy) code is a fast running code to simulate thermal-hydraulic transients, specifically developed for fusion reactors. In order to demonstrate CONSEN capabilities, the paper deals with the accident analysis of the magnet induced confinement bypass for ITER design 1996. During a plasma pulse, a poloidal field magnet experiences an over-voltage condition or an electrical insulation fault that results in two intense electrical arcs. It is assumed that this event produces two one square meters ruptures, resulting in a pathway that connects the interior of the vacuum vessel to the cryostat air space room. The rupture results also in a break of a single cooling channel within the wall of the vacuum vessel and a breach of the magnet cooling line, causing the blow down of a steam/water mixture in the vacuum vessel and in the cryostat and the release of 4K helium into the cryostat. In the meantime, all the magnet coils are discharged through the magnet protection system actuation. This postulated event creates the simultaneous failure of two radioactive confinement barrier and it envelopes all type of smaller \\{LOCAs\\} into the cryostat. Ice formation on the cryogenic walls is also involved. The accident has been simulated with the CONSEN code up to 32h. The accident evolution and the phenomena involved are discussed in the paper and the results are compared with available results obtained using the MELCOR code.

Gianfranco Caruso; Fabio Giannetti; Maria Teresa Porfiri

2013-01-01T23:59:59.000Z

93

Engineering design of the Nova Laser Facility for inertial-confinement fusion  

SciTech Connect

The design of the Nova Laser Facility for inertial confinement fusion experiments at Lawrence Livermore National Laboratory is presented from an engineering perspective. Emphasis is placed upon design-to-performance requirements as they impact the various subsystems that comprise this complex experimental facility.

Simmons, W W; Godwin, R O; Hurley, C A; Wallerstein, E. P.; Whitham, K.; Murray, J. E.; Bliss, E. S.; Ozarski, R. G.; Summers, M. A.; Rienecker, F.; Gritton, D. G.; Holloway, F. W.; Suski, G. J.; Severyn, J. R.

1982-01-25T23:59:59.000Z

94

Technical risks and R and D requirements for inertial confinement fusion. Volume 2. Final report  

SciTech Connect

If the technology breakthroughs and/or inventions identified in this preliminary analysis occur in a timely manner, an aggressive R and D program may allow commercial demonstration of confinement fusion within 30 years. Using an innovative interview methodology analysts have mapped out near-term and long-term R and D requirements for ICF to become a viable energy source.

McCarville, T.J.; Gordon, J.D.; Salem, S.L.; Maniscalco, J.A.; Berwald, D.H.; Sicherman, A.; Kulkarni, R.B.; Cherdack, R.N.; Lee, K.C.

1985-02-01T23:59:59.000Z

95

Spherical torus fusion reactor  

DOE Patents (OSTI)

The object of this invention is to provide a compact torus fusion reactor with dramatic simplification of plasma confinement design. Another object of this invention is to provide a compact torus fusion reactor with low magnetic field and small aspect ratio stable plasma confinement. In accordance with the principles of this invention there is provided a compact toroidal-type plasma confinement fusion reactor in which only the indispensable components inboard of a tokamak type of plasma confinement region, mainly a current conducting medium which carries electrical current for producing a toroidal magnet confinement field about the toroidal plasma region, are retained.

Martin Peng, Y.K.M.

1985-10-03T23:59:59.000Z

96

Inertial Confinement Fusion: Quarterly report, April-June 1996  

SciTech Connect

The lead article, `Ion-beam propagation in a low-density reactor chamber for heavy-ion inertial fusion` (p. 89), explores the ability of heavy-ion beams to be adequately transported and focused in an IFE reactor. The next article, `Efficient production and applications of 2- to 10-keV x rays by laser-heated underdense radiators` (p. 96), explores the ability of the NIF to produce sufficient high-energy x rays for diagnostic backlighting, target preheating, or uniform irradiation of large test objects for Nuclear Weapons Effects Testing. For capsule implosion experiments, the increasing energies and distances involved in the NIF compared to Nova require the development of new diagnostics methods. The article `Fusion reaction-rate measurements--Nova and NIF` (p. 115) first reviews the use of time-resolved neutron measurements on Nova to monitor fusion burn histories and then explores the limitations of that technique, principally Doppler broadening, for the proposed NIF. It also explores the use of gamma rays on Nova, thereby providing a proof-of-principle for using gamma rays for monitoring fusion burn histories on the NIF. The articles `The energetics of gas-filled hohlraums` (p. 110) and `Measurements of laser- speckle-induced perturbations in laser-driven foils` (p. 123) report measurements on Nova of two important aspects of implosion experiments. The first characterizes the amount of energy lost from a hohlraum by stimulated Brillouin and Raman scattering as a function of gas fill and laser-beam uniformity. The second of these articles shows that the growth of density nonuniformities implanted on smooth capsule surfaces by laser speckle can be correlated with the effects of physical surface roughness. The article `Laser-tissue interaction modeling with the LATIS computer program` (p. 103) explores the use of modeling to enhance the effectiveness--maximize desired effects and minimize collateral damage--of lasers for medical purposes.

Correll, D.

1996-06-01T23:59:59.000Z

97

Dynamic response of materials on subnanosecond time scales, and beryllium properties for inertial confinement fusion  

SciTech Connect

During the past few years, substantial progress has been made in developing experimental techniques capable of investigating the response of materials to dynamic loading on nanosecond time scales and shorter, with multiple diagnostics probing different aspects of the behavior. These relatively short time scales are scientifically interesting because plastic flow and phase changes in common materials with simple crystal structures--such as iron--may be suppressed, allowing unusual states to be induced and the dynamics of plasticity and polymorphism to be explored. Loading by laser-induced ablation can be particularly convenient: this technique has been used to impart shocks and isentropic compression waves from {approx}1 to 200 GPa in a range of elements and alloys, with diagnostics including line imaging surface velocimetry, surface displacement (framed area imaging), x-ray diffraction (single crystal and polycrystal), ellipsometry, and Raman spectroscopy. A major motivation has been the study of the properties of beryllium under conditions relevant to the fuel capsule in inertial confinement fusion: magnetically driven shock and isentropic compression shots at Z were used to investigate the equation of state and shock melting characteristics, complemented by laser ablation experiments to investigate plasticity and heterogeneous response from the polycrystalline microstructure. These results will help to constrain acceptable tolerances on manufacturing, and possible loading paths, for inertial fusion ignition experiments at the National Ignition Facility. Laser-based techniques are being developed further for future material dynamics experiments, where it should be possible to obtain high quality data on strength and phase changes up to at least 1 TPa.

Swift, Damian C.; Tierney, Thomas E.; Luo Shengnian; Paisley, Dennis L.; Kyrala, George A.; Hauer, Allan; Greenfield, Scott R.; Koskelo, Aaron C.; McClellan, Kenneth J.; Lorenzana, Hector E.; Kalantar, Daniel; Remington, Bruce A.; Peralta, Pedro; Loomis, Eric [Los Alamos National Laboratory, MS E526, Los Alamos, New Mexico 87545 (United States); Lawrence Livermore National Laboratory, 7000 East Avenue, Livermore, California 94550 (United States); Arizona State University, Tempe, Arizona 85287 (United States)

2005-05-15T23:59:59.000Z

98

Pre-Amplifier Module for Laser Inertial Confinement Fusion  

SciTech Connect

The Pre-Amplifier Modules (PAMs) are the heart of the National Ignition Facility (NIF), providing most of the energy gain for the most energetic laser in the world. Upon completion, NIF will be the only laboratory in which scientists can examine the fusion processes that occur inside stars, supernovae, and exploding nuclear weapons and that may someday serve as a virtually inexhaustible energy source for electricity. Consider that in a fusion power plant 50 cups of water could provide the energy comparable to 2 tons of coal. Of paramount importance for achieving laser-driven fusion ignition with the least energy input is the synchronous and symmetric compression of the target fuel--a condition known as laser power balance. NIF's 48 PAMs thus must provide energy gain in an exquisitely stable and consistent manner. While building one module that meets performance requirements is challenging enough, our design has already enabled the construction and fielding of 48 PAMs that are stable, uniform, and interchangeable. PAM systems are being tested at the University of Rochester's Laboratory for Laser Energetics, and the Atomic Weapons Enterprise of Great Britain has purchased the PAM power system.

Heebner, J E; Bowers, M W

2008-02-06T23:59:59.000Z

99

Basic hydrodynamics of RichtmyerMeshkov-type growth and oscillations in the inertial confinement fusion-relevant conditions  

Science Journals Connector (OSTI)

...phase of inertial confinement fusion implosionsPhys. Plasmas 9...adiabat shaping in inertial fusion, implosions:the relaxation...Solodov2007Shock ignition of thermonuclear fuel with high areal densityPhys...1998Direct-drive laser fusion:status and prospectsPhys...

2010-01-01T23:59:59.000Z

100

Investigation into Fusion Feasibility of a Magnetized Target Fusion Reactor: A Preliminary Numerical Framework  

Science Journals Connector (OSTI)

The efforts to engineer devices to produces conditions suitable for nuclear fusion on earth have made significant leaps and ... improved technology and engineering methods. Magnetized target fusion, or magneto-in...

Michael Lindstrom; Sandra Barsky; Brian Wetton

2014-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "magnetic confinement fusion" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


101

Improved Magnetic Fusion Energy Economics via Massive Resistive Electromagnets  

SciTech Connect

Abandoning superconductors for magnetic fusion reactors and instead using resistive magnet designs based on cheap copper or aluminum conductor material operating at "room temperature" (300 K) can reduce the capital cost per unit fusion power and simplify plant operations. By increasing unit size well beyond that of present magnetic fusion energy conceptual designs using superconducting electromagnets, the recirculating power fraction needed to operate resistive electromagnets can be made as close to zero as needed for economy without requiring superconductors. Other advantages of larger fusion plant size, such as very long inductively driven pulses, may also help reduce the cost per unit fusion power.

Woolley, R.D.

1998-08-19T23:59:59.000Z

102

Scientists discuss progress toward magnetic fusion energy at...  

NLE Websites -- All DOE Office Websites (Extended Search)

Scientists discuss progress toward magnetic fusion energy at 2013 AAAS annual meeting February 21, 2013 Tweet Widget Google Plus One Share on Facebook Scientists participating in...

103

Inertial Confinement Fusion quarterly report, October--December 1994. Volume 5, No. 1  

SciTech Connect

The ICF quarterly report is published by the Inertial Confinement Fusion Program at the Lawrence Livermore National Laboratory. Topics included in this issue include: system description and initial performance results for beamlet, design and performance of the beamlet amplifiers and optical switch, beamlet pulse-generation and wavefront-control system, large-aperture, high- damage-threshold optics for beamlet, beamlet pulsed power system, beamlet laser diagnostics, and beam propagation and frequency conversion modeling for the beamlet laser.

NONE

1995-09-01T23:59:59.000Z

104

Component framework for coupled integrated fusion plasma simulation  

Science Journals Connector (OSTI)

Successful simulation of the complex physics that affect magnetically confined fusion plasma remains an important target milestone towards the development of viable fusion energy. Major advances in the underlying physics formulations, mathematical modeling, ... Keywords: components, coupled simulation, framework, fusion

Wael R. Elwasif; David E. Bernholdt; Lee A. Berry; Donald B. Batchelor

2007-10-01T23:59:59.000Z

105

Harmonic conversion of large-aperture 1.05-?m laser beams for inertial-confinement fusion research  

Science Journals Connector (OSTI)

To provide high-energy, high-power beams at short wavelengths for inertial-confinement fusion experiments, we routinely convert the 1.05-?m output of the Nova,...

Wegner, P J; Henesian, M A; Speck, D R; Bibeau, C; Ehrlich, R B; Laumann, C W; Lawson, J K; Weiland, T L

1992-01-01T23:59:59.000Z

106

LA-UR-98-2413 Magnetized Target Fusion  

E-Print Network (OSTI)

to the Office of Fusion Energy Sciences May 19, 1998 PoP Program Leaders and Editors: K. F. Schoenberg and R. E, Massey University, New Zealand; R. D. Milroy, U. Washington; L. Green, Westinghouse Science APPENDIX A: Why Magnetized Target Fusion Offers A Low-Cost Development Path for Fusion Energy

107

COLLIMATION AND CONFINEMENT OF MAGNETIC JETS BY EXTERNAL MEDIA  

SciTech Connect

We study the collimation of a highly magnetized jet by a surrounding cocoon that forms as a result of the interaction of the jet with the external medium. We show that in regions where the jet is well confined by the cocoon, current-driven instabilities should develop over timescales shorter than the expansion time of the jet's head. We speculate that these instabilities would give rise to complete magnetic field destruction, whereby the jet undergoes a transition from high to low sigma above the collimation zone. Using this assumption, we construct a self-consistent model for the evolution of the jet-cocoon system in an ambient medium of arbitrary density profile. We apply the model to jet breakout in long gamma-ray bursts (GRBs) and show that the jet is highly collimated inside the envelope of the progenitor star and is likely to remain confined well after breakout. We speculate that this strong confinement may provide a channel for magnetic field conversion in GRB outflows, whereby the hot, low-sigma jet section thereby produced is the source of the photospheric emission observed in many bursts.

Levinson, Amir [School of Physics and Astronomy, Tel Aviv University, Tel Aviv 69978 (Israel)] [School of Physics and Astronomy, Tel Aviv University, Tel Aviv 69978 (Israel); Begelman, Mitchell C., E-mail: Levinson@wise.tau.ac.il, E-mail: mitch@jila.colorado.edu [JILA, University of Colorado and National Institute of Standards and Technology, 440 UCB, Boulder, CO 80309-0440 (United States)

2013-02-20T23:59:59.000Z

108

Inertial confinement fusion research and development studies. Final report, October 1979-August 1980  

SciTech Connect

These Inertial Confinement Fusion (ICF) research and development studies were selected for structural, thermal, and vacuum pumping analyses in support of the High Yield Lithium Injection Fusion Energy (HYLIFE) concept development. An additional task provided an outlined program plan for an ICF Engineering Test Facility, using the HYLIFE concept as a model, although the plan is generally applicable to other ICF concepts. The HYLIFE is one promising type of ICF concept which features a falling array of liquid lithium jets. These jets surround the fusion reaction to protect the first structural wall (FSW) of the vacuum chamber by absorbing the fusion energy, and to act as the tritium breeder. The fusion energy source is a deuterium-tritium pellet injected into the chamber every second and driven by laser or heavy ion beams. The studies performed by Grumman have considered the capabilities of specific HYLIFE features to meet life requirements and the requirement to recover to preshot conditions prior to each subsequent shot. The components under investigation were the FSW which restrains the outward motion of the liquid lithium, the nozzle plate which forms the falling jet array, the graphite shield which is in direct top view of the fusion pellet, and the vacuum pumping system. The FSW studies included structural analysis, and definition of an experimental program to validate computer codes describing lithium motion and the resulting impact on the wall.

Bullis, R.; Finkelman, M.; Leng, J.; Luzzi, T.; Ojalvo, I.; Powell, E.; Sedgley, D.

1980-08-01T23:59:59.000Z

109

Direct-Drive Inerital Confinement Fusion Research at the Laboratory for Laser Energetics: Charting the Path to Thermonuclear Ignition  

SciTech Connect

Significant theoretical and experimental progress continues to be made at the University of Rocheter's Laboratory for Laser Energetics (LLE), charting the path to direct-drive inertial confinement fusion (ICF) ignition. Direct drive offers the potential for higher-gain implosions than x-ray drive and is a leading candidate for an inertial fusion enery power plant.

McCrory, R.L.; Regan, S.P.; Loucks, S.J.; Meyerhofer, D.D.; Skupsky, S.; Betti, R.; Boehly, T.R.; Craxton, R.S.; Collins, T.J.B.; Delettrez, J.A.; Edgell, D.; Epstein, R.; Fletcher, K.A.; Freeman, C.; Frenje, J.A.; Glebov, V.Yu.; Goncharov, V.N.; Harding, D.R.; Igumenshchev, I.V.; Keck, R.L.; Kilkenny, J.D.; Knauer, J.P.; Li, C.K.; Marciante, J.; Marozas, J.A.; Marshall, F.J.; Maximov, A.V.; McKenty, P.W.; Myatt, J.; Padalino, S.; Petrasso, R.D.; Radha, P.B.; Sangster, T.C.; Seguin, F.H.; Seka, W.; Smalyuk, V.A.; Soures, J.M.; Stoeckl, C.; Yaakobi, B.; Zuegel, J.D.

2005-10-07T23:59:59.000Z

110

Enhanced confinement with increased extent of the low magnetic shear region in tokamak plasmas  

E-Print Network (OSTI)

Enhanced confinement with increased extent of the low magnetic shear region in tokamak plasmas. The Hamiltonian representation of magnetic field lines enables to study their confinement properties in tokamaks ignition, it is required that the present hot tokamak plasmas have a better energy confinement. The energy

Paris-Sud XI, Université de

111

The physics of magnetic fusion reactors  

Science Journals Connector (OSTI)

During the past two decades there have been substantial advances in magnetic fusion research. On the experimental front, progress has been led by the mainline tokamaks, which have achieved reactor-level values of temperature and plasma pressure. Comparable progress, when allowance is made for their smaller programs, has been made in complementary configurations such as the stellarator, reversed-field pinch and field-reversed configuration. In this paper, the status of understanding of the physics of toroidal plasmas is reviewed. It is shown how the physics performance, constrained by technological and economic realities, determines the form of reference toroidal reactors. A comparative study of example reactors is not made, because the level of confidence in projections of their performance varies widely, reflecting the vastly different levels of support which each has received. Success with the tokamak has led to the initiation of the International Thermonuclear Experimental Reactor project. It is designed to produce 1500 MW of fusion power from a deuterium-tritium plasma for pulses of 1000 s or longer and to demonstrate the integration of the plasma and nuclear technologies needed for a demonstration reactor.

John Sheffield

1994-07-01T23:59:59.000Z

112

Basics of Inertial Confinement Fusion NIF and Photon Science Directorate Chief Scientist  

E-Print Network (OSTI)

for ignition on the Nova and Omega laser · Final steps on the path to ignition - the National Ignition Campaign/Centurion Why do we believe that ignition will work on NIF? #12;Advances in laser performance, precision) MAGNETIC FIELD ELECTRON NUCLEUS + - SUN #12;The extreme conditions required for inertial fusion ignition

113

System and method of operating toroidal magnetic confinement devices  

DOE Patents (OSTI)

For toroidal magnetic confinement devices the second region of stability against ballooning modes can be accessed with controlled operation. Under certain modes of operation, the first and second stability regions may be joined together. Accessing the second region of stability is accomplished by forming a bean-shaped plasma and increasing the indentation until a critical value of indentation is reached. A pusher coil, located at the inner-major-radius side of the device, is engaged to form a bean-shaped poloidal cross-section in the plasma.

Chance, Morrell S. (Princeton Jct., NJ); Jardin, Stephen C. (Princeton, NJ); Stix, Thomas H. (Princeton, NJ); Grimm, deceased, Ray C. (late of Yowie Bay, AU); Manickam, Janardhan (Lawrenceville, NJ); Okabayashi, Michio (Princeton, NJ)

1987-01-01T23:59:59.000Z

114

Driving high-gain shock-ignited inertial confinement fusion targets by green laser light  

SciTech Connect

Standard direct-drive inertial confinement fusion requires UV light irradiation in order to achieve ignition at total laser energy of the order of 1 MJ. The shock-ignition approach opens up the possibility of igniting fusion targets using green light by reducing the implosion velocity and laser-driven ablation pressure. An analytical model is derived, allowing to rescale UV-driven targets to green light. Gain in the range 100-200 is obtained for total laser energy in the range 1.5-3 MJ. With respect to the original UV design, the rescaled targets are less sensitive to irradiation asymmetries and hydrodynamic instabilities, while operating in the same laser-plasma interaction regime.

Atzeni, Stefano; Marocchino, Alberto; Schiavi, Angelo [Dipartimento SBAI, Universita di Roma 'La Sapienza' and CNISM, Via A. Scarpa 14-16, I-00161 Roma (Italy)

2012-09-15T23:59:59.000Z

115

Multiple-beam laserplasma interactions in inertial confinement fusion  

SciTech Connect

The experimental evidence for multiple-beam laser-plasma instabilities of relevance to laser driven inertial confinement fusion at the ignition scale is reviewed, in both the indirect and direct-drive approaches. The instabilities described are cross-beam energy transfer (in both indirectly driven targets on the NIF and in direct-drive targets), multiple-beam stimulated Raman scattering (for indirect-drive), and multiple-beam two-plasmon decay instability (in direct drive). Advances in theoretical understanding and in the numerical modeling of these multiple beam instabilities are presented.

Myatt, J. F., E-mail: jmya@lle.rochester.edu; Zhang, J.; Maximov, A. V. [Laboratory for Laser Energetics, University of Rochester, 250 East River Road, Rochester, New York 14623-1299 (United States); Department of Mechanical Engineering, University of Rochester, Rochester, New York 14627 (United States); Short, R. W.; Seka, W.; Edgell, D. H.; Michel, D. T.; Igumenshchev, I. V. [Laboratory for Laser Energetics, University of Rochester, 250 East River Road, Rochester, New York 14623-1299 (United States); Froula, D. H. [Laboratory for Laser Energetics, University of Rochester, 250 East River Road, Rochester, New York 14623-1299 (United States); Department of Physics and Astronomy, University of Rochester, Rochester, New York 14627-0171 (United States); Hinkel, D. E.; Michel, P.; Moody, J. D. [Lawrence Livermore National Laboratory, P.O. Box 808, Livermore, California 94551-0808 (United States)

2014-05-15T23:59:59.000Z

116

Demonstration of Ignition Radiation Temperatures in Indirect-Drive Inertial Confinement Fusion Hohlraums  

SciTech Connect

We demonstrate the hohlraum radiation temperature and symmetry required for ignition-scale inertial confinement fusion capsule implosions. Cryogenic gas-filled hohlraums with 2.2 mm-diameter capsules are heated with unprecedented laser energies of 1.2 MJ delivered by 192 ultraviolet laser beams on the National Ignition Facility. Laser backscatter measurements show that these hohlraums absorb 87% to 91% of the incident laser power resulting in peak radiation temperatures of T{sub RAD}=300 eV and a symmetric implosion to a 100 {mu}m diameter hot core.

Glenzer, S. H.; MacGowan, B. J.; Meezan, N. B.; Adams, P. A.; Alfonso, J. B.; Alger, E. T.; Alherz, Z.; Alvarez, L. F.; Alvarez, S. S.; Amick, P. V.; Andersson, K. S.; Andrews, S. D.; Antonini, G. J.; Arnold, P. A.; Atkinson, D. P.; Auyang, L.; Azevedo, S. G.; Balaoing, B. N. M.; Baltz, J. A.; Barbosa, F. [Lawrence Livermore National Laboratory, Livermore, California 94550 (United States)

2011-02-25T23:59:59.000Z

117

Production and measurement of engineered surfaces for inertial confinement fusion research  

SciTech Connect

Inertial Confinement Fusion uses the optical energy from a very high power laser to implode spherical capsules that contain a fuel mixture of deuterium and tritium. The capsules are made of either Beryllium, plastic, or glass and range from 0.1 mm to 2 mm in diameter. As a capsule implodes, thereby compressing the fuel to reach nuclear fusion conditions, it achieves temperatures of millions of degrees Centigrade and very high pressures. In this state, the capsule materials act like fluids and often a low density fluidic material will push on a higher density material which can be a very unstable condition depending upon the smoothness of the interface between the two materials. This unstable condition is called a hydrodynamic instabillity which results in the mixing of the two materials. If the mixing occurs between the fuel and a non-fuel material, it can stop the fusion reaction just like adding significant amounts of water to gasoline can stop the operation of an automobile. Another region in the capsule where surface roughness can cause capsule performance degradation is at a joint. For instance, many capsules are made of hemispheres that are joined together. If the joint surfaces are too rough, then there will an effective reduction in density at the joint. This density reduction can cause a non-uniform implosion which will reduce the fusion energy coming out of the capsule.

Day, Robert D [Los Alamos National Laboratory; Hatch, Douglas J [Los Alamos National Laboratory; Rivera, Gerald [Los Alamos National Laboratory

2011-01-19T23:59:59.000Z

118

Routes to interchange mode turbulence and chaos in plasmas confined by a helical magnetic field  

E-Print Network (OSTI)

. The helical magnetic field lines introduce a periodicity condition for the flute modes in the verticalRoutes to interchange mode turbulence and chaos in plasmas confined by a helical magnetic field K in a laboratory plasma confined by a helical magnetic field [1], i.e. a toroidal plasma with a weak vertical

119

Observation of strong electromagnetic fields around laser-entrance holes of ignition-scale hohlraums in inertial-confinement fusion experiments at the National Ignition Facility  

E-Print Network (OSTI)

Energy spectra and spectrally resolved one-dimensional fluence images of self-emitted charged-fusion products (14.7 MeV D[superscript 3]He protons) are routinely measured from indirectly driven inertial-confinement fusion ...

Li, C. K.

120

The Path to Magnetic Fusion Energy  

SciTech Connect

When the possibility of fusion as an energy source for electricity generation was realized in the 1950s, understanding of the plasma state was primitive. The fusion goal has been paced by, and has stimulated, the development of plasma physics. Our understanding of complex, nonlinear processes in plasmas is now mature. We can routinely produce and manipulate 100 million degree plasmas with remarkable finesse, and we can identify a path to commercial fusion power. The international experiment, ITER, will create a burning (self-sustained) plasma and produce 500 MW of thermal fusion power. This talk will summarize the progress in fusion research to date, and the remaining steps to fusion power.

Prager, Stewart (PPPL) [PPPL

2011-05-04T23:59:59.000Z

Note: This page contains sample records for the topic "magnetic confinement fusion" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


121

RF Heating and Current Drive in Magnetically Confined Plasma: a Historical Perspective  

SciTech Connect

The history of high power RF waves injected into magnetically confined plasma for the purposes of heating to fusion relevant temperatures spans nearly five decades. The road to success demanded the development of the theory of wave propagation in high temperature plasma in complex magnetic field geometries, development of antenna structures and transmission lines capable of handling high RF powers, and the development of high power RF (microwave) sources. In the early days, progress was hindered by the lack of good confinement of energetic particles formed by high power RF wave-plasma interactions. For example, in the ion cyclotron resonance frequency regime (ICRF) ions with energies in the multi-100keV, or even MeV range may be formed due to the presence of efficient 'minority species' absorption. Electrons with similar energies can be formed upon the injection of RF waves in the electron cyclotron resonance (ECRH) or lower hybrid range of frequencies (LHRF) because of quasi-linear Landau (cyclotron) interactions between waves and particles. In this paper a summary of four decades of historical evolution of wave heating and current drive results will be given.

Porkolab, Miklos [Massachusetts Institute of Technology, Plasma Science and Fusion Center and Department of Physics, NW 16-288, 167 Albany Street, Cambridge, MA 02139 (United States)

2007-09-28T23:59:59.000Z

122

Laser or charged-particle-beam fusion reactor with direct electric generation by magnetic flux compression  

DOE Patents (OSTI)

The invention is a laser or particle-beam-driven fusion reactor system which takes maximum advantage of both the very short pulsed nature of the energy release of inertial confinement fusion (ICF) and the very small volumes within which the thermonuclear burn takes place. The pulsed nature of ICF permits dynamic direct energy conversion schemes such as magnetohydrodynamic (MHD) generation and magnetic flux compression; the small volumes permit very compact blanket geometries. By fully exploiting these characteristics of ICF, it is possible to design a fusion reactor with exceptionally high power density, high net electric efficiency, and low neutron-induced radioactivity. The invention includes a compact blanket design and method and apparatus for obtaining energy utilizing the compact blanket.

Lasche, G.P.

1983-09-29T23:59:59.000Z

123

FusEdWeb | Fusion Education  

NLE Websites -- All DOE Office Websites (Extended Search)

Achieving Fusion Conditions Achieving Fusion Conditions CPEP: Online Fusion Course Main Topics Energy Sources and Conversions Two Key Fusion Reactions How Fusion Reactions Work Creating the Conditions for Fusion Plasmas - the 4th State of Matter Achieving Fusion Conditions More Info About CPEP Fusion Chart Images: English + 6 More Languages Main CPEP Web Site Printed Charts in 3 Sizes Search webby award honoree Webby Awards Honoree April 10, 2007 webby award honoree Links2Go - Fusion, November 9, 1998 FusEdWeb: Fusion Energy Education Overview | The Guided Tour Achieving Fusion Conditions EXPERIMENTAL RESULTS IN FUSION RESEARCH Both inertial and magnetic confinement fusion research have focused on understanding plasma confinement and heating. This research has led to increases in plasma temperature, T, density, n, and energy confinement

124

Implications of NSTX Lithium Results for Magnetic Fusion Research  

SciTech Connect

Lithium wall coating techniques have been experimentally explored on NSTX for the last five years. The lithium experimentation on NSTX started with a few milligrams of lithium injected into the plasma as pellets and it has evolved to a lithium evaporation system which can evaporate up to ~ 100 g of lithium onto the lower divertor plates between lithium reloadings. The unique feature of the lithium research program on NSTX is that it can investigate the effects of lithium in H-mode divertor plasmas. This lithium evaporation system thus far has produced many intriguing and potentially important results; the latest of these are summarized in a companion paper by H. Kugel. In this paper, we suggest possible implications and applications of the NSTX lithium results on the magnetic fusion research which include electron and global energy confinement improvements, MHD stability enhancement at high beta, ELM control, H-mode power threshold reduction, improvements in radio frequency heating and non-inductive plasma start-up performance, innovative divertor solutions and improved operational efficiency.

M. Ono, M.G. Bell, R.E. Bell, R. Kaita, H.W. Kugel, B.P. LeBlanc, J.M. Canik, S. Diem, S.P.. Gerhardt, J. Hosea, S. Kaye, D. Mansfield, R. Maingi, J. Menard, S. F. Paul, R. Raman, S.A. Sabbagh, C.H. Skinner, V. Soukhanovskii, G. Taylor, and the NSTX Research Team

2010-01-14T23:59:59.000Z

125

Inertial confinement fusion. 1995 ICF annual report, October 1994--September 1995  

SciTech Connect

Lawrence Livermore National Laboratory`s (LLNL`s) Inertial Confinement Fusion (ICF) Program is a Department of Energy (DOE) Defense Program research and advanced technology development program focused on the goal of demonstrating thermonuclear fusion ignition and energy gain in the laboratory. During FY 1995, the ICF Program continued to conduct ignition target physics optimization studies and weapons physics experiments in support of the Defense Program`s stockpile stewardship goals. It also continued to develop technologies in support of the performance, cost, and schedule goals of the National Ignition Facility (NIF) Project. The NIF is a key element of the DOE`s Stockpile Stewardship and Management Program. In addition to its primary Defense Program goals, the ICF Program provides research and development opportunities in fundamental high-energy-density physics and supports the necessary research base for the possible long-term application to inertial fusion energy (IFE). Also, ICF technologies have had spin-off applications for industrial and governmental use. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

NONE

1996-06-01T23:59:59.000Z

126

Stability of localized MHD perturbations in confinement systems with closed magnetic field lines  

Science Journals Connector (OSTI)

Conditions are determined for the stability of a finite-pressure plasma against perturbations localized near a magnetic field line in a magnetic confinement system without average minimum-B. The marginal stabilit...

V. V. Arsenin

2002-09-01T23:59:59.000Z

127

Path Integral Confined Dirac Fermions in a Constant Magnetic Field  

E-Print Network (OSTI)

We consider Dirac fermion confined in harmonic potential and submitted to a constant magnetic field. The corresponding solutions of the energy spectrum are obtained by using the path integral techniques. For this, we begin by establishing a symmetric global projection, which provides a symmetric form for the Green function. Based on this, we show that it is possible to end up with the propagator of the harmonic oscillator for one charged particle. After some transformations, we derive the normalized wave functions and the eigenvalues in terms of different physical parameters and quantum numbers. By interchanging quantum numbers, we show that our solutions possed interesting properties. The density of current and the non-relativistic limit are analyzed where different conclusions are obtained.

Abdeldjalil Merdaci; Ahmed Jellal; Lyazid Chetouani

2014-04-17T23:59:59.000Z

128

The magnetic field and wind confinement of b Cephei: new clues for interpreting the Be phenomenon?  

E-Print Network (OSTI)

The magnetic field and wind confinement of b Cephei: new clues for interpreting the Be phenomenon and of the associated magnetically confined wind and circumstellar environment. A re- examination of the fundamental with an inclination of the rotation axis of about 608. Using two different modelling strategies, we obtain

Donati, Jean-François

129

Velocity Shear Stabilization of Centrifugally Confined Plasma  

Science Journals Connector (OSTI)

A magnetized, centrifugally confined plasma is subjected to a 3D MHD stability test. Ordinarily, the system is expected to be grossly unstable to flute interchanges of field lines. Numerical simulation shows though that the system is stable on account of velocity shear. This allows consideration of a magnetically confined plasma for thermonuclear fusion that has a particularly simple coil configuration.

Yi-Min Huang and A. B. Hassam

2001-11-16T23:59:59.000Z

130

Investigation of methods for fabricating, characterizing, and transporting cryogenic inertial-confinement-fusion tartets  

SciTech Connect

The objective of this work is to investigate methods for fabricating, characterizing and transporting cryogenic inertial confinement fusion targets on a continuous basis. A microprocessor-based data acquisition system has been built that converts a complete target image to digital data, which are then analyzed by automated software procedures. The low temperatures required to freeze the hydrogen isotopes contained in a target is provided by a cryogenic cold chamber capable of attaining 15 K. A new method for target manipulation and positioning is studied that employs molecular gas beams to levitate a target and an electrostatic quadrupole structure to provide for its lateral containment. Since the electrostatic target-positioning scheme requires that the targets be charged, preliminary investigation has been carried out for a target-charging mechanism based on ion-bombardment.

Fanning, J.J.; Kim, K.

1981-01-01T23:59:59.000Z

131

Change in Inertial Confinement Fusion Implosions upon Using an Ab Initio Multiphase DT Equation of State  

Science Journals Connector (OSTI)

Improving the description of the equation of state (EOS) of deuterium-tritium (DT) has recently been shown to change significantly the gain of an inertial confinement fusion target [S.?X. Hu et al., Phys. Rev. Lett. 104, 235003 (2010)]. Here we use an advanced multiphase EOS, based on abinitio calculations, to perform a full optimization of the laser pulse shape with hydrodynamic simulations starting from 19K in DT ice. The thermonuclear gain is shown to be a robust estimate over possible uncertainties of the EOS. Two different target designs are discussed, for shock ignition and self-ignition. In the first case, the areal density and thermonuclear energy can be recovered by slightly increasing the laser energy. In the second case, a lower in-flight adiabat is needed, leading to a significant delay (3ns) in the shock timing of the implosion.

L. Caillabet; B. Canaud; G. Salin; S. Mazevet; P. Loubeyre

2011-09-08T23:59:59.000Z

132

Development of a Bayesian method for the analysis of inertial confinement fusion experiments on the NIF  

E-Print Network (OSTI)

The complex nature of inertial confinement fusion (ICF) experiments results in a very large number of experimental parameters that are only known with limited reliability. These parameters, combined with the myriad physical models that govern target evolution, make the reliable extraction of physics from experimental campaigns very difficult. We develop an inference method that allows all important experimental parameters, and previous knowledge, to be taken into account when investigating underlying microphysics models. The result is framed as a modified $\\chi^{2}$ analysis which is easy to implement in existing analyses, and quite portable. We present a first application to a recent convergent ablator experiment performed at the NIF, and investigate the effect of variations in all physical dimensions of the target (very difficult to do using other methods). We show that for well characterised targets in which dimensions vary at the 0.5% level there is little effect, but 3% variations change the results of i...

Gaffney, Jim A; Sonnad, Vijay; Libby, Stephen B

2013-01-01T23:59:59.000Z

133

Advances in compact proton spectrometers for inertial-confinement fusion and plasma nuclear science  

SciTech Connect

Compact wedge-range-filter proton spectrometers cover proton energies {approx}3-20 MeV. They have been used at the OMEGA laser facility for more than a decade for measuring spectra of primary D{sup 3}He protons in D{sup 3}He implosions, secondary D{sup 3}He protons in DD implosions, and ablator protons in DT implosions; they are now being used also at the National Ignition Facility. The spectra are used to determine proton yields, shell areal density at shock-bang time and compression-bang time, fuel areal density, and implosion symmetry. There have been changes in fabrication and in analysis algorithms, resulting in a wider energy range, better accuracy and precision, and better robustness for survivability with indirect-drive inertial-confinement-fusion experiments.

Seguin, F. H.; Sinenian, N.; Rosenberg, M.; Zylstra, A.; Manuel, M. J.-E.; Sio, H.; Waugh, C.; Rinderknecht, H. G.; Johnson, M. Gatu; Frenje, J.; Li, C. K.; Petrasso, R. [Plasma Science and Fusion Center, Massachusetts Institute of Technology, Cambridge, Massachusetts 02139 (United States); Sangster, T. C.; Roberts, S. [Laboratory for Laser Energetics, University of Rochester, Rochester, New York 14623 (United States)

2012-10-15T23:59:59.000Z

134

Interactive tools designed to study mix in inertial confinement fusion implosions  

SciTech Connect

Graphical user interface tools have been built in IDL to study mix in inertial confinement fusion (ICF) implosion cores. FLAME (Fall-Line Analysis Mix Evaluator), a code which investigates yield degradation due to mix , was designed to post-process 1D hydrodynamic simulation output by implementing a variety of mix models. Three of these mix models are based on the physics of the fall-line. In addition, mixing data from other sources can be incorporated into the yield degradation analysis. Two independent tools called HAME (Haan Analysis Mix Evaluator) and YAME (Youngs Analysis Mix Evaluator) were developed to calculate the spatial extent of the mix region according to the Haan saturation model and Youngs' phenomenological model, respectively. FLAME facilitates a direct comparison to experimental data. The FLAME, HAME, and YAME interfaces are user-friendly, flexible, and platform-independent.

Welser-sherrill, Leslie [Los Alamos National Laboratory; Cooley, James H [Los Alamos National Laboratory; Wilson, Doug C [Los Alamos National Laboratory

2008-01-01T23:59:59.000Z

135

Improved Magnetic Fusion Energy Economics Via Massive Resistive Electromagnets  

E-Print Network (OSTI)

for magnetic fusion reactors and instead using resistive magnet designs based on cheap copper or aluminum maintenance cost To put the capital cost issue into perspective, consider the following comparison, which incorporate niobium, a rare and expensive material compared to copper or aluminum. In addition to the direct

136

Mode 1 drive asymmetry in inertial confinement fusion implosions on the National Ignition Facility  

SciTech Connect

Mode 1 radiation drive asymmetry (pole-to-pole imbalance) at significant levels can have a large impact on inertial confinement fusion implosions at the National Ignition Facility (NIF). This asymmetry distorts the cold confining shell and drives a high-speed jet through the hot spot. The perturbed hot spot shows increased residual kinetic energy and reduced internal energy, and it achieves reduced pressure and neutron yield. The altered implosion physics manifests itself in observable diagnostic signatures, especially the neutron spectrum which can be used to measure the neutron-weighted flow velocity, apparent ion temperature, and neutron downscattering. Numerical simulations of implosions with mode 1 asymmetry show that the resultant simulated diagnostic signatures are moved toward the values observed in many NIF experiments. The diagnostic output can also be used to build a set of integrated implosion performance metrics. The metrics indicate that P{sub 1} has a significant impact on implosion performance and must be carefully controlled in NIF implosions.

Spears, Brian K., E-mail: spears9@llnl.gov; Edwards, M. J.; Hatchett, S.; Kritcher, A.; Lindl, J.; Munro, D.; Patel, P.; Robey, H. F.; Town, R. P. J. [Lawrence Livermore National Laboratory, P.O. Box 808, Livermore, California 94551-0808 (United States)] [Lawrence Livermore National Laboratory, P.O. Box 808, Livermore, California 94551-0808 (United States); Kilkenny, J. [General Atomics, P.O. Box 85608, San Diego, California 92186-5608 (United States)] [General Atomics, P.O. Box 85608, San Diego, California 92186-5608 (United States); Knauer, J. [Laboratory for Laser Energetics, 250 E. River Road Rochester, New York 14623-1212 (United States)] [Laboratory for Laser Energetics, 250 E. River Road Rochester, New York 14623-1212 (United States)

2014-04-15T23:59:59.000Z

137

Achieving competitive excellence in nuclear energy: The threat of proliferation; the challenge of inertial confinement fusion  

SciTech Connect

Nuclear energy will have an expanding role in meeting the twenty-first-century challenges of population and economic growth, energy demand, and global warming. These great challenges are non-linearly coupled and incompletely understood. In the complex global system, achieving competitive excellence for nuclear energy is a multi-dimensional challenge. The growth of nuclear energy will be driven by its margin of economic advantage, as well as by threats to energy security and by growing evidence of global warming. At the same time, the deployment of nuclear energy will be inhibited by concerns about nuclear weapons proliferation, nuclear waste and nuclear reactor safety. These drivers and inhibitors are coupled: for example, in the foreseeable future, proliferation in the Middle East may undermine energy security and increase demand for nuclear energy. The Department of Energy`s nuclear weapons laboratories are addressing many of these challenges, including nuclear weapons builddown and nonproliferation, nuclear waste storage and burnup, reactor safety and fuel enrichment, global warming, and the long-range development of fusion energy. Today I will focus on two major program areas at the Lawrence Livermore National Laboratory (LLNL): the proliferation of nuclear weapons and the development of inertial confinement fusion (ICF) energy.

Nuckolls, J.H.

1994-06-01T23:59:59.000Z

138

Progress in laboratory high gain ICF (inertial confinement fusion): Prospects for the future  

SciTech Connect

Inertial confinement fusion (ICF), a thermonuclear reaction in a small (/approximately/5 mm diameter) fuel capsule filled with a few milligrams of deuterium and tritium, has been the subject of very fruitful experimentation since the early 1970's. High gain ICF is now on the threshold of practical applications. With a Laboratory Microfusion Facility (LMF), these applications will have major implications for national defense, basic and applied science, and power production. With a driver capable of delivering about 10 MJ in a 10-ns pulse at an intensity of /approximately/3 /times/ 10/sup 14/ W/cm/sup 2/, an appropriately configured cryogenic capsule could be compressed to a density of about 200 g/cm/sup 3/ and a temperature of 3--5 keV. Under these conditions, up to 10 mg of DT could be ignited, and with a burn efficiency of about 30%, release up to 1000 MJ of fusion energy, an energy gain of about 100. A thousand megajoules is equivalent to about one quarter ton of TNT, or about 7 gallons of oil--an amount of energy tractable under laboratory conditions and potentially very useful for a variety of applications. 61 refs., 33 figs.

Storm, E.; Lindl, J.D.; Campbell, E.M.; Bernat, T.P.; Coleman, L.W.; Emmett, J.L.; Hogan, W.J.; Hunt, J.T.; Krupke, W.F.; Lowdermilk, W.H.

1988-01-01T23:59:59.000Z

139

KrF laser path to high gain ICF (inertial confinement fusion) laboratory microfusion facility  

SciTech Connect

The krypton-fluoride laser has many desirable features for inertial confinement fusion. Because it is a gas laser capable of operation with high efficiency, it is the only known laser candidate capable of meeting the driver requirements for inertial fusion energy (IFE) production. Los Alamos National Laboratory has defined a program plan to develop KrF lasers for IFE production. This plan develops the KrF laser and demonstrates the target performance in single-pulse facilities. A 100-kJ Laser Target Test Facility (LTTF) is proposed as the next step, to be followed by a 3 to 10-MJ Laboratory Microfusion Facility (LMF). The LTTF will resolve many target physics issues and accurately define the driver energy required for the LMF. It is also proposed that the technology development for IFE, such as the high-efficiency, high-reliability, repetitively pulsed driver, the reactor, mass production of targets, and the mechanism of injecting targets be developed in parallel with the single-pulse facilities. 11 refs., 4 figs.

Harris, D.B.; Sullivan, J.A.; Figueiro, J.F.; Cartwright, D.C.; McDonald, T.E.; Hauer, A.A.; Coggeshall, S.V.; Younger, S.M.

1990-01-01T23:59:59.000Z

140

D-T gamma-to-neutron branching ratio determined from inertial confinement fusion plasmasa)  

Science Journals Connector (OSTI)

A new deuterium-tritium (D-T)fusion gamma-to-neutron branching ratio [3H(d ?)5He/3H(d n)4He] value of (4.2??2.0)??10?5 was recently reported by this group [Y. Kim et al. Phys. Rev. C (submitted)]. This measurement conducted at the OMEGA laser facility located at the University of Rochester was made for the first time using inertial confinement fusion(ICF)plasmas. Neutron-induced backgrounds are significantly reduced in these experiments as compared to traditional beam-target accelerator-based experiments due to the short pulse nature of ICF implosions and the use of gas Cherenkov ?-ray detectors with fast temporal responses and inherent energy thresholds. It is expected that this ICF-based measurement will help resolve the large and long-standing inconsistencies in previously reported accelerator-based values which vary by a factor of approximately 30. The reported value at ICF conditions was determined by averaging the results of two methods: (1) a direct measurement of ICFD-T ?-ray and neutron emissions using absolutely calibrated detectors and (2) a separate cross-calibration against the better known D-3He gamma-to-proton branching ratio [3He(d ??)5Li/3He(d p)4He]. Here we include a detailed explanation of these results and introduce as a corroborative method an in-situ ?-ray detectorcalibration using neutron-induced ?-rays. Also by extending the established techniques to two additional series of implosions with significantly different ion temperatures we test the branching ratio dependence on ion temperature. The data show a D-T branching ratio is nearly constant over the temperature range 29?keV. These studies motivate further investigation into the 5He and 5Li systems resulting from D-T and D-3He fusion respectively and result in improved ICF ?-ray reaction history diagnosis at the National Ignition Facility.

Y. Kim; J. M. Mack; H. W. Herrmann; C. S. Young; G. M. Hale; S. Caldwell; N. M. Hoffman; S. C. Evans; T. J. Sedillo; A. McEvoy; J. Langenbrunner; H. H. Hsu; M. A. Huff; S. Batha; C. J. Horsfield; M. S. Rubery; W. J. Garbett; W. Stoeffl; E. Grafil; L. Bernstein; J. A. Church; D. B. Sayre; M. J. Rosenberg; C. Waugh; H. G. Rinderknecht; M. Gatu Johnson; A. B. Zylstra; J. A. Frenje; D. T. Casey; R. D. Petrasso; E. Kirk Miller; V. Yu Glebov; C. Stoeckl; T. C. Sangster

2012-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "magnetic confinement fusion" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


141

Advances in inertial confinement fusion at the National Ignition Facility (NIF)  

Science Journals Connector (OSTI)

The 192-beam National Ignition Facility (NIF) at the Lawrence Livermore National Laboratory (LLNL) in Livermore, CA, is now operational and conducting experiments. NIF, the flagship facility of the U.S. Inertial Confinement Fusion (ICF) Program, will achieve high-energy-density conditions never previously obtained in the laboratorytemperatures over 100 million K, densities of 1000g/cm3, and pressures exceeding 100 billion atmospheres. Such conditions exist naturally only in the interiors of the stars and during thermonuclear burn. Demonstration of ignition and thermonuclear burn in the laboratory is a major NIF goal. To date, the NIF laser has demonstrated all pulse shape, beam quality, energy, and other specifications required to meet the ignition challenge. On March 10, 2009, the NIF laser delivered 1.1MJ of ultraviolet laser energy to target chamber center, approximately 30 times more energy than any previous facility. The ignition program at NIF is the National Ignition Campaign (NIC), a national collaboration for ignition experimentation with participation from General Atomics, LLNL, Los Alamos National Laboratory (LANL), Sandia National Laboratories (SNL), and the University of Rochester Laboratory for Laser Energetics (LLE). The achievement of ignition at NIF will demonstrate the scientific feasibility of ICF and focus worldwide attention on fusion as a viable energy option. A particular energy concept under investigation is the LIFE (Laser Inertial Fusion Energy) scheme. The LIFE engine is inherently safe, minimizes proliferation concerns associated with the nuclear fuel cycle, and can provide a sustainable carbon-free energy generation solution in the 21st century. This talk will describe NIF and its potential as a user facility and an experimental platform for high-energy-density science, NIC, and the LIFE approach for clean, sustainable energy.

Edward I. Moses

2010-01-01T23:59:59.000Z

142

Advances in Inertial Confinement Fusion at the National Ignition Facility (NIF)  

SciTech Connect

The 192-beam National Ignition Facility (NIF) at the Lawrence Livermore National Laboratory (LLNL) in Livermore, CA, is now operational and conducting experiments. NIF, the flagship facility of the U.S. Inertial Confinement Fusion (ICF) Program, will achieve high-energy-density conditions never previously obtained in the laboratory - temperatures over 100 million K, densities of 1,000 g/cm3, and pressures exceeding 100 billion atmospheres. Such conditions exist naturally only in the interiors of the stars and during thermonuclear burn. Demonstration of ignition and thermonuclear burn in the laboratory is a major NIF goal. To date, the NIF laser has demonstrated all pulse shape, beam quality, energy, and other specifications required to meet the ignition challenge. On March 10, 2009, the NIF laser delivered 1.1 MJ of ultraviolet laser energy to target chamber center, approximately 30 times more energy than any previous facility. The ignition program at NIF is the National Ignition Campaign (NIC), a national collaboration for ignition experimentation with participation from General Atomics, LLNL, Los Alamos National Laboratory (LANL), Sandia National Laboratories (SNL), and the University of Rochester Laboratory for Laser Energetics (LLE). The achievement of ignition at NIF will demonstrate the scientific feasibility of ICF and focus worldwide attention on fusion as a viable energy option. A particular energy concept under investigation is the LIFE (Laser Inertial Fusion Energy) scheme. The LIFE engine is inherently safe, minimizes proliferation concerns associated with the nuclear fuel cycle, and can provide a sustainable carbon-free energy generation solution in the 21st century. This talk will describe NIF and its potential as a user facility and an experimental platform for high-energy-density science, NIC, and the LIFE approach for clean, sustainable energy.

Moses, E

2009-10-15T23:59:59.000Z

143

An Acoustically Driven Magnetized Target Fusion Reactor  

Science Journals Connector (OSTI)

We propose a new compression system that offers many advantages. A near spherical vessel ?2m in diameter is filled with liquid lead-lithium alloy (PbLi). This liquid is under consideration for fusion reactor bla...

Michel Laberge

2008-06-01T23:59:59.000Z

144

Road Map for a Modular Magnetic Fusion Program Dale M. Meade  

E-Print Network (OSTI)

1 Road Map for a Modular Magnetic Fusion Program Dale M. Meade Princeton Plasma Physics Laboratory Princeton University During the past several decades magnetic fusion has made outstanding progress in understanding the science of fusion plasmas, the achievement of actual fusion plasmas and the development of key

145

Magneto-inertial Fusion: An Emerging Concept for Inertial Fusion and Dense Plasmas in Ultrahigh Magnetic Fields  

SciTech Connect

An overview of the U.S. program in magneto-inertial fusion (MIF) is given in terms of its technical rationale, scientific goals, vision, research plans, needs, and the research facilities currently available in support of the program. Magneto-inertial fusion is an emerging concept for inertial fusion and a pathway to the study of dense plasmas in ultrahigh magnetic fields (magnetic fields in excess of 500 T). The presence of magnetic field in an inertial fusion target suppresses cross-field thermal transport and potentially could enable more attractive inertial fusion energy systems. A vigorous program in magnetized high energy density laboratory plasmas (HED-LP) addressing the scientific basis of magneto-inertial fusion has been initiated by the Office of Fusion Energy Sciences of the U.S. Department of Energy involving a number of universities, government laboratories and private institutions.

Thio, Francis Y.C.

2008-01-01T23:59:59.000Z

146

THE DEVELOPMENT OF HEAVY-ION ACCELERATORS AS DRIVERS FOR INERTIALLY CONFINED FUSION  

E-Print Network (OSTI)

BEAMS QF A P.ELLET FUSION REACTOR BY.fiUADRUPOLJ"DOUBLETS,prefer much smaller fusion reactors. In view of the evidencecertain that soie pure fusion reactor scenarios exist with

Herrmannsfeldt, W.b.

2010-01-01T23:59:59.000Z

147

Dynamic symmetry of indirectly driven inertial confinement fusion capsules on the National Ignition Facility  

SciTech Connect

In order to achieve ignition using inertial confinement fusion it is important to control the growth of low-mode asymmetries as the capsule is compressed. Understanding the time-dependent evolution of the shape of the hot spot and surrounding fuel layer is crucial to optimizing implosion performance. A design and experimental campaign to examine sources of asymmetry and to quantify symmetry throughout the implosion has been developed and executed on the National Ignition Facility (NIF) [E. I. Moses et al., Phys. Plasmas 16, 041006 (2009)]. We have constructed a large simulation database of asymmetries applied during different time intervals. Analysis of the database has shown the need to measure and control the hot-spot shape, areal density distribution, and symmetry swings during the implosion. The shape of the hot spot during final stagnation is measured using time-resolved imaging of the self-emission, and information on the shape of the fuel at stagnation can be obtained from Compton radiography [R. Tommasini et al., Phys. Plasmas 18, 056309 (2011)]. For the first time on NIF, two-dimensional inflight radiographs of gas-filled and cryogenic fuel layered capsules have been measured to infer the symmetry of the radiation drive on the capsule. These results have been used to modify the hohlraum geometry and the wavelength tuning to improve the inflight implosion symmetry. We have also expanded our shock timing capabilities by the addition of extra mirrors inside the re-entrant cone to allow the simultaneous measurement of shock symmetry in three locations on a single shot, providing asymmetry information up to Legendre mode 4. By diagnosing the shape at nearly every step of the implosion, we estimate that shape has typically reduced fusion yield by about 50% in ignition experiments.

Town, R. P. J., E-mail: town2@llnl.gov; Bradley, D. K.; Kritcher, A.; Jones, O. S.; Rygg, J. R.; Tommasini, R.; Barrios, M.; Benedetti, L. R.; Berzak Hopkins, L. F.; Celliers, P. M.; Dppner, T.; Dewald, E. L.; Eder, D. C.; Field, J. E.; Glenn, S. M.; Izumi, N.; Haan, S. W.; Khan, S. F.; Ma, T.; Milovich, J. L. [Lawrence Livermore National Laboratory, P.O. Box 808, Livermore, California 94551-0808 (United States); and others

2014-05-15T23:59:59.000Z

148

THE MAGNETIC CONFINEMENT OF ELECTRON AND PHOTON DOSE PROFILES AND THE POSSIBLE EFFECT OF THE MAGNETIC FIELD ON  

E-Print Network (OSTI)

THE MAGNETIC CONFINEMENT OF ELECTRON AND PHOTON DOSE PROFILES AND THE POSSIBLE EFFECT OF THE MAGNETIC FIELD ON RELATIVE BIOLOGICAL EFFECTIVENESS by Yu Chen A dissertation submitted in partial magnetic field can significantly improve electron beam dose profiles. This could permit improved targeting

Becchetti, Fred

149

Fast ignition of a compressed inertial confinement fusion hemispherical capsule by two proton beams  

Science Journals Connector (OSTI)

A hemispherical conically guided indirectly driven inertial confinement fusion capsule has been considered. The fast ignition of the precompressed capsule driven by one or two laser-accelerated proton beams has been numerically investigated. The energy distribution of the protons is Gaussian with a mean energy of 12 MeV and a full width at half maximum of 1 MeV . A new scheme that uses two laser-accelerated proton beams is proposed. It is found that the energy deposition of 1 kJ provided by a first proton beam generates a low-density cylindrical channel and launches a forward shock. A second proton beam delayed by a few tens of ps and driving the energy of 6 kJ crosses the low-density channel and heats the dense shocked region where the ignition of the deuterium-tritium nuclear fuel is achieved. For the considered capsule this new two-beam configuration reduces the ignition energy threshold to 7 kJ .

Mauro Temporal

2006-01-01T23:59:59.000Z

150

Optimized beryllium target design for indirectly driven inertial confinement fusion experiments on the National Ignition Facility  

SciTech Connect

For indirect drive inertial confinement fusion, Beryllium (Be) ablators offer a number of important advantages as compared with other ablator materials, e.g., plastic and high density carbon. In particular, the low opacity and relatively high density of Be lead to higher rocket efficiencies giving a higher fuel implosion velocity for a given X-ray drive; and to higher ablation velocities providing more ablative stabilization and reducing the effect of hydrodynamic instabilities on the implosion performance. Be ablator advantages provide a larger target design optimization space and can significantly improve the National Ignition Facility (NIF) [J. D. Lindl et al., Phys. Plasmas 11, 339 (2004)] ignition margin. Herein, we summarize the Be advantages, briefly review NIF Be target history, and present a modern, optimized, low adiabat, Revision 6 NIF Be target design. This design takes advantage of knowledge gained from recent NIF experiments, including more realistic levels of laser-plasma energy backscatter, degraded hohlraum-capsule coupling, and the presence of cross-beam energy transfer.

Simakov, Andrei N., E-mail: simakov@lanl.gov; Wilson, Douglas C.; Yi, Sunghwan A.; Kline, John L.; Batha, Steven H. [Los Alamos National Laboratory, P.O. Box 1663, Los Alamos, New Mexico 87545 (United States)] [Los Alamos National Laboratory, P.O. Box 1663, Los Alamos, New Mexico 87545 (United States); Clark, Daniel S.; Milovich, Jose L.; Salmonson, Jay D. [Lawrence Livermore National Laboratory, P.O. Box 808, Livermore, California 94551 (United States)] [Lawrence Livermore National Laboratory, P.O. Box 808, Livermore, California 94551 (United States)

2014-02-15T23:59:59.000Z

151

Metrics for long wavelength asymmetries in inertial confinement fusion implosions on the National Ignition Facility  

SciTech Connect

We investigate yield degradation due to applied low mode P2 and P4 asymmetries in layered inertial confinement fusion implosions. This study has been performed with a large database of >600 2D simulations. We show that low mode radiation induced drive asymmetries can result in significant deviation between the core hot spot shape and the fuel ?R shape at peak compression. In addition, we show that significant residual kinetic energy at peak compression can be induced by these low mode asymmetries. We have developed a metric, which is a function of the hot spot shape, fuel ?R shape, and residual kinetic energy at peak compression, that is well correlated to yield degradation due to low mode shape perturbations. It is shown that the ?R shape and residual kinetic energy cannot, in general, be recovered by inducing counter asymmetries to make the hot core emission symmetric. In addition, we show that the yield degradation due to low mode asymmetries is well correlated to measurements of time dependent shape throughout the entire implosion, including early time shock symmetry and inflight fuel symmetry.

Kritcher, A. L.; Town, R.; Bradley, D.; Clark, D.; Spears, B.; Jones, O.; Haan, S.; Springer, P. T.; Lindl, J.; Callahan, D.; Edwards, M. J.; Landen, O. L. [Lawrence Livermore National Laboratory, P.O. Box 808, Livermore, California 94551-0808 (United States)] [Lawrence Livermore National Laboratory, P.O. Box 808, Livermore, California 94551-0808 (United States); Scott, R. H. H. [Rutherford Appleton Laboratory, Chilton, Didcot, Oxfordshire (United Kingdom)] [Rutherford Appleton Laboratory, Chilton, Didcot, Oxfordshire (United Kingdom)

2014-04-15T23:59:59.000Z

152

Moderate-convergence inertial confinement fusion implosions in tetrahedral hohlraums at Omega  

SciTech Connect

A highly uniform thermal x-radiation field for indirect-drive inertial confinement fusion implosions may be obtained by irradiating a four-hole, tetrahedral geometry, spherical hohlraum with all 60 Omega laser beams. Implosion studies and calculations [J. M. Wallace et al., Phys. Rev. Lett. 82, 3807 (1999)] indicate a drive uniformity comparable to that expected for the National Ignition Facility [J. A. Painser et al., Laser Focus World 30, 75 (1994)]. With 60 beams distributed over the cavity wall, tetrahedral hohlraums have a natural insensitivity to power balance and pointing errors. Standard, smooth Nova capsules imploded with this drive indicate that moderate convergence-ratio implosions, Cr{approx}18, have measured-neutron yield to calculated-clean-one-dimensional-neutronyield ratios similar to those previously investigated using the comparatively poor drive uniformity of Nova cylindrical hohlraums. This may indicate that a nonsymmetry-related neutron yield degradation mechanism, e.g., hydrodynamic mixing of cold, dense ablator material with the hot-spot region or some combination of nonsymmetry effects, is dominating in this Cr regime. (c) 2000 American Institute of Physics.

Bennett, G. R. [Los Alamos National Laboratory, Los Alamos, New Mexico 87545-0001 (United States)] [Los Alamos National Laboratory, Los Alamos, New Mexico 87545-0001 (United States); Wallace, J. M. [Los Alamos National Laboratory, Los Alamos, New Mexico 87545-0001 (United States)] [Los Alamos National Laboratory, Los Alamos, New Mexico 87545-0001 (United States); Murphy, T. J. [Los Alamos National Laboratory, Los Alamos, New Mexico 87545-0001 (United States)] [Los Alamos National Laboratory, Los Alamos, New Mexico 87545-0001 (United States); Chrien, R. E. [Los Alamos National Laboratory, Los Alamos, New Mexico 87545-0001 (United States)] [Los Alamos National Laboratory, Los Alamos, New Mexico 87545-0001 (United States); Delamater, N. D. [Los Alamos National Laboratory, Los Alamos, New Mexico 87545-0001 (United States)] [Los Alamos National Laboratory, Los Alamos, New Mexico 87545-0001 (United States); Gobby, P. L. [Los Alamos National Laboratory, Los Alamos, New Mexico 87545-0001 (United States)] [Los Alamos National Laboratory, Los Alamos, New Mexico 87545-0001 (United States); Hauer, A. A. [Los Alamos National Laboratory, Los Alamos, New Mexico 87545-0001 (United States)] [Los Alamos National Laboratory, Los Alamos, New Mexico 87545-0001 (United States); Klare, K. A. [Los Alamos National Laboratory, Los Alamos, New Mexico 87545-0001 (United States)] [Los Alamos National Laboratory, Los Alamos, New Mexico 87545-0001 (United States); Oertel, J. A. [Los Alamos National Laboratory, Los Alamos, New Mexico 87545-0001 (United States)] [Los Alamos National Laboratory, Los Alamos, New Mexico 87545-0001 (United States); Watt, R. G. [Los Alamos National Laboratory, Los Alamos, New Mexico 87545-0001 (United States)] (and others) [Los Alamos National Laboratory, Los Alamos, New Mexico 87545-0001 (United States)

2000-06-01T23:59:59.000Z

153

Novel free-form hohlraum shape design and optimization for laser-driven inertial confinement fusion  

SciTech Connect

The hohlraum shape attracts considerable attention because there is no successful ignition method for laser-driven inertial confinement fusion at the National Ignition Facility. The available hohlraums are typically designed with simple conic curves, including ellipses, parabolas, arcs, or Lame curves, which allow only a few design parameters for the shape optimization, making it difficult to improve the performance, e.g., the energy coupling efficiency or radiation drive symmetry. A novel free-form hohlraum design and optimization approach based on the non-uniform rational basis spline (NURBS) model is proposed. In the present study, (1) all kinds of hohlraum shapes can be uniformly represented using NURBS, which is greatly beneficial for obtaining the optimal available hohlraum shapes, and (2) such free-form uniform representation enables us to obtain an optimal shape over a large design domain for the hohlraum with a more uniform radiation and higher drive temperature of the fuel capsule. Finally, a hohlraum is optimized and evaluated with respect to the drive temperature and symmetry at the Shenguang III laser facility in China. The drive temperature and symmetry results indicate that such a free-form representation is advantageous over available hohlraum shapes because it can substantially expand the shape design domain so as to obtain an optimal hohlraum with high performance.

Jiang, Shaoen; Jing, Longfei, E-mail: scmyking-2008@163.com; Ding, Yongkun [Laser Fusion Research Center, China Academy Engineering Physics, Mianyang 621900 (China); Huang, Yunbao, E-mail: huangyblhy@gmail.com [Mechatronics School of Guangdong University of Technology, Guangzhou 510006 (China)

2014-10-15T23:59:59.000Z

154

Real viscosity effects in inertial confinement fusion target deuteriumtritium micro-implosions  

SciTech Connect

We report on numerical studies of real viscous effects on the implosion characteristics of imploded DT micro-targets. We use the implicit ePLAS code to perform 2D simulations of spherical and slightly ellipsoidal DT shells on DT gas filled ?40??m diameter voids. Before their final implosions the shells have been nearly adiabatically compressed up to 10{sup 2} or 10{sup 3}?g/cm{sup 3} densities. While the use of conventional artificial viscosity can lead to high central densities for initially spherical shells, we find that a real physical viscosity from ion-ion collisions can give a high (>20?keV) central temperature but severely reduced central density (<200?g/cm{sup 3}), while the elliptical shells evidence p?=?2 distortion of the heated central fuel region. These results suggest that the general use of artificial viscosities in Inertial Confinement Fusion (ICF) modeling may have lead to overly optimistic yields for current NIF targets and that polar direct drive with more energy for the imploding capsule may be needed for ultimate ICF success.

Mason, R. J., E-mail: rodmason01@msn.com; Kirkpatrick, R. C.; Faehl, R. J. [Research Applications Corporation, Los Alamos, New Mexico 87544 (United States)] [Research Applications Corporation, Los Alamos, New Mexico 87544 (United States)

2014-02-15T23:59:59.000Z

155

An improved method for measuring the absolute DD neutron yield and calibrating neutron time-of-flight detectors in inertial confinement fusion experiments  

E-Print Network (OSTI)

Since the establishment of nuclear physics in the early 1900's and the development of the hydrogen bomb in the 1950's, inertial confinement fusion (ICF) has been an important field in physics. Funded largely though the ...

Waugh, C. (Caleb Joseph)

2014-01-01T23:59:59.000Z

156

Hamiltonian description of low frequency waves propagation and absorption in magnetically confined plasmas  

SciTech Connect

Magnetically confined fusion plasmas feature a large variety of waves. In the Ion Cyclotron Range of Frequencies (ICRF), radiofrequency waves are routinely used for plasma heating and non-inductive current-drive, whereas unstable modes in the Alfven range of frequencies are observed in ongoing experiments and are expected to play a crucial role in future devices. In experiments where Alfven and ICRF waves co-exist, a strong interplay between them is observed via the intermediary of the wave accelerated fast ions. A Hamiltonian description of the resonating particles is particularly well adapted to describe accurately their interaction with ICRF and Alfven waves. It provides a convenient framework for self-consistent calculations of the wave propagation and the kinetics of resonating plasma species. In the wave-field calculation, this formulation allows to account for non-local effects caused by wide fast particle orbits (e.g. wave accelerated fast ions and alpha particles). We present here the progress made in the development of the full-wave code EVE, based on a Hamiltonian description of the particle dynamics in terms of action-angle variables. The formalism of EVE, the numerical aspects, as well as some simulation results obtained with the code are discussed.

Dumont, R. J.; Eriksson, L.-G. [Association Euratom-CEA, CEA/DSM/DRFC, Centre de Cadarache, 13108 Saint-Paul-lez-Durance (France)

2006-11-30T23:59:59.000Z

157

Simultaneous usage of pinhole and penumbral apertures for imaging small scale neutron sources from inertial confinement fusion experiments  

SciTech Connect

Inertial confinement fusion experiments at the National Ignition Facility are designed to understand the basic principles of creating self-sustaining fusion reactions by laser driven compression of deuterium-tritium (DT) filled cryogenic plastic capsules. The neutron imaging diagnostic provides information on the distribution of the central fusion reaction region and the surrounding DT fuel by observing neutron images in two different energy bands for primary (13-17 MeV) and down-scattered (6-12 MeV) neutrons. From this, the final shape and size of the compressed capsule can be estimated and the symmetry of the compression can be inferred. These experiments provide small sources with high yield neutron flux. An aperture design that includes an array of pinholes and penumbral apertures has provided the opportunity to image the same source with two different techniques. This allows for an evaluation of these different aperture designs and reconstruction algorithms.

Guler, N.; Volegov, P.; Danly, C. R.; Grim, G. P.; Merrill, F. E.; Wilde, C. H. [Los Alamos National Laboratory, P.O. Box 1663, Los Alamos, New Mexico 87545 (United States)

2012-10-15T23:59:59.000Z

158

Magnetic particles confined in a modulated channel: structural transitions tunable by tilting a magnetic field  

E-Print Network (OSTI)

The ground state of colloidal magnetic particles in a modulated channel are investigated as function of the tilt angle of an applied magnetic field. The particles are confined by a parabolic potential in the transversal direction while in the axial direction a periodic substrate potential is present. By using Monte Carlo (MC) simulations, we construct a phase diagram for the different crystal structures as a function of the magnetic field orientation, strength of the modulated potential and the commensurability factor of the system. Interestingly, we found first and second order phase transitions between different crystal structures, which can be manipulated by the orientation of the external magnetic field. A re-entrant behavior is found between two- and four-chain configurations, with continuous second order transitions. Novel configurations are found consisting of frozen in solitons. By changing the orientation and/or strength of the magnetic field and/or the strength and the spatial frequency of the periodic substrate potential, the system transits through different phases.

J. E. Galvn-Moya; D. Lucena; W. P. Ferreira; F. M. Peeters

2014-01-03T23:59:59.000Z

159

Fusion Technologies for Tritium-Suppressed D-D Fusion White Paper prepared for FESAC Materials Science Subcommittee  

E-Print Network (OSTI)

1 Fusion Technologies for Tritium-Suppressed D-D Fusion White Paper prepared for FESAC Materials, Columbia University 2 Plasma Science and Fusion Center, MIT December 19, 2011 Summary The proposal for tritium-suppressed D-D fusion and the understanding of the turbulent pinch in magnetically confined plasma

160

Equilibrium and Stability Studies of Plasmas Confined in a Dipole Magnetic Field Using  

E-Print Network (OSTI)

Equilibrium and Stability Studies of Plasmas Confined in a Dipole Magnetic Field Using Magnetic Measurements by Ishtak Karim Submitted to the Department of Nuclear Science and Engineering in partial fulfillment of the requirements for the degree of Doctor of Science in Applied Plasma Physics

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161

MMMMaaaaggggnnnneeeettttiiiicccc FFFFuuuussssiiiioooonnnn EEEEnnnneeeerrrrggggyyyy MAGNETIC FUSION ENERGY  

E-Print Network (OSTI)

· ENVIRONMENTAL ADVANTAGES - NO CARBON EMISSIONS - LOW RADIOACTIVITY · CAN'T BLOW UP, CAN'T MELT DOWN - , WIND, ETC. - MINIMAL LAND USE · Not subject to daily, seasonal or regional weather variation. - NO NEED FFFFuuuussssiiiioooonnnn EEEEnnnneeeerrrrggggyyyy Schematic of MFE Power Plant Raw Fuel WasteFuel p First Wall Magnet

162

On the Existence and Location of the Free.Boundary for an Equilibrium Problem in Nuclear Fusion  

Science Journals Connector (OSTI)

We consider a non linear elliptic problem arising in the mathematical modeling of the nuclear fusion by magnetic confinement of a plasma in...

J. Francisco Padial

2011-01-01T23:59:59.000Z

163

FusEdWeb | Fusion Education  

NLE Websites -- All DOE Office Websites (Extended Search)

FAQ FAQ FusEdWeb: Discover Fusion CPEP's Online Fusion Course Fusion FAQ Fusion and Plasma Glossary Plasma Dictionary Student and Teacher Resources Education and Outreach Ideas Other Fusion and Plasma Sites Great Sites Internet Plasma Physics EXperience GA's Fusion Energy Slide Show International Thermonuclear Experimental Reactor National Ignition Facility Search webby award honoree Webby Awards Honoree April 10, 2007 webby award honoree Links2Go - Fusion, November 9, 1998 FusEdWeb: Fusion Energy Education Our Sun | Other Stars and Galaxies | Inertial Confinement | Magnetic Confinement Answers to Frequently Asked Questions about Fusion Research An updated, searchable Fusion FAQ is being prepared. In the meantime, the incomplete public-domain Fusion FAQ from 1994-1995 is still available

164

Study of internal magnetic field via polarimetry in fusion plasmas  

E-Print Network (OSTI)

Motivation Controlled thermonuclear fusion is a promising2007]. Controlled thermonuclear fusion is based on the

Zhang, Jie

2013-01-01T23:59:59.000Z

165

Neutron Transport and Nuclear Burnup Analysis for the Laser Inertial Confinement Fusion-Fission Energy (LIFE) Engine  

SciTech Connect

Lawrence Livermore National Laboratory is currently developing a hybrid fusion-fission nuclear energy system, called LIFE, to generate power and burn nuclear waste. We utilize inertial confinement fusion to drive a subcritical fission blanket surrounding the fusion chamber. It is composed of TRISO-based fuel cooled by the molten salt flibe. Low-yield (37.5 MJ) targets and a repetition rate of 13.3 Hz produce a 500 MW fusion source that is coupled to the subcritical blanket, which provides an additional gain of 4-8, depending on the fuel. In the present work, we describe the neutron transport and nuclear burnup analysis. We utilize standard analysis tools including, the Monte Carlo N-Particle (MCNP) transport code, ORIGEN2 and Monteburns to perform the nuclear design. These analyses focus primarily on a fuel composed of depleted uranium not requiring chemical reprocessing or enrichment. However, other fuels such as weapons grade plutonium and highly-enriched uranium are also under consideration. In addition, we have developed a methodology using {sup 6}Li as a burnable poison to replace the tritium burned in the fusion targets and to maintain constant power over the lifetime of the engine. The results from depleted uranium analyses suggest up to 99% burnup of actinides is attainable while maintaining full power at 2GW for more than five decades.

Kramer, K J; Latkowski, J F; Abbott, R P; Boyd, J K; Powers, J J; Seifried, J E

2008-10-24T23:59:59.000Z

166

RAMI Analysis Program Design and Research for CFETR (Chinese Fusion Engineering Testing Reactor) Tokamak Machine  

Science Journals Connector (OSTI)

Chinese Fusion Engineering Testing Reactor (CFETR) is a test reactor which shall be constructed by National Integration Design Group for Magnetic Confinement Fusion Reactor of China with an ambitious scientific ...

Shijun Qin; Yuntao Song; Damao Yao; Yuanxi Wan; Songtao Wu

2014-10-01T23:59:59.000Z

167

Influence of Quantum Confinement on the Electronic and Magnetic Properties  

E-Print Network (OSTI)

of magnetic semiconducting nanoparticles, and the production of magnetically doped II- VI, including CdS,11 Zn in diameter. Below this size, the doped holes are significantly self-trapped by the Mn sites, signaling both valence and electronic transitions. Our results imply that magnetically doped III-V nanoparticles

Sanvito, Stefano

168

Failure modes and effects analysis of fusion magnet systems  

SciTech Connect

A failure modes and consequence analysis of fusion magnet system is an important contributor towards enhancing the design by improving the reliability and reducing the risk associated with the operation of magnet systems. In the first part of this study, a failure mode analysis of a superconducting magnet system is performed. Building on the functional breakdown and the fault tree analysis of the Toroidal Field (TF) coils of the Next European Torus (NET), several subsystem levels are added and an overview of potential sources of failures in a magnet system is provided. The failure analysis is extended to the Poloidal Field (PF) magnet system. Furthermore, an extensive analysis of interactions within the fusion device caused by the operation of the PF magnets is presented in the form of an Interaction Matrix. A number of these interactions may have significant consequences for the TF magnet system particularly interactions triggered by electrical failures in the PF magnet system. In the second part of this study, two basic categories of electrical failures in the PF magnet system are examined: short circuits between the terminals of external PF coils, and faults with a constant voltage applied at external PF coil terminals. An electromagnetic model of the Compact Ignition Tokamak (CIT) is used to examine the mechanical load conditions for the PF and the TF coils resulting from these fault scenarios. It is found that shorts do not pose large threats to the PF coils. Also, the type of plasma disruption has little impact on the net forces on the PF and the TF coils. 39 refs., 30 figs., 12 tabs.

Zimmermann, M; Kazimi, M S; Siu, N O; Thome, R J

1988-12-01T23:59:59.000Z

169

Progress with developing a target for magnetized target fusion  

SciTech Connect

Magnetized Target Fusion (MTF) is an approach to fusion where a preheated and magnetized plasma is adiabatically compressed to fusion conditions. Successful MTF requires a suitable initial target plasma with an embedded magnetic field of at least 5 T in a closed-field-line topology, a density of roughly 10{sup 18} cm{sup {minus}3}, a temperature of at least 50 eV, and must be free of impurities which would raise radiation losses. Target plasma generation experiments are underway at Los Alamos National Laboratory using the Colt facility; a 0.25 MJ, 2--3 {micro}s rise-time capacitor bank. The goal of these experiments is to demonstrate plasma conditions meeting the minimum requirements for a MTF initial target plasma. In the first experiments, a Z-pinch is produced in a 2 cm radius by 2 cm high conducting wall using a static gas-fill of hydrogen or deuterium gas in the range of 0.5 to 2 torr. Thus far, the diagnostics include an array of 12 B-dot probes, framing camera, gated OMA visible spectrometer, time-resolved monochrometer, filtered silicon photodiodes, neutron yield, and plasma-density interferometer. These diagnostics show that a plasma is produced in the containment region that lasts roughly 10 to 20 {micro}s with a maximum plasma density exceeding 10{sup 18} cm{sup {minus}3}. The experimental design and data are presented.

Wysocki, F.J.; Chrien, R.E.; Idzorek, G.; Oona, H.; Whiteson, D.O.; Kirkpatrick, R.C.; Lindemuth, I.R.; Sheehey, P.T.

1997-09-01T23:59:59.000Z

170

A Magnetic Diagnostic Code for 3D Fusion Equilibria  

SciTech Connect

A synthetic magnetic diagnostics code for fusion equilibria is presented. This code calculates the response of various magnetic diagnostics to the equilibria produced by the VMEC and PIES codes. This allows for treatment of equilibria with both good nested flux surfaces and those with stochastic regions. DIAGNO v2.0 builds upon previous codes through the implementation of a virtual casing principle. The codes is validated against a vacuum shot on the Large Helical Device where the vertical field was ramped. As an exercise of the code, the diagnostic response for various equilibria are calculated on the Large Helical Device (LHD).

Samuel Aaron Lazerson

2012-07-27T23:59:59.000Z

171

A Magnetic Diagnostic Code for 3D Fusion Equilibria  

SciTech Connect

A synthetic magnetic diagnostics code for fusion equilibria is presented. This code calculates the response of various magnetic diagnostics to the equilibria produced by the VMEC and PIES codes. This allows for treatment of equilibria with both good nested flux surfaces and those with stochastic regions. DIAGNO v2.0 builds upon previous codes through the implementation of a virtual casing principle. The code is validated against a vacuum shot on the Large Helical Device (LHD) where the vertical field was ramped. As an exercise of the code, the diagnostic response for various equilibria are calculated on the LHD.

Samuel A. Lazerson, S. Sakakibara and Y. Suzuki

2013-03-12T23:59:59.000Z

172

THE PATH TOWARD MAGNETIC FUSION ENERGY DEMONSTRATON AND THE ROLE OF ITER  

E-Print Network (OSTI)

and component scale phenomena. FNST testing in fusion facilities prior to DEMO can be classified into three conducting magnets. 1. Introduction: Fusion has great potential to be a sustainable energy source. There are five pillar

Abdou, Mohamed

173

Inertial confinement fusion. Quarterly report, July--September 1993: Volume 3, No. 4  

SciTech Connect

This report discusses the following research: Diode-pumped solid- state-laser driver for inertial fusion energy power plants; Longitudinal beam dynamics in heavy ion fusion accelerators; Design of the ion sources for heavy ion fusion; Measurement of electron density in laser-produced plasma with a soft x-ray moire deflectometer; and Analysis of weakly nonlinear three-dimensional Rayleigh-Taylor instability growth.

Sacks, R.A.; Murphy, P.W.; Schleich, D.P. [eds.

1993-12-31T23:59:59.000Z

174

Single crystal growth and formation of defects in deuterium-tritium layers for inertial confinement nuclear fusion  

SciTech Connect

We identify vapor-etched grain boundary grooves on the solid-vapor interface as the main source of surface roughness in the deuterium-tritium (D-T) fuel layers, which are solidified and then cooled. Current inertial confinement fusion target designs impose stringent limits to the cross-sectional area and total volume of these grooves. Formation of these grain boundaries occurs over time scales of hours as the dislocation network anneals and is inevitable in a plastically deformed material. Therefore, either cooling on a much shorter time scale or a technique that requires no cooling after solidification should be used to minimize the roughness.

Chernov, A. A.; Kozioziemski, B. J.; Koch, J. A.; Atherton, L. J.; Johnson, M. A.; Hamza, A. V.; Kucheyev, S. O.; Lugten, J. B.; Mapoles, E. A.; Moody, J. D.; Salmonson, J. D.; Sater, J. D. [Lawrence Livermore National Laboratory, 7000 East Avenue Livermore, California 94551 (United States)

2009-02-09T23:59:59.000Z

175

Single Crystal Growth and Formation of Defects in Deuterium-Tritium Ice Layers for Inertial Confinement Fusion  

SciTech Connect

We identify vapor-etched grain boundary grooves on the solid-vapor interface as the main source of surface roughness in the Deuterium-Tritium (D-T) fuel layers which are solidified and then cooled. Current inertial confinement fusion target designs impose stringent limits to the cross sectional area and total volume of these grooves. Formation of these grain boundaries occurs over timescales of hours as the dislocation network anneals, and is inevitable in a plastically deformed material. Therefore, either cooling on a much shorter time scale or a technique that requires no cooling after solidification should be used to minimize the fuel layer surface roughness.

Chernov, A A; Kozioziemski, B J; Koch, J A; Atherton, L J; Johnson, M A; Hamza, A V; Kucheyev, S O; Lugten, J B; Mapoles, E A; Moody, J D; Salmonson, J D; Sater, J D

2008-09-05T23:59:59.000Z

176

Applications of high-speed dust injection to magnetic fusion  

SciTech Connect

It is now an established fact that a significant amount of dust is produced in magnetic fusion devices due to plasma-wall interactions. Dust inventory must be controlled, in particular for the next-generation steady-state fusion machines like ITER, as it can pose significant safety hazards 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. We have recognized that dust transport, dust-plasma interactions in magnetic fusion devices can be effectively studied experimentally by injection of dust with known properties into fusion plasmas. Other applications of injected dust include diagnosis of fusion plasmas and edge localized mode (ELM)'s pacing. In diagnostic applications, dust can be regarded as a source of transient neutrals before complete ionization. ELM's pacing is a promising scheme to prevent disruptions and type I ELM's that can cause catastrophic damage to fusion machines. Different implementation schemes are available depending on applications of dust injection. One of the simplest dust injection schemes is through gravitational acceleration of dust in vacuum. Experiments at Los Alamos and Princeton will be described, both of which use piezoelectric shakers to deliver dust to plasma. In Princeton experiments, spherical particles (40 micron) have been dropped in a systematic and reproducible manner using a computer-controlled piezoelectric bending actuator operating at an acoustic (0,2) resonance. The circular actuator was constructed with a 2.5 mm diameter central hole. At resonance ({approx} 2 kHz) an applied sinusoidal voltage has been used to control the flux of particles exiting the hole. A simple screw throttle located {approx}1mm above the hole has been used to set the magnitude of the flux achieved for a given voltage. Particle fluxes ranging from a few tens of particle per second up to thousands of particles per second have been achieved using this simple device. To achieve higher dust injection speed, another key consideration is how to accelerate dust at controlled amount. In addition to gravity, other possible acceleration mechanisms include electrostatic, electromagnetic, gas-dragged, plasma-dragged, and laser-ablation-based acceleration. Features and limitations of the different acceleration methods will be discussed. We will also describe laboratory experiments on dust acceleration.

Wang, Zhehui [Los Alamos National Laboratory; Li, Yangfang [Max Planck Institute for Extraterrestrial Physics, Germany

2012-08-08T23:59:59.000Z

177

THE DEVELOPMENT OF HEAVY-ION ACCELERATORS AS DRIVERS FOR INERTIALLY CONFINED FUSION  

E-Print Network (OSTI)

tion of fusion could provide the world with an energy sourcefusion power is to provide an inex haustible source of energy

Herrmannsfeldt, W.b.

2010-01-01T23:59:59.000Z

178

FusEdWeb | Fusion Education  

NLE Websites -- All DOE Office Websites (Extended Search)

Our Sun Our Sun FusEdWeb: Discover Fusion CPEP's Online Fusion Course Fusion FAQ Fusion and Plasma Glossary Plasma Dictionary Student and Teacher Resources Education and Outreach Ideas Other Fusion and Plasma Sites Great Sites Internet Plasma Physics EXperience GA's Fusion Energy Slide Show International Thermonuclear Experimental Reactor National Ignition Facility Search webby award honoree Webby Awards Honoree April 10, 2007 webby award honoree Links2Go - Fusion, November 9, 1998 FusEdWeb: Fusion Energy Education Our Sun | Other Stars and Galaxies | Inertial Confinement | Magnetic Confinement The Sun Runs on Fusion Energy How the sun looks through x-ray eyes! Like all stars, the sun is a huge fusion reactor, pumping out 100 million times as much energy in a single second as the entire population of Earth

179

High-field, high-current-density, stable superconducting magnets for fusion machines  

SciTech Connect

Designs for large fusion machines require high-performance superconducting magnets to reduce cost or increase machine performance. By employing force-flow cooling, cable-in-conduit conductor configuration, and NbTi superconductor, it is now possible to design superconducting magnets that operate a high fields (8-12 T) with high current densities (5-15 kA/cm/sup 2/ over the winding pack) in a stable manner. High current density leads to smaller, lighter, and thus less expensive coils. The force-flow cooling provides confined helium, full conductor insulation, and a rigid winding pack for better load distribution. The cable-in-conduit conductor configuration ensures a high stability margin for the magnet. The NbTi superconductor has reached a good engineering material standard. Its strain-insensitive critical parameters are particularly suitable for complex coil windings of a stellarator machine. The optimization procedure for such a conductor design, developed over the past decade, is summarized here. If desired a magnet built on the principles outlines in this paper can be extended to a field higher than the design value without degrading its stability by simply lowering the operating temperature below 4.2 K. 11 refs., 3 figs.

Lue, J.W.; Dresner, L.; Lubell, M.S.

1989-01-01T23:59:59.000Z

180

Inertial Confinement Fusion, High Energy Density Plasmas and an Energy Source on Earth  

E-Print Network (OSTI)

Driver Laser h=5-10% Heavy ion Accelerator h=15-40% Z-pinch h~15% Ignition by stagnation of convergent good progress toward achieving fusion ignition and high gain for energy applications We are making good progress toward achievingWe are making good progress toward achieving fusion ignition and high gain

Note: This page contains sample records for the topic "magnetic confinement fusion" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


181

Study of internal magnetic field via polarimetry in fusion plasmas  

E-Print Network (OSTI)

to exploit in a fusion reactor on earth is the fusion of thethis process in a fusion reactor for power generationSince the cost of the fusion reactor increases with the

Zhang, Jie

2013-01-01T23:59:59.000Z

182

Solenoid transport of a heavy ion beam for warm dense matterstudies and inertial confinement fusion  

SciTech Connect

From February to July 2006, I have been doing research as a guest at Lawrence Berkeley National Laboratory (LBNL), in the Heavy Ion Fusion group. This internship, which counts as one semester in my master's program in France, I was very pleased to do it in a field that I consider has the beauty of fundamental physics, and at the same time the special appeal of a quest for a long-term and environmentally-respectful energy source. During my stay at LBNL, I have been involved in three projects, all of them related to Neutralized Drift Compression Experiment (NDCX). The first one, experimental and analytical, has consisted in measuring the effects of the eddy currents induced by the pulsed magnets in the conducting plates of the source and diagnostic chambers of the Solenoid Transport Experiment (STX, which is a subset of NDCX). We have modeled the effect and run finite-element simulations that have reproduced the perturbation to the field. Then, we have modified WARP, the Particle-In-Cell code used to model the whole experiment, in order to import realistic fields including the eddy current effects and some details of each magnet. The second project has been to take part in a campaign of WARP simulations of the same experiment to understand the leakage of electrons that was observed in the experiment as a consequence to some diagnostics and the failure of the electrostatic electron trap. The simulations have shown qualitative agreement with the measured phenomena, but are still in progress. The third project, rather theoretical, has been related to the upcoming target experiment of a thin aluminum foil heated by a beam to the 1-eV range. At the beginning I helped by analyzing simulations of the hydrodynamic expansion and cooling of the heated material. But, progressively, my work turned into making estimates for the nature of the liquid/vapor two-phase flow. In particular, I have been working on criteria and models to predict the formation of droplets, their size, and their partial or total evaporation in the expanding flow.

Armijo, Julien

2006-10-01T23:59:59.000Z

183

MAGNETIC FIELD CONFINEMENT IN THE SOLAR CORONA. II. FIELD-PLASMA INTERACTION B. Fornberg,2  

E-Print Network (OSTI)

MAGNETIC FIELD CONFINEMENT IN THE SOLAR CORONA. II. FIELD-PLASMA INTERACTION N. Flyer,1 B. Fornberg numerically to generate a continuum of solutions with two parameters to control the total azimuthal flux from the study to the solar corona and the energetics of coronal mass ejections and flares. Subject

Fornberg, Bengt

184

Beryllium pressure vessels for creep tests in magnetic fusion energy  

SciTech Connect

Beryllium has interesting applications in magnetic fusion experimental machines and future power-producing fusion reactors. Chief among the properties of beryllium that make these applications possible is its ability to act as a neutron multiplier, thereby increasing the tritium breeding ability of energy conversion blankets. Another property, the behavior of beryllium in a 14-MeV neutron environment, has not been fully investigated, nor has the creep behavior of beryllium been studied in an energetic neutron flux at thermodynamically interesting temperatures. This small beryllium pressure vessel could be charged with gas to test pressures around 3, 000 psi to produce stress in the metal of 15,000 to 20,000 psi. Such stress levels are typical of those that might be reached in fusion blanket applications of beryllium. After contacting R. Powell at HEDL about including some of the pressure vessels in future test programs, we sent one sample pressure vessel with a pressurizing tube attached (Fig. 1) for burst tests so the quality of the diffusion bond joints could be evaluated. The gas used was helium. Unfortunately, budget restrictions did not permit us to proceed in the creep test program. The purpose of this engineering note is to document the lessons learned to date, including photographs of the test pressure vessel that show the tooling necessary to satisfactorily produce the diffusion bonds. This document can serve as a starting point for those engineers who resume this task when funds become available.

Neef, W.S.

1990-07-20T23:59:59.000Z

185

Magnetic Charge Lattices, Moduli Spaces and Fusion Rules  

E-Print Network (OSTI)

We analyze the set of magnetic charges carried by smooth BPS monopoles in Yang-Mills-Higgs theory with arbitrary gauge group G spontaneously broken to a subgroup H. The charges are restricted by a generalized Dirac quantization condition and by an inequality due to Murray. Geometrically, the set of allowed charges is a solid cone in the coroot lattice of G, which we call the Murray cone. We argue that magnetic charge sectors correspond to points in the Murray cone divided by the Weyl group of H; hence magnetic charge sectors are labelled by dominant integral weights of the dual group H*. We define generators of the Murray cone modulo Weyl group, and interpret the monopoles in the associated magnetic charge sectors as basic; monopoles in sectors with decomposable charges are interpreted as composite configurations. This interpretation is supported by the dimensionality of the moduli spaces associated to the magnetic charges and by classical fusion properties for smooth monopoles in particular cases. Throughout the paper we compare our findings with corresponding results for singular monopoles recently obtained by Kapustin and Witten.

L. Kampmeijer; J. K. Slingerland; B. J. Schroers; F. A. Bais

2008-03-24T23:59:59.000Z

186

FusEdWeb | Fusion Education  

NLE Websites -- All DOE Office Websites (Extended Search)

Glossary Glossary FusEdWeb: Discover Fusion CPEP's Online Fusion Course Fusion FAQ Fusion and Plasma Glossary Plasma Dictionary Student and Teacher Resources Education and Outreach Ideas Other Fusion and Plasma Sites Great Sites Internet Plasma Physics EXperience GA's Fusion Energy Slide Show International Thermonuclear Experimental Reactor National Ignition Facility Search webby award honoree Webby Awards Honoree April 10, 2007 webby award honoree Links2Go - Fusion, November 9, 1998 FusEdWeb: Fusion Energy Education Our Sun | Other Stars and Galaxies | Inertial Confinement | Magnetic Confinement The Glossary of Plasma Physics and Fusion Energy Research Browse | Search | Submit an Entry Introduction, Sources and Contributors This Glossary seeks to provide plain-language definitions of over 3600

187

FusEdWeb | Fusion Education  

NLE Websites -- All DOE Office Websites (Extended Search)

Home> Student and Teacher Resources > For Introductory Students Home> Student and Teacher Resources > For Introductory Students FusEdWeb: Discover Fusion CPEP's Online Fusion Course Fusion FAQ Fusion and Plasma Glossary Plasma Dictionary Student and Teacher Resources Education and Outreach Ideas Other Fusion and Plasma Sites Great Sites Internet Plasma Physics EXperience GA's Fusion Energy Slide Show International Thermonuclear Experimental Reactor National Ignition Facility Search webby award honoree Webby Awards Honoree April 10, 2007 webby award honoree Links2Go - Fusion, November 9, 1998 FusEdWeb: Fusion Energy Education Our Sun | Other Stars and Galaxies | Inertial Confinement | Magnetic Confinement Guide to Fusion Education Resources for Introductory Physics Students This is a compilation of online and offline education resources for

188

FusEdWeb | Fusion Education  

NLE Websites -- All DOE Office Websites (Extended Search)

About Us About Us FusEdWeb: Discover Fusion CPEP's Online Fusion Course Fusion FAQ Fusion and Plasma Glossary Plasma Dictionary Student and Teacher Resources Education and Outreach Ideas Other Fusion and Plasma Sites Great Sites Internet Plasma Physics EXperience GA's Fusion Energy Slide Show International Thermonuclear Experimental Reactor National Ignition Facility Search webby award honoree Webby Awards Honoree April 10, 2007 webby award honoree Links2Go - Fusion, November 9, 1998 FusEdWeb: Fusion Energy Education Our Sun | Other Stars and Galaxies | Inertial Confinement | Magnetic Confinement Webby Honoree graphic graphic Key Resource Snap editors choice new scientist DrMatrix Webby Awards Honoree, April 10, 2007 The Alchemist - WebPick, January 29, 1999 Links2Go - Fusion, November 9, 1998 October 19, 1998 - October 19, 1999 Site of the Day, September 24, 1998. Hot spot. Student Science Resource, April 16, 1997

189

Effect of low transverse magnetic field on the confinement strength in a quasi-1D wire  

SciTech Connect

Transport measurements in a quasi-one dimensional (1D) quantum wire are reported in the presence of low transverse magnetic field. Differential conductance shows weak quantised plateaus when the 2D electrons are squeezed electrostatically. Application of a small transverse magnetic field (0.2T) enhances the overall degree of quantisation due to the formation of magneto-electric subbands. The results show the role of magnetic field to fine tune the confinement strength in low density wires when interaction gives rise to double row formation.

Kumar, Sanjeev [London Centre for Nanotechnology, University College London, 17-19 Gordon Street, London WC1H 0AH (United Kingdom); Thomas, K. J. [London Centre for Nanotechnology, University College London, 17-19 Gordon Street, London WC1H 0AH, UK and Department of Electronic and Electrical Engineering, Sungkyunkwan University, Suwon 440-746 (Korea, Republic of); Smith, L. W.; Farrer, I.; Ritchie, D. A.; Jones, G. A. C.; Griffiths, J. [Cavendish Laboratory, J. J. Thomson Avenue, Cambridge CB3 OHE (United Kingdom); Pepper, M. [London Centre for Nanotechnology, University College London, 17-19 Gordon Street, London WC1H 0AH, UK and Department of Electrical and Electronic Engineering, Torrington Place, London WC1E 7JE (United Kingdom)

2013-12-04T23:59:59.000Z

190

12th IAEA Technical Meeting on Energetic Particles in Magnetic Confinement Systems  

SciTech Connect

The 12th IAEA Technical Meeting on Energetic Particles in Magnetic Confinement Systems took place in Austin, Texas (711 September 2011). This meeting was organized jointly with the 5th IAEA Technical Meeting on Theory of Plasma Instabilities (57 September 2011). The two meetings shared one day (7 September 2011) with presentations relevant to both groups. Some of the work reported at these meetings was then published in a special issue of Nuclear Fusion [Nucl. Fusion 52 (2012)]. Summaries of the Energetic Particle Conference presentations were given by Kazuo Toi and Boris Breizman. They respectively discussed the experimental and theoretical progress presented at the meeting. Highlights of this meeting include the tremendous progress that has been achieved in the development of diagnostics that enables the viewing of internal fluctuations and allows comparison with theoretical predictions, as demonstrated, for example, in the talks of P. Lauber and M. Osakabe. The need and development of hardened diagnostics in the severe radiation environment, such as those that will exist in ITER, was discussed in the talks of V. Kiptily and V.A. Kazakhov. In theoretical studies, much of the effort is focused on nonlinear phenomena. For example, detailed comparison of theory and experiment on D-III-D on the n = 0 geodesic mode was reported in separate papers by R. Nazikian and G. Fu. A large number of theoretical papers were presented on wave chirping including a paper by B.N. Breizman, which notes that wave chirping from a single frequency may emanate continuously once marginal stability conditions have been established. Another area of wide interest was the detailed study of alpha orbits in a burning plasma, where losses can come from symmetry breaking due to finite coil number or magnetic field imperfections introduced by diagnostic or test modules. An important area of development, covered by M.A. Hole and D.A. Spong, is concerned with the self-consistent treatment of the induced fields that accounts for toroidally asymmetric MHD response. In addition, a significant number of studies focused on understanding nonlinear behavior by means of computer simulation of energetic particle driven instability. An under-represented area of investigation was the study of electron runaway formation during major tokamak disruptions. It was noted in an overview by S. Putvinski that electron energies in the 1020 MeV range is to be expected during projected major disruptions in ITER and that reliable methods for mitigation of the runaway process needs to be developed. Significant recent work in the field of the disruption induced electron runaway, which was reported by J. Riemann, had been submitted to Physics of Plasmas [3]. Overall it is clear that reliable mitigation of electron runaway is an extremely important topic that is in need of better understanding and solutions.

Berk, Herbert L.; Breizman, Boris N.

2014-02-21T23:59:59.000Z

191

Experimental Demonstration of Fusion-Relevant Conditions in Magnetized Liner Inertial Fusion  

Science Journals Connector (OSTI)

This Letter presents results from the first fully integrated experiments testing the magnetized liner inertial fusion concept [S.?A. Slutz et al., Phys. Plasmas 17, 056303 (2010)], in which a cylinder of deuterium gas with a preimposed 10T axial magnetic field is heated by Z beamlet, a 2.5kJ, 1TW laser, and magnetically imploded by a 19MA, 100ns rise time current on the Z facility. Despite a predicted peak implosion velocity of only 70??km/s, the fuel reaches a stagnation temperature of approximately 3keV, with Te?Ti, and produces up to 21012 thermonuclear deuterium-deuterium neutrons. X-ray emission indicates a hot fuel region with full width at half maximum ranging from 60 to 120???m over a 6mm height and lasting approximately 2ns. Greater than 1010 secondary deuterium-tritium neutrons were observed, indicating significant fuel magnetization given that the estimated radial areal density of the plasma is only 2??mg/cm2.

M.?R. Gomez et al.

2014-10-06T23:59:59.000Z

192

Evidence for Stratification of Deuterium-Tritium Fuel in Inertial Confinement Fusion Implosions  

E-Print Network (OSTI)

Measurements of the D(d,p)T (dd) and T(t,2n)[superscript 4]He (tt) reaction yields have been compared with those of the D(t,n)[superscript 4]He (dt) reaction yield, using deuterium-tritium gas-filled inertial confinement ...

Casey, Daniel Thomas

193

Seiberg-Witten and 'Polyakov-like' Magnetic Bion Confinements are Continuously Connected  

SciTech Connect

We study four-dimensional N = 2 supersymmetric pure-gauge (Seiberg-Witten) theory and its N = 1 mass perturbation by using compactification on S{sup 1} x R{sup 3}. It is well known that on R{sup 4} (or at large S{sup 1} size L) the perturbed theory realizes confinement through monopole or dyon condensation. At small S{sup 1}, we demonstrate that confinement is induced by a generalization of Polyakov's three-dimensional instanton mechanism to a locally four-dimensional theory - the magnetic bion mechanism - which also applies to a large class of nonsupersymmetric theories. Using a large- vs. small-L Poisson duality, we show that the two mechanisms of confinement, previously thought to be distinct, are in fact continuously connected.

Poppitz, Erich; /Toronto U.; Unsal, Mithat; /SLAC /Stanford U., Phys. Dept.

2012-06-01T23:59:59.000Z

194

TORE SUPRA : Physics, Technology and ...Strategy - Andre GROSMAN - Deputy Head of Magnetic Fusion Research Institute (CEA/DSM/IRFM)  

E-Print Network (OSTI)

TORE SUPRA : Physics, Technology and ...Strategy - Andre GROSMAN - Deputy Head of Magnetic Fusion Research Institute (CEA/DSM/IRFM)

CERN. Geneva

2011-01-01T23:59:59.000Z

195

Confinement Of Pure Ion Plasma In A Cylindrical Current Sheet  

E-Print Network (OSTI)

j ?B force. An equilibrium calculation using a relativistic, 1-D, cold-fluid model shows: the confine- ment of non-neutral ion plasmas that are adequately dense for controlled thermonu- clear fusion limit? Conventional magnetic fusion devices contain quasi-neutral plasmas in a toroidal or linear

196

A compact proton spectrometer for measurement of the absolute DD proton spectrum from which yield and R are determined in thin-shell inertial-confinement-fusion  

E-Print Network (OSTI)

Energetics, University of Rochester, Rochester, New York 14623, USA 3 Lawrence Livermore National Laboratory neutron spectrometer for characterizing inertial confinement fusion implosions at OMEGA and the NIF Rev, Livermore, California 94550, USA 4 General Atomics, San Diego, California 92186, USA (Received 5 June 2014

197

Sub-100 nm Confinement of Magnetic Nanoparticles Using Localized Magnetic Field Gradients  

E-Print Network (OSTI)

that generate large magnetic gradients. In a homogeneous magnetic field, the field lines are parallel; that is, then the field lines converge into the ferromagnet. This convergence forms a shallow magnetic field gradient, to minimize the magnetic potential energy, the field lines exiting one magnet converge into the other magnet

Prentiss, Mara

198

A Snowflake-Shaped Magnetic Field Holds Promise for Taming Harsh Fusion  

NLE Websites -- All DOE Office Websites (Extended Search)

A Snowflake-Shaped Magnetic Field Holds Promise for Taming Harsh Fusion A Snowflake-Shaped Magnetic Field Holds Promise for Taming Harsh Fusion Plasmas Fusion Energy Sciences (FES) FES Home About Research Facilities Science Highlights Benefits of FES Funding Opportunities Fusion Energy Sciences Advisory Committee (FESAC) News & Resources Contact Information Fusion Energy Sciences U.S. Department of Energy SC-24/Germantown Building 1000 Independence Ave., SW Washington, DC 20585 P: (301) 903-4941 F: (301) 903-8584 E: sc.fes@science.doe.gov More Information » October 2012 A Snowflake-Shaped Magnetic Field Holds Promise for Taming Harsh Fusion Plasmas Recent experiments have confirmed the great potential of a novel plasma-material interface concept. Print Text Size: A A A Subscribe FeedbackShare Page Click to enlarge photo. Enlarge Photo

199

Magnetic discrete gauge field in the confining vacua and the supersymmetric index  

E-Print Network (OSTI)

It has recently been argued that the confining vacua of Yang-Mills theory in the far infrared can have topological degrees of freedom given by magnetic $\\mathbb{Z}_q$ gauge field, both in the non-supersymmetric case and in the N=1 supersymmetric case. In this short note we give another piece of evidence by computing and matching the supersymmetric index of the pure super Yang-Mills theory both in the ultraviolet and in the infrared.

Tachikawa, Yuji

2014-01-01T23:59:59.000Z

200

Magnetic discrete gauge field in the confining vacua and the supersymmetric index  

E-Print Network (OSTI)

It has recently been argued that the confining vacua of Yang-Mills theory in the far infrared can have topological degrees of freedom given by magnetic $\\mathbb{Z}_q$ gauge field, both in the non-supersymmetric case and in the N=1 supersymmetric case. In this short note we give another piece of evidence by computing and matching the supersymmetric index of the pure super Yang-Mills theory both in the ultraviolet and in the infrared.

Yuji Tachikawa

2014-12-09T23:59:59.000Z

Note: This page contains sample records for the topic "magnetic confinement fusion" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


201

Magnetic Bion Condensation: A New Mechanism ofConfinement and Mass Gap in Four Dimensions  

SciTech Connect

In recent work, we derived the long distance confining dynamics of certain QCD-like gauge theories formulated on small S{sup 1} x R{sup 3} based on symmetries, an index theorem and abelian duality. Here, we give the microscopic derivation. The solution reveals a new mechanism of confinement in QCD(adj) in the regime where we have control over both perturbative and nonperturbative aspects. In particular, consider SU(2) QCD(adj) theory with 1 {le} n{sub f} {le} 4 Majorana fermions, a theory which undergoes gauge symmetry breaking at small S{sup 1}. If the magnetic charge of the BPS monopole is normalized to unity, we show that confinement occurs due to condensation of objects with magnetic charge 2, not 1. Due to index theorems, we know that such an object cannot be a two identical monopole configuration. Its net topological charge must vanish, and hence it must be topologically indistinguishable from the perturbative vacuum. We construct such objects, the magnetically charged, topologically null molecules of a BPS monopole and {bar K}{bar K} antimonopole, which we refer as magnetic bions. An immediate puzzle with this proposal is the apparent Coulomb repulsion between BPS-{bar K}{bar K} pair. An attraction which overcomes the Coulomb repulsion between the two is induced by 2n{sub f} -fermion exchange. Bion condensation is also the mechanism of confinement in N = 1 SYM on the same four-manifold. The SU(N) generalization hints a possible hidden integrability behind nonsupersymmetric QCD of affine Toda type, and allows us to analytically compute the string tensions and thicknesses. We currently do not know the extension to R{sup 4}.

Unsal, Mithat; /SLAC /Stanford U., Phys. Dept.

2007-09-25T23:59:59.000Z

202

Inertial confinement fusion quarterly report, October--December 1992. Volume 3, No. 1  

SciTech Connect

This report contains papers on the following topics: The Beamlet Front End: Prototype of a new pulse generation system;imaging biological objects with x-ray lasers; coherent XUV generation via high-order harmonic generation in rare gases; theory of high-order harmonic generation; two-dimensional computer simulations of ultra- intense, short-pulse laser-plasma interactions; neutron detectors for measuring the fusion burn history of ICF targets; the recirculator; and lasnex evolves to exploit computer industry advances.

Dixit, S.N. [ed.

1992-12-31T23:59:59.000Z

203

Observation of strong electromagnetic fields around laser-entrance holes of ignition-scale hohlraums in inertial-confinement fusion experiments at the National Ignition Facility  

Science Journals Connector (OSTI)

Energy spectra and spectrally resolved one-dimensional fluence images of self-emitted charged-fusion products (14.7MeV D3He protons) are routinely measured from indirectly driven inertial-confinement fusion (ICF) experiments utilizing ignition-scaled hohlraums at the National Ignition Facility (NIF). A striking and consistent feature of these images is that the fluence of protons leaving the ICF target in the direction of the hohlraum's laser entrance holes (LEHs) is very nonuniform spatially, in contrast to the very uniform fluence of protons leaving through the hohlraum equator. In addition, the measured nonuniformities are unpredictable, and vary greatly from shot to shot. These observations were made separately at the times of shock flash and of compression burn, indicating that the asymmetry persists even at ~0.52.5ns after the laser has turned off. These phenomena have also been observed in experiments on the OMEGA laser facility with energy-scaled hohlraums, suggesting that the underlying physics is similar. Comprehensive data sets provide compelling evidence that the nonuniformities result from proton deflections due to strong spontaneous electromagnetic fields around the hohlraum LEHs. Although it has not yet been possible to uniquely determine whether the fields are magnetic (B) or electric (E), preliminary analysis indicates that the strength is ~1MG if B fields or ~109Vcm?1 if E fields. These measurements provide important physics insight into the ongoing ignition experiments at the NIF. Understanding the generation, evolution, interaction and dissipation of the self-generated fields may help to answer many physics questions, such as why the electron temperatures measured in the LEH region are anomalously large, and may help to validate hydrodynamic models of plasma dynamics prior to plasma stagnation in the center of the hohlraum.

C K Li; A B Zylstra; J A Frenje; F H Sguin; N Sinenian; R D Petrasso; P A Amendt; R Bionta; S Friedrich; G W Collins; E Dewald; T Dppner; S H Glenzer; D G Hicks; O L Landen; J D Kilkenny; A J Mackinnon; N Meezan; J Ralph; J R Rygg; J Kline; G Kyrala

2013-01-01T23:59:59.000Z

204

THE INFLUENCES OF MAGNETIC SHEAR ON THE IMPROVEMENT OF THE QUALITY OF CONFINEMENT IN THE PLASMA OF TOKAMAK  

E-Print Network (OSTI)

OF TOKAMAK M. El Mouden1 , D. Saifaoui1 , A. Dezairi2 , H. Imzi1 ; 1 Laboratory of Theoretical Physics of reversed shear on the improvement of the confinement's quality in the plasma of tokamak and especially, is evaluated. Key Words: Plasma confinement, Tokamak, Anomalous transport, Magnetic shear, Transport barrier

Paris-Sud XI, Université de

205

Controlled Fusion and Reactors of the Tokamak Type  

Science Journals Connector (OSTI)

Research on fusion reactor problems has increased dramatically as the plasma physics of magnetic confinement continues to make substantial progress. As part of this research several studies (16) have been comple...

Robert W. Conn

1977-01-01T23:59:59.000Z

206

Quantum confinement induced magnetism in LaNiO3-LaMnO3 superlattices  

SciTech Connect

The emergence of magnetic reconstructions at the interfaces of oxide heterostructures are often explained via subtle modifications in the electronic densities, exchange couplings, or strain. Here, an additional possible route for induced magnetism is studied in the context of the (LaNiO3)n/(LaMnO3)n superlattices using a hybrid tightbinding model. In the LaNiO3 region, the induced magnetizations decouple from the intensity of charge leakage from Mn to Ni, but originate from the spin-filtered quantum confinement present in these nanostructures. In general, the induced magnetization is the largest for the (111)-stacking and the weakest for the (001)-stacking superlattices; results compatible with the exchange bias effects reported byGibert et al. [Nat.Mater. 11, 195 (2012)].

Dong, Shuai [ORNL; Dagotto, Elbio R [ORNL

2013-01-01T23:59:59.000Z

207

Method of controlling fusion reaction rates  

DOE Patents (OSTI)

A method of controlling the reaction rates of the fuel atoms in a fusion reactor comprises the step of polarizing the nuclei of the fuel atoms in a particular direction relative to the plasma confining magnetic field. Fusion reaction rates can be increased or decreased, and the direction of emission of the reaction products can be controlled, depending on the choice of polarization direction.

Kulsrud, Russell M. (Princeton, NJ); Furth, Harold P. (Princeton, NJ); Valeo, Ernest J. (Princeton Junction, NJ); Goldhaber, Maurice (Bayport, NY)

1988-01-01T23:59:59.000Z

208

Diagnosing inertial confinement fusion implosions at OMEGA and the NIF Using novel neutron spectrometry  

E-Print Network (OSTI)

A novel neutron spectrometer, called the Magnetic Recoil Spectrometer (MRS), was designed, built, and implemented on the OMEGA laser facility and the National Ignition Facility (NIF) to measure the neutron spectra from ...

Casey, Daniel Thomas

2012-01-01T23:59:59.000Z

209

White Paper on Magnetic Fusion Energy Priorities by Paul M. Bellan, Professor of Applied Physics, Caltech  

E-Print Network (OSTI)

White Paper on Magnetic Fusion Energy Priorities by Paul M. Bellan, Professor of Applied Physics, Caltech It is important to make ITER work (surpass fusion breakeven) and it is equally important for ITER there will be problems with plasmawall interactions or materials. There are many possible types of problems or there may

210

A Snowflake-Shaped Magnetic Field Holds Promise for Taming Harsh Fusion  

NLE Websites -- All DOE Office Websites (Extended Search)

A Snowflake-Shaped Magnetic Field Holds Promise for Taming Harsh Fusion A Snowflake-Shaped Magnetic Field Holds Promise for Taming Harsh Fusion Plasmas Recent experiments have confirmed the great potential of a novel plasma-material interface concept. By U.S Department of Energy Office of Science October 31, 2012 Tweet Widget Facebook Like Google Plus One National Spherical Torus Experiment (Photo by Elle Starkman, Office of Communications, PPPL) National Spherical Torus Experiment The Science Heat escaping from the core of a twelve-million degree nuclear fusion plasma device was successfully contained by a snowflake-shaped magnetic field to mitigate its impact on device walls. The Impact One of the grand challenges of the magnetic fusion research is to "tame the plasma-material interface"-to develop an interface between the hot

211

Mechanical Strength, Swelling and Weight Loss of Inorganic Fusion Magnet Insulation Systems Following Reactor Irradiation  

Science Journals Connector (OSTI)

Superconducting fusion magnets require a high electrical and mechanical ... were irradiated at ambient temperature in the TRIGA reactor (Vienna, Austria) up to neutron fluences...21, 1022 and 5x1022 m?2...(E>0.1 ...

K. Humer; P. Rosenkranz; H. W. Weber

2000-01-01T23:59:59.000Z

212

A 1.54 K detachable cold?sample transfer system: Application to inertially confined fusion with spin?polarized hydrogen fuels  

Science Journals Connector (OSTI)

A compact cold?transfer apparatus for engaging and retrieving samples at liquid?helium temperatures (1.54 K) maintaining the samples at such temperatures for periods of hours and subsequently inserting them in diverse apparatuses followed by disengagement is described. The properties of several thermal radiation?insulating shrouds necessary for very low sample temperatures are presented. The immediate intended application is transportable target shells containing highly spin?polarized deuterons in solid HD or D2 for inertially confined fusion experiments. The system is also valuable for unpolarized high?density fusion fuels as well as for other applications which are discussed.

N. Alexander; J. Barden; Q. Fan; A. Honig

1991-01-01T23:59:59.000Z

213

Use of Organometallic Polymers for Pre-Heat Shields for Targets in Inertial-Confinement Nuclear Fusion  

Science Journals Connector (OSTI)

Nuclear fusion, the energy process operating in the sun ... radioactive wastes associated with nuclear fission. Harnessing nuclear fusion, however, has proven to be a...

John E. Sheats; Fred Hessel; Louis Tsarouhas

1985-01-01T23:59:59.000Z

214

Computational study of laser imprint mitigation in foam-buffered inertial confinement fusion targets  

SciTech Connect

Recent experiments have shown that low density foam layers can significantly mitigate the perturbing effects of beam nonuniformities affecting the acceleration of thin shells. This problem is studied parametrically with two-dimensional LASNEX [G. B. Zimmerman and W. L. Kruer, Comments Plasma Phys. Controlled Fusion {bold 2}, 51 (1975)]. Foam-buffered targets are employed, consisting typically of 250 {Angstrom} of gold, and 50 {mu}m of 50mg/cm{sup 3} C{sub 10}H{sub 8}O{sub 4} foam attached to a 10 {mu}m foil. In simulation these were characteristically exposed to 1.2 ns, flat-topped green light pulses at 1.4{times}10{sup 14}W/cm{sup 2} intensity, bearing 30 {mu}m lateral perturbations of up to 60{percent} variation in intensity. Without the buffer layers the foils were severely disrupted by 1 ns. With buffering only minimal distortion was manifest at 3 ns. The smoothing is shown to derive principally from the high thermal conductivity of the heated foam. The simulation results imply that (1) the foam thickness should exceed the disturbance wavelength; (2) intensities exceeding 5{times}10{sup 13}W/cm{sup 2} are needed for assured stability beyond 2 ns; (3) longer foams at lower densities are needed for effective mitigation with shorter wavelength light; (4) the gold layer hastens conversion of the structured foam to a uniform plasma. {copyright} {ital 1998 American Institute of Physics.}

Mason, R.J.; Kopp, R.A.; Vu, H.X.; Wilson, D.C.; Goldman, S.R.; Watt, R.G. [Los Alamos National Laboratory, Los Alamos, New Mexico 87545 (United States)] [Los Alamos National Laboratory, Los Alamos, New Mexico 87545 (United States); Dunne, M. [Atomic Weapons Establishment, Aldermaston, Reading, RG7 4PR (United Kingdom)] [Atomic Weapons Establishment, Aldermaston, Reading, RG7 4PR (United Kingdom); Willi, O. [The Blackett Laboratory, Imperial College of Science and Technology, London SW72BZ (United Kingdom)] [The Blackett Laboratory, Imperial College of Science and Technology, London SW72BZ (United Kingdom)

1998-01-01T23:59:59.000Z

215

The LLNL (Lawrence Livermore National Laboratory) ICF (Inertial Confinement Fusion) Program: Progress toward ignition in the Laboratory  

SciTech Connect

The Inertial Confinement Fusion (ICF) Program at the Lawrence Livermore National Laboratory (LLNL) has made substantial progress in target physics, target diagnostics, and laser science and technology. In each area, progress required the development of experimental techniques and computational modeling. The objectives of the target physics experiments in the Nova laser facility are to address and understand critical physics issues that determine the conditions required to achieve ignition and gain in an ICF capsule. The LLNL experimental program primarily addresses indirect-drive implosions, in which the capsule is driven by x rays produced by the interaction of the laser light with a high-Z plasma. Experiments address both the physics of generating the radiation environment in a laser-driven hohlraum and the physics associated with imploding ICF capsules to ignition and high-gain conditions in the absence of alpha deposition. Recent experiments and modeling have established much of the physics necessary to validate the basic concept of ignition and ICF target gain in the laboratory. The rapid progress made in the past several years, and in particular, recent results showing higher radiation drive temperatures and implosion velocities than previously obtained and assumed for high-gain target designs, has led LLNL to propose an upgrade of the Nova laser to 1.5 to 2 MJ (at 0.35 {mu}m) to demonstrate ignition and energy gains of 10 to 20 -- the Nova Upgrade.

Storm, E.; Batha, S.H.; Bernat, T.P.; Bibeau, C.; Cable, M.D.; Caird, J.A.; Campbell, E.M.; Campbell, J.H.; Coleman, L.W.; Cook, R.C.; Correll, D.L.; Darrow, C.B.; Davis, J.I.; Drake, R.P.; Ehrlich, R.B.; Ellis, R.J.; Glendinning, S.G.; Haan, S.W.; Haendler, B.L.; Hatcher, C.W.; Hatchett, S.P.; Hermes, G.L.; Hunt, J.P.; Kania, D.R.; Kauffman, R.L.; Kilkenny, J.D.; Kornblum, H.N.; Kruer, W.L.; Kyrazis, D.T.; Lane, S.M.; Laumann

1990-10-02T23:59:59.000Z

216

HEAVY ION INERTIAL FUSION  

E-Print Network (OSTI)

in the Tokamak Fusion Test Reactor which will be completedDrivers and Reactors for Inertial Confinement Fusion, K.A.

Keefe, D.

2008-01-01T23:59:59.000Z

217

Magnetic Fusion Energy Research: A Summary of Accomplishments  

DOE R&D Accomplishments (OSTI)

Some of the more important contributions of the research program needed to establish the scientific and technical base for fusion power production are discussed. (MOW)

1986-12-00T23:59:59.000Z

218

Magnetic monopole loops supported by a meron pair as the quark confiner  

E-Print Network (OSTI)

We give a definition of gauge-invariant magnetic monopoles in Yang-Mills theory without using the Abelian projection due to 't Hooft. They automatically appear from the Wilson loop operator. This is shown by rewriting the Wilson loop operator using a non-Abelian Stokes theorem. The magnetic monopole defined in this way is a topological object of co-dimension 3, i.e., a loop in four-dimensions. We show that such magnetic loops indeed exist in four-dimensional Yang-Mills theory. In fact, we give an analytical solution representing circular magnetic monopole loops joining a pair of merons in the four-dimensional Euclidean SU(2) Yang-Mills theory. This is achieved by solving the differential equation for the adjoint color (magnetic monopole) field in the two--meron background field within the recently developed reformulation of the Yang-Mills theory. Our analytical solution corresponds to the numerical solution found by Montero and Negele on a lattice. This result strongly suggests that a meron pair is the most relevant quark confiner in the original Yang-Mills theory, as Callan, Dashen and Gross suggested long ago.

Kei-Ichi Kondo

2008-12-21T23:59:59.000Z

219

An experimental and theoretical investigation of a magnetically confined dc plasma discharge  

SciTech Connect

A magnetically confined dc plasma discharge sustained by a thermionic source was investigated using a combined experimental and theoretical approach. The discharge originates in an arc plasma source and is expanded in a cylindrical chamber, where it is stabilized by an annular anode. The plasma expansion is contained by an axial magnetic field generated by coils positioned at the top and the bottom of the reactor. The plasma reactor design allows control of the energy of ions impinging on the substrate and thus a high electron density of about 10{sup 17} m{sup -3} at 1 Pa can be reached. The plasma is studied using a model composed of the Poisson and of the charged species continuity equations, solved in the flow and temperature fields determined by solving the Navier-Stokes and Fourier equations. The model equations are integrated using the finite element method in a two-dimensional axial symmetric domain. Ionization rates are either assumed constant or determined by solving the Boltzmann transport equation in the local electric field with the Monte Carlo (MC) method. Electron and ion transport parameters are determined by accounting for magnetic confinement through a simplified solution of the ion and electron momentum conservation equations, which yielded parameters in good agreement with those determined with the MC simulations. Calculated electron densities and plasma potentials were satisfactorily compared to those measured using a Langmuir probe. The model demonstrates that the intensity of the magnetic field greatly influences the electron density, so that a decrease by a factor of 2 in its intensity corresponds to a decrease by almost an order of magnitude of the electron and ion concentrations.

Rondanini, Maurizio; Cavallotti, Carlo [Dipartimento. di Chimica, Materiali e Ingegneria Chimica, 'G. Natta' Politecnico di Milano, Via Mancinelli 7, 20131 Milano (Italy); Ricci, Daria [Dipartimento di Fisica, 'G. Occhialini' Universita degli Studi di Milano, Bicocca Piazza della Scienza 3, 20126 Milano (Italy); Chrastina, Daniel; Isella, Giovanni; Moiseev, Tamara; Kaenel, Hans von [L-NESS Laboratory, Dipartimento di Fisica, Politecnico di Milano, Via Anzani 42, 22100 Como (Italy)

2008-07-01T23:59:59.000Z

220

IEEE thirteenth symposium on fusion engineering  

SciTech Connect

This report contains papers of the following topics on fusion engineering: magnet engineering; blanket engineering; electric power control; plasma engineering; vacuum systems and vessels; diagnostic systems; controls, instrumentation, and data acquisition; heating and current drive; next generation devices; health and safety; magnet materials and insulation; quality assurance and reliability; electrical generators; divertors and plasma-facing components; power systems; tritium; and inertial confinement fusion. These papers have been procedure and cataloged separately. (LSP)

Lubell, M.S.; Nestor, M.B.; Vaughan, S.F. (eds.)

1989-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "magnetic confinement fusion" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


221

IEEE thirteenth symposium on fusion engineering  

SciTech Connect

This report contains papers of the following topics on fusion engineering: magnetic engineering; blanket engineering; plasma engineering; vacuum systems and vessels; controls, instrumentation, and data acquisition; heating and current drive; health and safety; magnet materials and insulation; quality assurance and reliability; electrical generators; divertors and plasma-facing components; power systems; tritium; inertial confinement fusion; plasma fueling; cryogenics; commercial reactors; shielding; and design and performance. (LSP)

Lubell, M.S.; Nestor, M.B.; Vaughan, S.F. (eds.)

1989-01-01T23:59:59.000Z

222

Dependence of Shell Mix on Feedthrough in Direct Drive Inertial Confinement Fusion S. P. Regan, J. A. Delettrez, V. N. Goncharov, F. J. Marshall, J. M. Soures, V. A. Smalyuk, P. B. Radha, B. Yaakobi,  

E-Print Network (OSTI)

Dependence of Shell Mix on Feedthrough in Direct Drive Inertial Confinement Fusion S. P. Regan, J 87545, USA J. A. Frenje, C. K. Li, R. D. Petrasso, and F. H. Se´guin Plasma Science and Fusion Center May 2004) The mixing of cold, high-density shell plasma with the low-density, hot spot plasma

223

A Plan for the Deveiopment of Magnetic Fusion Energy  

E-Print Network (OSTI)

and to enable the US to benefitfromits commercialization. Executive Summary Fusionenergy should be a long, controlof plasma-wall interactions, tritium processing, developmentof low basisforfusion commercialization. 4. Constructa fusion power demonstrationfacility (DEMO)in the US,which would

224

Rotation studies in fusion plasmas via imaging X-ray crystal spectroscopy  

E-Print Network (OSTI)

The increase in plasma performance associated with turbulence suppression via flow shear in magnetically confined fusion plasmas has been well documented. Currently, the standard methods for both generating and measuring ...

Ince-Cushman, Alexander Charles

2008-01-01T23:59:59.000Z

225

Plasma-Sprayed Beryllium on Macro-Roughened Substrates for Fusion Reactor High Heat Flux Applications  

Science Journals Connector (OSTI)

The development of beryllium first wall (FW) plasma facing components for future magnetic confinement fusion experiments, such as the International Thermonuclear Experimental Reactor (ITER), is a topic of great.....

Kendall J. Hollis; Brian D. Bartram; Manfred Roedig

2007-03-01T23:59:59.000Z

226

Photo of the Week: The Mirror Fusion Test Facility | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

The Mirror Fusion Test Facility The Mirror Fusion Test Facility Photo of the Week: The Mirror Fusion Test Facility July 19, 2013 - 4:17pm Addthis This 1981 photo shows the Mirror Fusion Test Facility (MFTF), an experimental magnetic confinement fusion device built using a magnetic mirror at Lawrence Livermore National Laboratory (LLNL). The MFTF functioned as the primary research center for mirror fusion devices. The design consisted of a 64-meter-long vacuum vessel fitted with 26 coil magnets bonding the center of the vessel and two 400-ton yin-yang magnet mirrors at either end. The first magnet produced a magnetic field force equal to the weight of 30 jumbo jets hanging from the magnet coil. | Photo courtesy of Lawrence Livermore National Laboratory. This 1981 photo shows the Mirror Fusion Test Facility (MFTF), an

227

THE ROTATING MAGNETIC FIELD OSCILLATOR SYSTEM FOR CURRENT DRIVE IN THE TRANSLATION, CONFINEMENT AND SUSTAINMENT EXPERIMENT  

SciTech Connect

The experimental setup and test results for the {approximately}125 MW rotating magnetic field current drive system of the Translation, Confinement and Sustainment Experiment at the University of Washington are described. The oscillator system, constructed at Los Alamos National Laboratory, drives two tank circuits (15 kV{sub peak} potential, 8.5 kA{sub peak} maximum circulating current in each tank to date) operated 90{degree} out of phase to produce a 54 G rotating magnetic field with a frequency of 163 kHz ({omega} = 1.02{sup x} 10{sup {minus}6} s{sup {minus}1}). Programmable waveform generators control ''hot deck'' totem pole drivers that are used to control the grid of 12 Machlett 8618 magnetically beamed triode tubes. This setup allows the current to be turned on or off in less than 100 ns ({approximately}6{degree}). Both tank circuits are isolated from the current source by a 1:1 air core, transmission line transformer. Each tank circuit contains two saddle coils (combined inductance of 1.6 {micro}H) and radio frequency capacitors (580 nF). Test results are presented for three conditions: no external load, a resistive external load and a plasma load. A SPICE model of the oscillator system was created. Comparisons between this model and experimental data are given.

S. TOBIN; ET AL

2000-12-01T23:59:59.000Z

228

Laser-based diagnostic for tracing magnetic-field lines in spheromaks and other self-organized magnetically confined plasmas  

Science Journals Connector (OSTI)

We are in the process of testing a technique for measuring the magnetic-field line topology in magnetically confined plasmas. The basic idea is to use a high-powerful short-pulse laser to launch a burst of energetic (?100 keV) electrons from a target passing through the plasma of interest; these electrons then generally follow field lines until they strike a solid surface where a burst of x rays is produced and then detected. The field line connection length can be determined from the time delay between the laser pulse and the burst of x rays. The topology of the field lines can be inferred by measuring the connection length as a function of initial target location inside the plasma. Measuring the spatial distribution of the x-ray production will provide further information on the field topology including the effects of magnetic-field fluctuations and stochasticity. The work will eventually include testing the appropriate x-ray detectors measuring the background x-ray emission in a spheromak plasma measuring the energetic electron production by a short-pulse high-power laser and making preliminary measurements of the edge field line topology in the Sustained Spheromak Physics Experiment using a pulsed electron-beam source as a prototype for a laser-based source. This technique may have broad application to a variety of plasma configurations and provide physics data applicable to a wide range of plasma physics problems.

H. S. McLean; D. N. Hill; D. D. Ryutov; H. Chen

2003-01-01T23:59:59.000Z

229

HEAVY ION INERTIAL FUSION  

E-Print Network (OSTI)

Accelerators as Drivers for Inertially Confined Fusion, W.B.LBL-9332/SLAC-22l (1979) Fusion Driven by Heavy Ion Beams,OF CALIFORNIA f Accelerator & Fusion Research Division

Keefe, D.

2008-01-01T23:59:59.000Z

230

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.)

1983-04-01T23:59:59.000Z

231

Status and Promise CT's and Magnetized Target Fusion  

E-Print Network (OSTI)

. Hill (LLNL) #12;CT's: Spheromaks & Field Reversed Configurations At LLNL, the SSPX experiment is investigating spheromak formation, sustainment, and confinement issues. (Hill, Mclean, Wood, Ryutov). At UC-Davis, formation and acceleration of spheromaks. (Hwang) At the U of Washington, field reversed configuration

232

THE NATIONAL FUSION COLLABORATORY PROJECT: APPLYING GRID TECHNOLOGY FOR MAGNETIC FUSION RESEARCH  

E-Print Network (OSTI)

of advanced software tools that reduce technical barriers to collaboration and sharing on a national scale. Our vision is to make resources -- data, computers along with analysis, simulation and visualization-institutional collaboration on fusion experiments, and improving comparisons between experiments and theory. The project

Thompson, Mary R.

233

Magnetized Target Fusion (MTF) (a.k.a. Magneto-Inertial Fusion)  

E-Print Network (OSTI)

.g., Atlas $50M). The low cost and size of experimental facilities should significantly reduce fusion TEMPERATURE (eV) IONDENSITY(/cm)3 1016 1014 1018 1020 1022 1024 1026 103 104 105 Facility Cost($) = 1 TEMPERATURE (eV) 104 105 Facility Cost($) B=5 MG Operation at an intermediate density leads to reduced

234

Magnetic Probe to Study Plasma Jets for Magneto-Inertial Fusion  

SciTech Connect

A probe has been constructed to measure the magnetic field of a plasma jet generated by a pulsed plasma rail-gun. The probe consists of two sets of three orthogonally-oriented commercial chip inductors to measure the three-dimensional magnetic field vector at two separate positions in order to give information about the magnetic field evolution within the jet. The strength and evolution of the magnetic field is one of many factors important in evaluating the use of supersonic plasma jets for forming imploding spherical plasma liners as a standoff driver for magneto-inertial fusion.

Martens, Daniel [Los Alamos National Laboratory; Hsu, Scott C. [Los Alamos National Laboratory

2012-08-16T23:59:59.000Z

235

Basic hydrodynamics of RichtmyerMeshkov-type growth and oscillations in the inertial confinement fusion-relevant conditions  

Science Journals Connector (OSTI)

...one-dimensional time history of the CH foil acceleration...al. 1999). The price paid for high uniformity...hohlraum is its low energy efficiency: only...ignition, fusion energy gain and, eventually, fusion energy production on NIF in the USA, LMJ in France...

2010-01-01T23:59:59.000Z

236

Proliferation risks of magnetic fusion energy: clandestine production, covert production and breakout  

Science Journals Connector (OSTI)

Nuclear proliferation risks from magnetic fusion energy associated with access to weapon-usable materials can be divided into three main categories: (1) clandestine production of weapon-usable material in an undeclared facility, (2) covert production of such material in a declared facility and (3) use of a declared facility in a breakout scenario, in which a state begins production of fissile material without concealing the effort. In this paper, we address each of these categories of risks from fusion. For each case, we find that the proliferation risk from fusion systems can be much lower than the equivalent risk from fission systems, if the fusion system is designed to accommodate appropriate safeguards.

A. Glaser; R.J. Goldston

2012-01-01T23:59:59.000Z

237

Laser or charged-particle-beam fusion reactor with direct electric generation by magnetic flux compression  

DOE Patents (OSTI)

A high-power-density-laser or charged-particle-beam fusion reactor system maximizes the directed kinetic energy imparted to a large mass of liquid lithium by a centrally located fusion target. A fusion target is embedded in a large mass of lithium, of sufficient radius to act as a tritium breeding blanket, and provided with ports for the access of beam energy to implode the target. The directed kinetic energy is converted directly to electricity with high efficiency by work done against a pulsed magnetic field applied exterior to the lithium. Because the system maximizes the blanket thickness per unit volume of lithium, neutron-induced radioactivities in the reaction chamber wall are several orders of magnitude less than is typical of other fusion reactor systems. 25 figs.

Lasche, G.P.

1987-02-20T23:59:59.000Z

238

Ultrasound and nuclear magnetism in bulk and confined liquid sup 3 He  

SciTech Connect

Two different experiments on liquid {sup 3}He in open and confined geometries were performed. In the first, the attenuation and velocity of 5 MHz ultra-sound were measured in both the bulk normal and superfluid phases as a function of temperature (0.3 to 30 mK) and pressure (0.3 to 34 bars). The zero temperature limiting behavior was observed in the B-phase superfluid at temperatures below T/{Tc} = 0.4. The velocity was found to return to its ordinary first-sound value as was theoretically expected. Using precise measurements of the difference between the zero-and first-sound velocities, the second symmetric Landau parameter, F{sub 2}{sup s}, was deduced as a function of pressure. In the other experiment, nuclear magnetic resonance (NMR) was used to probe the magnetic susceptibility, {chi}, transverse spin dephasing time, {tau}{sub 2}, and spin-lattice relaxation time, {tau}{sub 1}. Measurements were performed as a function of temperature (0.3 mK to 2K), pressure (0 to 9 bars), and frequency (231,345,462,692, and 924 kHz). The magnetic susceptibility was found to obey a Curie-Weiss law with a pressure-dependent ferromagnetic Weiss temperature. The spin dephasing time was found to be a strong function of temperature at low temperature, with its slope determined by the resonance frequency. This frequency dependence of {tau}{sub 2} was exploited, using a simple model, to obtain the true spin-spin relaxation time, {tau}{sub 2}, as a function of temperature. This was found to obey the same inverse temperature dependence as the susceptibility, diverging at the extrapolated ferromagnetic transition.

Engel, B.N.

1988-01-01T23:59:59.000Z

239

Spherical torus fusion reactor  

DOE Patents (OSTI)

A fusion reactor is provided having a near spherical-shaped plasma with a modest central opening through which straight segments of toroidal field coils extend that carry electrical current for generating a toroidal magnet plasma confinement fields. By retaining only the indispensable components inboard of the plasma torus, principally the cooled toroidal field conductors and in some cases a vacuum containment vessel wall, the fusion reactor features an exceptionally small aspect ratio (typically about 1.5), a naturally elongated plasma cross section without extensive field shaping, requires low strength magnetic containment fields, small size and high beta. These features combine to produce a spherical torus plasma in a unique physics regime which permits compact fusion at low field and modest cost.

Peng, Yueng-Kay M. (Oak Ridge, TN)

1989-01-01T23:59:59.000Z

240

Prospects of High Temperature Superconductors for fusion magnets and power applications  

Science Journals Connector (OSTI)

Abstract During the last few years, progress in the field of second-generation High Temperature Superconductors (HTS) was breathtaking. Industry has taken up production of long length coated REBCO conductors with reduced angular dependency on external magnetic field and excellent critical current density jc. Consequently these REBCO tapes are used more and more in power application. For fusion magnets, high current conductors in the kA range are needed to limit the voltage during fast discharge. Several designs for high current cables using High Temperature Superconductors have been proposed. With the REBCO tape performance at hand, the prospects of fusion magnets based on such high current cables are promising. An operation at 4.5K offers a comfortable temperature margin, more mechanical stability and the possibility to reach even higher fields compared to existing solutions with Nb3Sn which could be interesting with respect to DEMO. After a brief overview of HTS use in power application the paper will give an overview of possible use of HTS material for fusion application. Present high current HTS cable designs are reviewed and the potential using such concepts for future fusion magnets is discussed.

Walter H. Fietz; Christian Barth; Sandra Drotziger; Wilfried Goldacker; Reinhard Heller; Sonja I. Schlachter; Klaus-Peter Weiss

2013-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "magnetic confinement fusion" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


241

Alternative conceptual design of a magnet support structure for plasma fusion devices of stellarator type  

Science Journals Connector (OSTI)

Engineering design of magnet coil support structures for plasma fusion devices of the stellarator type are at present an important task in stellarator hardware R&D activities. In particular this is one of the basic core components in developing the stellarator's line in view of a robust and reliable fusion reactor. Based on long time experience in design and structural analyses of stellarator magnet systems and their support structure, the authors are proposing in this paper an alternative conceptual design for the magnet support structure. This paper describes the basic assumptions that a conceptual design of a magnet support structure has to fulfil. In this context, essential experiences gathered during manufacturing and assembly of the magnet support structure for a current stellarator fusion device engineered at Max Planck Institute for Plasma Physics are taken into account. The concept provides flexibility in matters of readjustment and positional optimization of the magnet coils during the assembly phase and potentially during the operation. The flexibility during the assembly phase allows a simplification of technical requirements and performance criteria which may result in a reduction of costs and improved reliability of a stellarator based power device.

Nikola Jaksic; Boris Mendelevitch; Jrg Tretter

2011-01-01T23:59:59.000Z

242

Radial Fokker-Planck model for plasmas confined by magnetic mirror fields  

SciTech Connect

A time-dependent computer model has been developed for the spatially dependent distribution function f(r,v,t). An orbit averaged Fokker-Planck equation treats Coulomb collisions and various atomic physics processes. The motivation for the present code is to provide an accurate treatment of gyro-radius effects and realistic beam geometries which have been neglected in previous Fokker-Planck codes. Finite width beams may be offset from the plasma center to determine beam injection for build-up studies. The inclusion of a finite gyro-radius is essential for studying radial transport due to both quasilinear fluctuations and charge exchange collisions. Charge exchange with energetic beam atoms and plasma erosion due to charge-exchange collisions with thermal gas are both included. Quasilinear diffusion terms include the effects of turbulent diffusion in the model. The model has been used to study particle and energy confinement times in the 2XIIB experiment and in the mirror plug of the TMX experiment. Calculated values of T/sub e/ decrease from classical Fokker-Planck values (1000 eV for 2XIIB) to the 50 eV to 200 eV range observed in 2XIIB and TMX experiments. Radial density profiles and n tau scaling with plasma radius and magnetic field agree with experimental data.

Futch, A.H.

1986-05-01T23:59:59.000Z

243

The Nuclear Fusion Award  

Science Journals Connector (OSTI)

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 63544 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 45161 Honrubia J.J. et al 2006 Three-dimensional fast electron transport for ignition-scale inertial fusion capsules Nucl. Fusion 46 L258 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 51220 Plyusnin V.V. et al 2006 Study of runaway electron generation during major disruptions in JET Nucl. Fusion 46 27784 Pitts R.A. et al 2006 Far SOL ELM ion energies in JET Nucl. Fusion 46 8298 Berk H.L. et al 2006 Explanation of the JET n = 0 chirping mode Nucl. Fusion 46 S88897 Urano H. et al 2006 Confinement degradation with beta for ELMy HH-mode plasmas in JT-60U tokamak Nucl. Fusion 46 7817 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 5417 Inagaki S. et al 2006 Comparison of transient electron heat transport in LHD helical and JT-60U tokamak plasmas Nucl. Fusion 46 13341 Watanabe T.-H. et al 2006 Velocityspace structures of distribution function in toroidal ion temperature gradient turbulence Nucl. Fusion 46 2432 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 161824 Lipschultz B. et al 2007 Plasmasurface interaction, scrape-off layer and divertor physics: implications for ITER Nucl. Fusion 47 1189205 Loarer T. et al 2007 Gas balance and fuel retention in fusion devices Nucl. Fusion 47 111220 Garcia O.E et al 2007 Fluctuations and transport in the TCV scrape-off layer Nucl. Fusion 47 66776 Zonca F. et al 2007 Electron fishbones: theory and experimental evidence Nucl. Fusion 47 158897 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 53551 Yoshida M. et al 2007 Momentum transport and plasma rotation profile in toroidal direction in JT-60U L-mode plasmas Nucl. Fusion 47 85663 Zohm H. et al 2007 Control of MHD instabilities by ECCD: ASDEX Upgrade results and implications for ITER Nucl. Fusion 47 22832 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 9618 Urano H. et al 2007 H-mode pedestal structure in the v

M. Kikuchi

2011-01-01T23:59:59.000Z

244

Impact of pulsed irradiation upon neutron activation calculations for inertial and magnetic fusion energy power plants  

SciTech Connect

Sisolak et al. defined two methods for the approximation of pulsed irradiation: the steady-state (SS) and the equivalent steady-state (ESS) methods. Both methods have been shown to greatly simplify the process of calculating radionuclide inventories. However, they are not accurate when applied to magnetic fusion energy (MFF) and inertial fusion energy (IFE) experimental facilities. In the work reported here, an attempt has been made to evaluate the accuracy of the SS and ESS methods as they might be applied to typical MFE and IFE power plants. 18 refs., 6 figs.

Latkowski, J.F. [Lawrence Livermore National Lab., CA (United States); Sanz, J. [Universidad Politecnica de Madrid (Spain); Vujic, J.L. [Univ. of California, Berkeley, CA (United States)

1996-12-31T23:59:59.000Z

245

External proton beam analysis of plasma facing materials for magnetic confinement fusion applications  

E-Print Network (OSTI)

A 1.7MV tandem accelerator was reconstructed and refurbished for this thesis and for surface science applications at the Cambridge laboratory for accelerator study of surfaces (CLASS). At CLASS, an external proton beam ...

Barnard, Harold Salvadore

2009-01-01T23:59:59.000Z

246

Nuclear processes in magnetic fusion reactors with polarized fuel  

E-Print Network (OSTI)

We consider the processes $d +d \\to n +{^3He}$, $d +{^3He} \\to p +{^4He}$, $d +{^3H} \\to n +{^4He}$, ${^3He} +{^3He}\\to p+p +{^4He}$, ${^3H} +{^3He}\\to d +{^4He}$, with particular attention for applications in fusion reactors. After a model independent parametrization of the spin structure of the matrix elements for these processes at thermal colliding energies, in terms of partial amplitudes, we study polarization phenomena in the framework of a formalism of helicity amplitudes. The strong angular dependence of the final nuclei and of the polarization observables on the polarizations of the fuel components can be helpful in the design of the reactor shielding, blanket arrangement etc..We analyze also the angular dependence of the neutron polarization for the processes $\\vec d +\\vec d \\to n +{^3He}$ and $\\vec d +\\vec {^3H} \\to n +{^4He}$.

Michail P. Rekalo; Egle Tomasi-Gustafsson

2000-10-16T23:59:59.000Z

247

Hydrogen Hydrogen FusionFusionFusionFusionFusionFusion  

E-Print Network (OSTI)

100.000 years LNGS Laboratori Nazionali del Gran Sasso Borexino THE THERMONUCLEAR FUSION REACTIONHydrogen Hydrogen Fusion Deuterium FusionFusionFusionFusionFusionFusion THE SUN AS BOREXINO SEES

Heiz, Ulrich

248

Dynamics of chaotic magnetic lines and noble ITB's in the Tokamap J. H. Misguich and Fusion BFR Working Group (*)  

E-Print Network (OSTI)

Dynamics of chaotic magnetic lines and noble ITB's in the Tokamap J. H. Misguich and Fusion BFR and study the dynamics of magnetic lines in a situation of " incomplete chaos". Several previous studies have used Hamiltonian mapping to represent magnetic lines. Here we use the Hamiltonian twist map

249

Core transport studies in fusion devices  

E-Print Network (OSTI)

The turbulence in magnetically confined fusion plasmas has important and non-trivial effects on the quality of the energy confinement. These effects are hard to make a quantitative assessment of analytically. The problem investigated in this article is the transport of energy and particles, in particular impurities, in a Tokamak plasma. Impurities from the walls of the plasma vessel cause energy losses if they reach the plasma core. It is therefore important to understand the transport mechanisms to prevent impurity accumulation and minimize losses. This is an area of research where turbulence plays a major role and is intimately associated with the performance of future fusion reactors, such as ITER.

Strand, Pr; Nordman, Hans

2010-01-01T23:59:59.000Z

250

A NATIONAL COLLABORATORY TO ADVANCE THE SCIENCE OF HIGH TEMPERATURE PLASMA PHYSICS FOR MAGNETIC FUSION  

SciTech Connect

This report summarizes the work of the University of Utah, which was a member of the National Fusion Collaboratory (NFC) Project funded by the United States Department of Energy (DOE) under the Scientific Discovery through Advanced Computing Program (SciDAC) to develop a persistent infrastructure to enable scientific collaboration for magnetic fusion research. A five year project that was initiated in 2001, it the NFC built on the past collaborative work performed within the U.S. fusion community and added the component of computer science research done with the USDOE Office of Science, Office of Advanced Scientific Computer Research. The project was itself a collaboration, itself uniting fusion scientists from General Atomics, MIT, and PPPL and computer scientists from ANL, LBNL, and Princeton University, and the University of Utah to form a coordinated team. The group leveraged existing computer science technology where possible and extended or created new capabilities where required. The complete finial report is attached as an addendum. The In the collaboration, the primary technical responsibility of the University of Utah in the collaboration was to develop and deploy an advanced scientific visualization service. To achieve this goal, the SCIRun Problem Solving Environment (PSE) is used on FusionGrid for an advanced scientific visualization service. SCIRun is open source software that gives the user the ability to create complex 3D visualizations and 2D graphics. This capability allows for the exploration of complex simulation results and the comparison of simulation and experimental data. SCIRun on FusionGrid gives the scientist a no-license-cost visualization capability that rivals present day commercial visualization packages. To accelerate the usage of SCIRun within the fusion community, a stand-alone application built on top of SCIRun was developed and deployed. This application, FusionViewer, allows users who are unfamiliar with SCIRun to quickly create visualizations and perform analysis of their simulation data from either the MDSplus data storage environment or from locally stored HDF5 files. More advanced tools for visualization and analysis also were created in collaboration with the SciDAC Center for Extended MHD Modeling. Versions of SCIRun with the FusionViewer have been made available to fusion scientists on the Mac OS X, Linux, and other Unix based platforms and have been downloaded 1163 times. SCIRun has been used with NIMROD, M3D, BOUT fusion simulation data as well as simulation data from other SciDAC application areas (e.g., Astrophysics). The subsequent visualization results - including animations - have been incorporated into invited talks at multiple APS/DPP meetings as well as peer reviewed journal articles. As an example, SCIRun was used for the visualization and analysis of a NIMROD simulation of a disruption that occurred in a DIII-D experiment. The resulting animations and stills were presented as part of invited talks at APS/DPP meetings and the SC04 conference in addition to being highlighted in the NIH/NSF Visualization Research Challenges Report. By achieving its technical goals, the University of Utah played a key role in the successful development of a persistent infrastructure to enable scientific collaboration for magnetic fusion research. Many of the visualization tools developed as part of the NFC continue to be used by Fusion and other SciDAC application scientists and are currently being supported and expanded through follow-on up on SciDAC projects (Visualization and Analytics Center for Enabling Technology, and the Visualization and Analysis in Support of Fusion SAP).

Allen R. Sanderson; Christopher R. Johnson

2006-08-01T23:59:59.000Z

251

Modifying locally the safety profile to improve the confinement of magnetic field lines in tokamak  

E-Print Network (OSTI)

Published in Nuclear Fusion 52 (2012) 054006. hal-00698991,version1-18May2012 Author manuscript, published in "Nuclear Fusion 52, 5 (2012) 054006" DOI : 10.1088/0029-5515/52/5/054006 #12;Modifying locally the safety center, with negligible input power. In this way, they were able to demonstrate that the electron

Paris-Sud XI, Université de

252

Plasma generation and confinement in a toroidal magnetic cusp J. Egedal, A. Fasoli,a)  

E-Print Network (OSTI)

, and D. Tarkowski Massachusetts Institute of Technology, Plasma Science and Fusion Center, Cambridge, Massachusetts 02139 Received 29 December 1999; accepted for publication 31 May 2000 The first measurements. Reconnection is believed to be the key process in the sun corona heating via solar flares,2 and in fusion

Egedal, Jan

253

Negative specific heat of a magnetically self-confined plasma torus  

Science Journals Connector (OSTI)

...fusion plasma are considered. The goal of the controlled thermonuclear fusion program is to make the energy source that powers our...case the negative specific heat may aid the ignition of thermonuclear burning. The if part is good news; the bad news...

Michael K.-H. Kiessling; Thomas Neukirch

2003-01-01T23:59:59.000Z

254

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

E-Print Network (OSTI)

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

2014-01-01T23:59:59.000Z

255

Plasma Barodiffusion in Inertial-Confinement-Fusion Implosions: Application to Observed Yield Anomalies in Thermonuclear Fuel Mixtures  

E-Print Network (OSTI)

Anomalies in Thermonuclear Fuel Mixtures Peter Amendt, O. L. Landen, and H. F. Robey Lawrence Livermore National Laboratory, Livermore, California 94551, USA C. K. Li and R. D. Petrasso Plasma Science and Fusion performance in general, and upcoming igni- tion tuning campaigns on the National Ignition Facility (NIF) [4

256

A novel method for modeling the neutron time of flight detector response in current mode to inertial confinement fusion experiments (invited)  

SciTech Connect

A novel method for modeling the neutron time of flight (nTOF) detector response in current mode for inertial confinement fusion experiments has been applied to the on-axis nTOF detectors located in the basement of the Z-Facility. It will be shown that this method can identify sources of neutron scattering, and is useful for predicting detector responses in future experimental configurations, and for identifying potential sources of neutron scattering when experimental set-ups change. This method can also provide insight on how much broadening neutron scattering contributes to the primary signals, which is then subtracted from them. Detector time responses are deconvolved from the signals, allowing a transformation from dN/dt to dN/dE, extracting neutron spectra at each detector location; these spectra are proportional to the absolute yield.

Nelson, A. J.; Cooper, G. W. [Department of Chemical and Nuclear Engineering, University of New Mexico, Albuquerque, New Mexico 87131 (United States); Ruiz, C. L.; Chandler, G. A.; Fehl, D. L.; Hahn, K. D.; Leeper, R. J.; Smelser, R.; Torres, J. A. [Sandia National Laboratories, Albuquerque, New Mexico 87185-1196 (United States)

2012-10-15T23:59:59.000Z

257

Fusion Energy Division annual progress report period ending December 31, 1986  

SciTech Connect

This annual report on fusion energy discusses the progress on work in the following main topics: toroidal confinement experiments; atomic physics and plasma diagnostics development; plasma theory and computing; plasma-materials interactions; plasma technology; superconducting magnet development; fusion engineering design center; materials research and development; and neutron transport. (LSP)

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

1987-10-01T23:59:59.000Z

258

Simulation of Fusion Plasmas  

ScienceCinema (OSTI)

The upcoming ITER experiment (www.iter.org) represents the next major milestone in realizing the promise of using nuclear fusion as a commercial energy source, by moving into the ?burning plasma? regime where the dominant heat source is the internal fusion reactions. As part of its support for the ITER mission, the US fusion community is actively developing validated predictive models of the behavior of magnetically confined plasmas. In this talk, I will describe how the plasma community is using the latest high performance computing facilities to develop and refine our models of the nonlinear, multiscale plasma dynamics, and how recent advances in experimental diagnostics are allowing us to directly test and validate these models at an unprecedented level.

Chris Holland

2010-01-08T23:59:59.000Z

259

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

E-Print Network (OSTI)

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

2014-01-01T23:59:59.000Z

260

Fusion utility in the Knudsen layer  

SciTech Connect

In inertial confinement fusion, the loss of fast ions from the edge of the fusing hot-spot region reduces the reactivity below its Maxwellian value. The loss of fast ions may be pronounced because of the long mean free paths of fast ions, compared with those of thermal ions. We introduce a fusion utility function to demonstrate essential features of this Knudsen layer effect, in both magnetized and unmagnetized cases. The fusion utility concept is also used to evaluate the restoring reactivity in the Knudsen layer by manipulating fast ions in phase space using waves.

Davidovits, Seth; Fisch, Nathaniel J. [Princeton Plasma Physics Laboratory, Princeton University, Princeton, New Jersey 08544 (United States)

2014-09-15T23:59:59.000Z

Note: This page contains sample records for the topic "magnetic confinement fusion" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


261

Fusion Energy Division annual progress report, period ending December 31, 1989  

SciTech Connect

The Fusion Program of Oak Ridge National Laboratory (ORNL) carries out research in most areas of magnetic confinement fusion. The program is directed toward the development of fusion as an energy source and is a strong and vital component of both the US fusion program and the international fusion community. Issued as the annual progress report of the ORNL Fusion Energy Division, this report also contains information from components of the Fusion Program that are carried out by other ORNL organizations (about 15% of the program effort). The areas addressed by the Fusion Program and discussed in this report 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. Highlights from program activities are included in this report.

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

1991-07-01T23:59:59.000Z

262

Development of imaging bolometers for magnetic fusion reactors (invited)  

SciTech Connect

Imaging bolometers utilize an infrared (IR) video camera to measure the change in temperature of a thin foil exposed to the plasma radiation, thereby avoiding the risks of conventional resistive bolometers related to electric cabling and vacuum feedthroughs in a reactor environment. A prototype of the IR imaging video bolometer (IRVB) has been installed and operated on the JT-60U tokamak demonstrating its applicability to a reactor environment and its ability to provide two-dimensional measurements of the radiation emissivity in a poloidal cross section. In this paper we review this development and present the first results of an upgraded version of this IRVB on JT-60U. This upgrade utilizes a state-of-the-art IR camera (FLIR/Indigo Phoenix-InSb) (3-5 {mu}m, 256x360 pixels, 345 Hz, 11 mK) mounted in a neutron/gamma/magnetic shield behind a 3.6 m IR periscope consisting of CaF{sub 2} optics and an aluminum mirror. The IRVB foil is 7 cmx9 cmx5 {mu}m tantalum. A noise equivalent power density of 300 {mu}W/cm{sup 2} is achieved with 40x24 channels and a time response of 10 ms or 23 {mu}W/cm{sup 2} for 16x12 channels and a time response of 33 ms, which is 30 times better than the previous version of the IRVB on JT-60U.

Peterson, Byron J.; Parchamy, Homaira; Ashikawa, Naoko [National Institute for Fusion Science, Toki 509-5292 (Japan); Kawashima, Hisato; Konoshima, Shigeru [Japan Atomic Energy Agency, Naka 311-0193 (Japan); Kostryukov, Artem Yu.; Miroshnikov, Igor V. [St. Petersburg State Technical University, St. Petersburg 195251 (Russian Federation); Seo, Dongcheol [National Fusion Research Institute, Daejeon 305-333 (Korea, Republic of); Omori, T. [Graduate University for Advanced Studies, Toki 509-5292 (Japan)

2008-10-15T23:59:59.000Z

263

Near-resonant spatial images of confined Bose-Einstein condensates in a 4-Dee magnetic bottle  

Science Journals Connector (OSTI)

We present quantitative measurements of the spatial density profile of Bose-Einstein condensates of sodium atoms confined in a 4-Dee magnetic bottle. The condensates are imaged in transmission with near-resonant laser light. We demonstrate that the Thomas-Fermi surface of a condensate can be determined to better than 1%. More generally, we obtain excellent agreement with mean-field theory. We conclude that precision measurements of atomic scattering lengths and interactions between phase-separated cold atoms in a harmonic trap can be performed with high precision using this method.

Lene Vestergaard Hau; B. D. Busch; Chien Liu; Zachary Dutton; Michael M. Burns; J. A. Golovchenko

1998-07-01T23:59:59.000Z

264

Inertial electrostatic confinement and nuclear fusion in the interelectrode plasma of a nanosecond vacuum discharge. I: Experiment  

SciTech Connect

Properties of an aerosol substance with a high power density in the interelectrode space of a nano- second vacuum discharge are studied. The possibilities of emission and/or trapping of fast ions and hard X-rays by ensembles of clusters and microparticles are analyzed. The possibility of simultaneous partial trapping (diffusion) of X-rays and complete trapping of fast ions by a cluster ensemble is demonstrated experimentally. Due to such trapping, the aerosol ensemble transforms into a 'dusty' microreactor that can be used to investigate a certain class of nuclear processes, including collisional DD microfusion. Operating regimes of such a microreactor and their reproducibility were studied. On the whole, the generation efficiency of hard X-rays and neutrons in the proposed vacuum discharge with a hollow cathode can be higher by two orders of magnitude than that in a system 'high-power laser pulse-cluster cloud.' Multiply repeated nuclear fusion accompanied by pulsating DD neutron emission was reproducibly detected in experiment. Ion acceleration mechanisms in the interelectrode space and the fundamental role of the virtual cathode in observed nuclear fusion processes are discussed.

Kurilenkov, Yu. K. [Russian Academy of Sciences, Joint Institute for High Temperatures (Russian Federation); Skowronek, M. [Universite Pierre et Marie Curie, Laboratoire des Plasmas Denses (France)

2010-12-15T23:59:59.000Z

265

Mon. Not. R. Astron. Soc. 000, 000--000 (0000) Printed 7 June 2001 (MN L A T E X style file v2.2) The magnetic field and wind confinement of fi Cephei  

E-Print Network (OSTI)

.2) The magnetic field and wind confinement of fi Cephei: new clues for interpreting the Be phenomenon? J of the large scale magnetic field and of the associated magnetically confined wind and cir­ cumstellar of 26000 K and age of 12 Myr, viewed with an inclination of the rotation axis of about 60 ffi . Using two

Donati, Jean-François

266

On the efficacy of imploding plasma liners for magnetized fusion target compression  

SciTech Connect

A new theoretical model is formulated to study the idea of merging a spherical array of converging plasma jets to form a 'plasma liner' that further converges to compress a magnetized plasma target to fusion conditions [Y. C. F. Thio et al., 'Magnetized target fusion in a spheroidal geometry with standoff drivers', Current Trends in International Fusion Research II, edited by E. Panarella (National Research Council Canada, Ottawa, Canada, 1999)]. For a spherically imploding plasma liner shell with high initial Mach number (M=liner speed/sound speed) the rise in liner density with decreasing radius r goes as {rho}{approx}1/r{sup 2}, for any constant adiabatic index {gamma}=d ln p/d ln {rho}. Accordingly, spherical convergence amplifies the ram pressure of the liner on target by the factor A{approx}C{sup 2}, indicating strong coupling to its radial convergence C=r{sub m}/R, where r{sub m}(R)=jet merging radius (compressed target radius), and A=compressed target pressure/initial liner ram pressure. Deuterium-tritium (DT) plasma liners with initial velocity {approx}100 km/s and {gamma}=5/3, need to be hypersonic M{approx}60 and thus cold in order to realize values of A{approx}10{sup 4} necessary for target ignition. For optically thick DT liners, T<2 eV, n>10{sup 19}-10{sup 20} cm{sup -3}, blackbody radiative cooling is appreciable and may counteract compressional heating during the later stages of the implosion. The fluid then behaves as if the adiabatic index were depressed below 5/3, which in turn means that the same amplification A=1.6x10{sup 4} can be accomplished with a reduced initial Mach number M{approx_equal}12.7({gamma}-0.3){sup 4.86}, valid in the range (10fusion {alpha}-particle heating of the collapsed liner indicates that 'spark' ignition of the DT liner fuel does not appear to be possible for magnetized fusion targets with typical threshold values of areal density {rho}R<0.02 g cm{sup -2}.

Parks, P. B. [General Atomics, P.O. Box 85608, San Diego, California 92186-5688 (United States)

2008-06-15T23:59:59.000Z

267

Status of target physics for inertial confinement fusion: Report on the review at DOE Headquarters, Germantown, MD on November 14--17, 1988  

SciTech Connect

A four day review to assess the status of target physics of inertial confinement fusion was held at US Department of Energy (DOE) Headquarters on November 14--17, 1988. This review completes the current series of reviews of the inertial fusion program elements to assess the status of the data base for a decision to proceed with the proposed Laboratory Microfusion Facility (LMF) that is being planned. In addition to target physics, the program elements that have been reviewed previously include the driver technology development for KrF and solid-state lasers, and the light-on beam pulsed power system. This series of reviews was undertaken for internal DOE assessment in anticipation of the ICF program review mandated by the Congress in 1988 to be completed in 1990 to assess the significance and implications of the progress that has been realized in the laboratory and the underground Halite/Centurion experiments. For this target physics review, both the direct and the indirect drive approaches were considered. The principal issues addressed in this review were: Is the present target physics data base adequate for a decision to proceed with design and construction of LMF now as opposed to continue planning activities at this time What specific additional target physics data are desirable to reduce the risk for a DOE decision to construct an LMF What is the role for continuation of Halite/Centurion experiments What priority should be given to the direct drive approach Are the program elements optimally structured to resolve the critical issues for an LMF decision Specific findings relating to these five issues are summarized in the following.

Not Available

1990-03-09T23:59:59.000Z

268

IEFIT - An Interactive Approach to High Temperature Fusion Plasma Magnetic Equilibrium Fitting  

SciTech Connect

An interactive IDL based wrapper, IEFIT, has been created for the magnetic equilibrium reconstruction code EFIT written in FORTRAN. It allows high temperature fusion physicists to rapidly optimize a plasma equilibrium reconstruction by eliminating the unnecessarily repeated initialization in the conventional approach along with the immediate display of the fitting results of each input variation. It uses a new IDL based graphics package, GaPlotObj, developed in cooperation with Fanning Software Consulting, that provides a unified interface with great flexibility in presenting and analyzing scientific data. The overall interactivity reduces the process to minutes from the usual hours.

Peng, Q.; Schachter, J.; Schissel, D.P.; Lao, L.L.

1999-06-01T23:59:59.000Z

269

Development of a polar direct-drive platform for studying inertial confinement fusion implosion mix on the National Ignition Facility  

SciTech Connect

Experiments were performed to develop a platform for the simultaneous measurement of mix and its effects on fusion burn. Two polar direct drive implosions of all-plastic capsules were conducted for the first time on the National Ignition Facility (NIF). To measure implosion trajectory and symmetry, area image backlighting of these capsules was also employed for the first time on NIF, an advance over previous 1-D slit imaging experiments, providing detailed symmetry data of the capsules as they imploded. The implosion trajectory and low-mode asymmetry seen in the resultant radiographs agreed with pre-shot predictions even though the 700 kJ drive energy produced laser beam intensities exceeding laser-plasma instability thresholds. Post-shot simulations indicate that the capsule yield was reduced by a factor of two compared to pre-shot predictions owing to as-shot laser drive asymmetries. The pre-shot predictions of bang time agreed within 200 ps with the experimental results. The second shot incorporated a narrow groove encircling the equator of the capsule. A predicted yield reduction factor of three was not observed.

Schmitt, Mark J.; Bradley, Paul A.; Cobble, James A.; Fincke, James R.; Hakel, Peter; Hsu, Scott C.; Krasheninnikova, Natalia S.; Kyrala, George A.; Magelssen, Glenn R.; Montgomery, David S.; Murphy, Thomas J.; Obrey, Kimberly A.; Shah, Rahul C.; Tregillis, Ian L.; Baumgaertel, Jessica A.; Wysocki, Frederick J.; Batha, Steven H. [Los Alamos National Laboratory, MS F699, Los Alamos, New Mexico 87545 (United States)] [Los Alamos National Laboratory, MS F699, Los Alamos, New Mexico 87545 (United States); Stephen Craxton, R.; McKenty, Patrick W. [Laboratory for Laser Energetics, University of Rochester, 250 E. River Road, Rochester, New York 14623 (United States)] [Laboratory for Laser Energetics, University of Rochester, 250 E. River Road, Rochester, New York 14623 (United States); Fitzsimmons, Paul [General Atomics, 3550 General Atomics Court, San Diego, California 92121 (United States)] [General Atomics, 3550 General Atomics Court, San Diego, California 92121 (United States); and others

2013-05-15T23:59:59.000Z

270

An in-flight radiography platform to measure hydrodynamic instability growth in inertial confinement fusion capsules at the National Ignition Facility  

SciTech Connect

A new in-flight radiography platform has been established at the National Ignition Facility (NIF) to measure RayleighTaylor and RichtmyerMeshkov instability growth in inertial confinement fusion capsules. The platform has been tested up to a convergence ratio of 4. An experimental campaign is underway to measure the growth of pre-imposed sinusoidal modulations of the capsule surface, as a function of wavelength, for a pair of ignition-relevant laser drives: a low-foot drive representative of what was fielded during the National Ignition Campaign (NIC) [Edwards et al., Phys. Plasmas 20, 070501 (2013)] and the new high-foot [Dittrich et al., Phys. Rev. Lett. 112, 055002 (2014); Park et al., Phys. Rev. Lett. 112, 055001 (2014)] pulse shape, for which the predicted instability growth is much lower. We present measurements of Legendre modes 30, 60, and 90 for the NIC-type, low-foot, drive, and modes 60 and 90 for the high-foot drive. The measured growth is consistent with model predictions, including much less growth for the high-foot drive, demonstrating the instability mitigation aspect of this new pulse shape. We present the design of the platform in detail and discuss the implications of the data it generates for the on-going ignition effort at NIF.

Raman, K. S.; Smalyuk, V. A.; Casey, D. T.; Haan, S. W.; Hurricane, O. A.; Kroll, J. J.; Peterson, J. L.; Remington, B. A.; Robey, H. F.; Clark, D. S.; Hammel, B. A.; Landen, O. L.; Marinak, M. M.; Munro, D. H.; Salmonson, J. [Lawrence Livermore National Laboratory, Livermore, California 94550 (United States); Hoover, D. E.; Nikroo, A. [General Atomics, San Diego, California 92121 (United States); Peterson, K. J. [Sandia National Laboratory, Albuquerque, New Mexico 87125 (United States)

2014-07-15T23:59:59.000Z

271

The solar tachocline: a self-consistent model of magnetic confinement  

E-Print Network (OSTI)

field lines are advected by the fluid flow, and that the field diffuses at a rate inversely proportional to ?, the electrical conductivity of the plasma. Specifically, ?B ?t = ? (uB? ??B) , (1.3) where ? = (4pi?)?1 is the magnetic diffusivity.5... pi?( 1 2 |B| 2) + 14piB ?B , (1.4) which are separately called the magnetic pressure force and magnetic tension. In the limit of perfect electrical conductivity (i.e. zero magnetic diffusivity) the field lines behave like elastic strings frozen...

Wood, Toby

2011-01-11T23:59:59.000Z

272

Final Report on Development of Optimized Field-Reversed Configuration Plasma Formation Techniques for Magnetized Target Fusion  

SciTech Connect

The University of New Mexico (UNM) proposed a collaboration with Los Alamos National Laboratory (LANL) to develop and test methods for improved formation of field-reversed configuration (FRC) plasmas relevant to magnetized target fusion (MTF) energy research. MTF is an innovative approach for a relatively fast and cheap path to the production of fusion energy that utilizes magnetic confinement to assist in the compression of a hot plasma to thermonuclear conditions by an external driver. LANL is currently pursing demonstration of the MTF concept via compression of an FRC plasma by a metal liner z-pinch in conjunction with the Air Force Research Laboratory in Albuquerque, NM. A key physics issue for the FRC's ultimate success as an MTF target lies in the initial pre-ionization (PI) stage. The PI plasma sets the initial conditions from which the FRC is created. In particular, the PI formation process determines the amount of magnetic flux that can be trapped to form the FRC. A ringing theta pinch ionization (RTPI) technique, such as currently used by the FRX-L device at LANL, has the advantages of high ionization fraction, simplicity (since no additional coils are required), and does not require internal electrodes which can introduce impurities into the plasma. However RTPI has been shown to only trap #24;50% of the initial bias flux at best and imposes additional engineering constraints on the capacitor banks. The amount of trapped flux plays an important role in the FRC's final equilibrium, transport, and stability properties, and provides increased ohmic heating of the FRC through induced currents as the magnetic field decays. Increasing the trapped flux also provides the route to greatest potential gains in FRC lifetime, which is essential to provide enough time to translate and compress the FRC effectively. In conjunction with LANL we initially planned to develop and test a microwave break- down system to improve the initial PI plasma formation. The UNM team would design the microwave optics and oversee the fabrication and assembly of all components and assist with integration into the FRX-L machine control system. LANL would provide a preexisting 65 kW X-band microwave source and some associated waveguide hardware. Once constructed and installed, UNM would take the lead in operating the microwave breakdown system and conducting studies to optimize its use in FRC PI formation in close cooperation with the needs of the LANL MTF team. In conjunction with our LANL collaborators, we decided after starting the project to switch from a microwave plasma breakdown approach to a plasma gun technology to use for enhanced plasma formation in the FRX-L field-reversed configuration experiment at LANL. Plasma guns would be able to provide significantly higher density plasma with greater control over its distribution in time and space within the experiment. This would allow greater control and #12;ne-tuning of the PI plasma formed in the experiment. Multiple plasma guns would be employed to fill a Pyrex glass test chamber (built at UNM) with plasma which would then be characterized and optimized for the MTF effort.

Lynn, Alan

2013-11-01T23:59:59.000Z

273

Plasma sweeper to control the coupling of RF power to a magnetically confined plasma  

DOE Patents (OSTI)

A device for coupling RF power (a plasma sweeper) from a phased waveguide array for introducing RF power to a plasma having a magnetic field associated therewith comprises at least one electrode positioned near the plasma and near the phased waveguide array; and a potential source coupled to the electrode for generating a static electric field at the electrode directed into the plasma and having a component substantially perpendicular to the plasma magnetic field such that a non-zero vector cross-product of the electric and magnetic fields exerts a force on the plasma causing the plasma to drift.

Motley, Robert W. (Princeton, NJ); Glanz, James (Lawrenceville, NJ)

1985-01-01T23:59:59.000Z

274

Magnetic mirror fusion-fission early history and applicability to other systems  

SciTech Connect

In the mid 1970s to mid 1980s the mirror program was stuck with a concept, the Standard Mirror that was Q {approx} 1 where Q=P{sub fusion}/P{sub injection}. Heroic efforts were put into hybridizing thinking added energy and fuel sales would make a commercial product. At the same time the tokamak was thought to allow ignition and ultrahigh Q values of 20 or even higher. There was an effort to use neutral beams to drive the tokamak just like the mirror machines were driven in which case the Q value plunged to a few, however this was thought to be achievable decades earlier than the high Q versions. Meanwhile current drive and other features of the tokamak have seen the projected Q values come down to the range of 10. Meanwhile the mirror program got Q enhancement into high gear and various tandem mirrors projected Q values up towards 10 and with advanced features over 10 with axi-symmetric magnets (See R. F. Post papers), however the experimental program is all but non-existent. Meanwhile, the gas dynamic trap mirror system which is present day state-of-the-art can with low risk produce Q of {approx}0.1 useful for a low risk, low cost neutron source for materials development useful for the development of materials for all fusion concepts (see Simonen white paper: 'A Physics-Based Strategy to Develop a Mirror Fusion-Fission Hybrid' and D.D. Ryutov, 'Axisymmetric MHD-stable mirror as a neutron source and a driver for a fusion-fission hybrid'). Many early hybrid designs with multi-disciplinary teams were carried out in great detail for the mirror system with its axi-symmetric blanket modules. It is recognized that most of these designs are adaptable to tokamak or inertial fusion geometry. When Q is low (1 to 2) economics gives a large economic penalty for high recirculating power. These early studies covered the three design types: Power production, fuel production and waste burning. All three had their place but power production fell away because every study showed fusion machines that were extensively studied by multidisciplinary teams came up with power costs much higher than for existing fission plants except in very large sizes (3 GWe). There was lots of work on waste burning - Ted Parrish - comes to mind. However, fuel production along with power production became nearly everyone's goals. First, fast-fission blankets were favored but later to enhance safety, fission-suppressed blankets came into vogue. Both fuel producing and waste burning hybrid studies were terminated with the advent of accidents, high interest rates, rising 'green like' movement and cheap natural gas for power production. For waste burning and fast-fission fuel producing designs, the blanket energy multiplication was about 10 and economics was OK relative to recirculating power for Q over 2. For fission-suppressed fuel producers, where the blanket multiplication is under 2, the Q needed was over 5. In the mirror program we came at this problem by trying to find a product for mirror fusion technology. We hoped we had a product and studied and promoted it. There was no market pull and when the mirror program collapsed in the US, so did both hybrid programs for mirrors and tokamaks and IFE by the mid 1980s. Today, the problem of what to do with wastes that were supposed to be accepted by the government appears to be a high value market pull. It remains to be shown if fusion neutrons can be generated at low enough cost so that economics will not be a showstopper. For burning only the minor actinides, the economics will be the most favorable. Burning the Pu as well will lower the number of fission reactors supported by each burner fusion machine and hurt economics of the system. The fuel-producing role of fusion to fuel fission reactors remains an important possible use of fusion especially in the early stages of fusion development. It is not clear that burning fission wastes in a fusion machine is more appropriate than burning these wastes in specially designed fission machines. Fusion can produce U-233 along with over 2.4%U-232 making the material large

Moir, R

2009-08-24T23:59:59.000Z

275

Causality detection and turbulence in fusion plasmas  

E-Print Network (OSTI)

This work explores the potential of an information-theoretical causality detection method for unraveling the relation between fluctuating variables in complex nonlinear systems. The method is tested on some simple though nonlinear models, and guidelines for the choice of analysis parameters are established. Then, measurements from magnetically confined fusion plasmas are analyzed. The selected data bear relevance to the all-important spontaneous confinement transitions often observed in fusion plasmas, fundamental for the design of an economically attractive fusion reactor. It is shown how the present method is capable of clarifying the interaction between fluctuating quantities such as the turbulence amplitude, turbulent flux, and Zonal Flow amplitude, and uncovers several interactions that were missed by traditional methods.

van Milligen, B Ph; Ramisch, M; Estrada, T; Hidalgo, C; Alonso, A

2013-01-01T23:59:59.000Z

276

Electron transport in confined structures in very high mobility GaAs in perpendicular magnetic fields  

E-Print Network (OSTI)

In this thesis we study properties of two-dimensional electron transport through constrictions in perpendicular magnetic fields. We present two sets of experiments, one focusing on properties in the integer quantum Hall ...

Radu, Iuliana

2009-01-01T23:59:59.000Z

277

Masked-backlighter technique used to simultaneously image x-ray absorption and x-ray emission from an inertial confinement fusion plasma  

SciTech Connect

A method to simultaneously image both the absorption and the self-emission of an imploding inertial confinement fusion plasma has been demonstrated on the OMEGA Laser System. The technique involves the use of a high-Z backlighter, half of which is covered with a low-Z material, and a high-speed x-ray framing camera aligned to capture images backlit by this masked backlighter. Two strips of the four-strip framing camera record images backlit by the high-Z portion of the backlighter, while the other two strips record images aligned with the low-Z portion of the backlighter. The emission from the low-Z material is effectively eliminated by a high-Z filter positioned in front of the framing camera, limiting the detected backlighter emission to that of the principal emission line of the high-Z material. As a result, half of the images are of self-emission from the plasma and the other half are of self-emission plus the backlighter. The advantage of this technique is that the self-emission simultaneous with backlighter absorption is independently measured from a nearby direction. The absorption occurs only in the high-Z backlit frames and is either spatially separated from the emission or the self-emission is suppressed by filtering, or by using a backlighter much brighter than the self-emission, or by subtraction. The masked-backlighter technique has been used on the OMEGA Laser System to simultaneously measure the emission profiles and the absorption profiles of polar-driven implosions.

Marshall, F. J., E-mail: fredm@lle.rochester.edu; Radha, P. B. [Laboratory for Laser Energetics, University of Rochester, Rochester, New York 14623 (United States)

2014-11-15T23:59:59.000Z

278

Proceedings of the third symposium on the physics and technology of compact toroids in the magnetic fusion energy program  

SciTech Connect

This document contains papers contributed by the participants of the Third Symposium on Physics and Technology of Compact Toroids in the Magnetic Fusion Energy Program. Subjects include reactor aspects of compact toroids, energetic particle rings, spheromak configurations (a mixture of toroidal and poloidal fields), and field-reversed configurations (FRC's that contain purely poloidal field).

Siemon, R.E. (comp.)

1981-03-01T23:59:59.000Z

279

Identification of future engineering-development needs of alternative concepts for magnetic-fusion energy  

SciTech Connect

A qualitative identification of future engineering needs of alternative fusion concepts (AFCs) is presented. These needs are assessed relative to the similar needs of the tokamak in order to emphasize differences in required technology with respect to the well documented mainline approach. Although nearly thirty AFCs can be identified as being associated with some level of reactor projection, redirection, refocusing, and general similarities can be used to generate a reduced AFC list that includes only the bumpy tori, stellarators, reversed-field pinches, and compact toroids. Furthermore, each AFC has the potential of operating as a conventional (low power density, superconducting magnets) or a compact, high-power-density (HPD) system. Hence, in order to make tractable an otherwise difficult task, the future engineering needs for the AFCs are addressed here for conventional versus compact approaches, with the latter being treated as a generic class and the former being composed of bumpy tori, stellarators, reversed-field pinches, and compact toroids.

Krakowski, R.A.

1982-01-01T23:59:59.000Z

280

DOE-STD-6002-96; DOE Standard Safety of Magnetic Fusion Facilities: Requirements  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

6002-96 6002-96 May 1996 DOE STANDARD SAFETY OF MAGNETIC FUSION FACILITIES: REQUIREMENTS U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. This document has been reproduced directly from the best available copy. Available to DOE and DOE contractors from the Office of Scientific and Technical Information, P.O. Box 62, Oak Ridge, TN 37831; (423) 576-8401. Available to the public from the U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161; (703) 487-4650. Order No. DE96009495 DOE-STD-6002-96 iii TABLE OF CONTENTS Page FOREWORD....................................................................................................................... v

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281

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.

1994-03-01T23:59:59.000Z

282

Fusion Plasma Theory project summaries  

SciTech Connect

This Project Summary book is a published compilation consisting of short descriptions of each project supported by the Fusion Plasma Theory and Computing Group of the Advanced Physics and Technology Division of the Department of Energy, Office of Fusion Energy. The summaries contained in this volume were written by the individual contractors with minimal editing by the Office of Fusion Energy. Previous summaries were published in February of 1982 and December of 1987. The Plasma Theory program is responsible for the development of concepts and models that describe and predict the behavior of a magnetically confined plasma. Emphasis is given to the modelling and understanding of the processes controlling transport of energy and particles in a toroidal plasma and supporting the design of the International Thermonuclear Experimental Reactor (ITER). A tokamak transport initiative was begun in 1989 to improve understanding of how energy and particles are lost from the plasma by mechanisms that transport them across field lines. The Plasma Theory program has actively-participated in this initiative. Recently, increased attention has been given to issues of importance to the proposed Tokamak Physics Experiment (TPX). Particular attention has been paid to containment and thermalization of fast alpha particles produced in a burning fusion plasma as well as control of sawteeth, current drive, impurity control, and design of improved auxiliary heating. In addition, general models of plasma behavior are developed from physics features common to different confinement geometries. This work uses both analytical and numerical techniques. The Fusion Theory program supports research projects at US government laboratories, universities and industrial contractors. Its support of theoretical work at universities contributes to the office of Fusion Energy mission of training scientific manpower for the US Fusion Energy Program.

Not Available

1993-10-01T23:59:59.000Z

283

Low radioactive and hybrid fusion A path to clean energy  

Science Journals Connector (OSTI)

Abstract Aneutronic/low radioactive fuel is the way to clean and cheap energy of the future. An alternative scheme using compact toroids field-reversed configuration or spheromak may be applied for the reactor based on any magnetic confinement system. Even more, any fusion concept, including hybrid magneto-inertial fusion might use advantages of D3He fuel. Advanced fuel, including helium-3 based fusion plasma and alternative systems are reviewed. Different schemes of reactors, near-term technology and non-electric applications are discussed.

Sergei V. Ryzhkov

2015-01-01T23:59:59.000Z

284

Atomic Physics and Thermonuclear Fusion Research  

Science Journals Connector (OSTI)

Presently thermonuclear fusion research is faced with a number of atomic and molecular physics problems depending on the type of high-temperature plasma investigated. The present article discusses some particular atomic physics aspects in connection with magnetically confined plasmas (Tokamaks, Stellarators): (1) rate equations for density, momentum and energy with application to plasmas; (2) initial phase of Tokamak plasmas; (3) influence of impurity radiation on operating conditions of fusion plasmas in general and on Tokamak plasmas in particular; (4) influence of atomic elementary reactions on thermodynamic plasma properties; (5) level structures of highly ionized atoms; (6) spectroscopic diagnostic problems.

H W Drawin

1981-01-01T23:59:59.000Z

285

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

E-Print Network (OSTI)

19 8 Magnetic Fusion Energy Science (MFES) Case 2017 8 Magnetic Fusion Energy Science (MFES) Case and NERSC Senior Science Advisor Magnetic Fusion

Gerber, Richard

2014-01-01T23:59:59.000Z

286

Large Scale Computing and Storage Requirements for Fusion Energy Sciences Research  

E-Print Network (OSTI)

General Plasma Science Magnetic Fusion Energy Magneticfor Fusion Energy Sciences Magnetic Fusion Plasma from the crosscutting science of magnetic reconnection and

Gerber, Richard

2012-01-01T23:59:59.000Z

287

Three-dimensional linear peeling-ballooning theory in magnetic fusion devices  

SciTech Connect

Ideal magnetohydrodynamics theory is extended to fully 3D magnetic configurations to investigate the linear stability of intermediate to high n peeling-ballooning modes, with n the toroidal mode number. These are thought to be important for the behavior of edge localized modes and for the limit of the size of the pedestal that governs the high confinement H-mode. The end point of the derivation is a set of coupled second order ordinary differential equations with appropriate boundary conditions that minimize the perturbed energy and that can be solved to find the growth rate of the perturbations. This theory allows of the evaluation of 3D effects on edge plasma stability in tokamaks such as those associated with the toroidal ripple due to the finite number of toroidal field coils, the application of external 3D fields for elm control, local modification of the magnetic field in the vicinity of ferromagnetic components such as the test blanket modules in ITER, etc.

Weyens, T., E-mail: tweyens@fis.uc3m.es; Snchez, R.; Garca, L. [Departamento de Fsica, Universidad Carlos III de Madrid, Madrid 28911 (Spain)] [Departamento de Fsica, Universidad Carlos III de Madrid, Madrid 28911 (Spain); Loarte, A.; Huijsmans, G. [ITER Organization, Route de Vinon sur Verdon, 13067 Saint Paul Lez Durance (France)] [ITER Organization, Route de Vinon sur Verdon, 13067 Saint Paul Lez Durance (France)

2014-04-15T23:59:59.000Z

288

Space-charge waves in magnetized and collisional quantum plasma columns confined in carbon nanotubes  

SciTech Connect

We study the dispersion relation of electrostatic waves propagating in a column of quantum magnetized collisional plasma embraced completely by a metallic single-walled carbon nanotubes. The analysis is based on the quantum linearized hydrodynamic formalism of collective excitations within the quasi-static approximation. It is shown when the electronic de Broglie's wavelength of the plasma is comparable in the order of magnitude to the radius of the nanotube, the quantum effects are quite meaningful and our model anticipates one acoustical and two optical space-charge waves which are positioned into three propagating bands. With increasing the nanotube radius, the features of the acoustical branch remain unchanged, yet two distinct optical branches are degenerated and the classical behavior is recovered. This study might provide a platform to create new finite transverse cross section quantum magnetized plasmas and to devise nanometer dusty plasmas based on the metallic carbon nanotubes in the absence of either a drift or a thermal electronic velocity and their existence could be experimentally examined.

Bagheri, Mehran, E-mail: mh-bagheri@sbu.ac.ir [Laser and Plasma Research Institute, Shahid Beheshti University, G. C., Evin, Tehran 19835-63113 (Iran, Islamic Republic of)] [Laser and Plasma Research Institute, Shahid Beheshti University, G. C., Evin, Tehran 19835-63113 (Iran, Islamic Republic of); Abdikian, Alireza, E-mail: abdykian@gmail.com [Department of Physics, Malayer University, Malayer 65719-95863 (Iran, Islamic Republic of)] [Department of Physics, Malayer University, Malayer 65719-95863 (Iran, Islamic Republic of)

2014-04-15T23:59:59.000Z

289

Fusion reactor systems  

Science Journals Connector (OSTI)

In this review we consider deuterium-tritium (D-T) fusion reactors based on four different plasma-confinement and heating approaches: the tokamak, the theta-pinch, the magnetic-mirror, and the laser-pellet system. We begin with a discussion of the dynamics of reacting plasmas and basic considerations of reactor power balance. The essential plasma physical aspects of each system are summarized, and the main characteristics of the corresponding conceptual power plants are described. In tokamak reactors the plasma densities are about 1020 m-3, and the ? values (ratio of plasma pressure to confining magnetic pressure) are approximately 5%. Plasma burning times are of the order of 100-1000 sec. Large superconducting dc magnets furnish the toroidal magnetic field, and 2-m thick blankets and shields prevent heat deposition in the superconductor. Radially diffusing plasma is diverted away from the first wall by means of null singularities in the poloidal (or transverse) component of the confining magnetic field. The toroidal theta-pinch reactor has a much smaller minor diameter and a much larger major diameter, and operates on a 10-sec cycle with 0.1-sec burning pulses. It utilizes shock heating from high-voltage sources and adabatic-compression heating powered by low-voltage, pulsed cryogenic magnetic or inertial energy stores, outside the reactor core. The plasma has a density of about 1022 m-3 and ? values of nearly unity. In the power balance of the reactor, direct-conversion energy obtained by expansion of the burning high-? plasma against the containing magnetic field is an important factor. No divertor is necessary since neutral-gas flow cools and replaces the "spent" plasma between pulses. The open-ended mirror reactor uses both thermal conversion of neutron energy and direct conversion of end-loss plasma energy to dc electrical power. A fraction of this direct-convertor power is then fed back to the ioninjection system to sustain the reaction and maintain the plasma. The average ion energy is 600 keV, plasma diameter 6 m, and the plasma beta 85%. The power levels of the three magnetic-confinement devices are in the 500-2000 MWe range, with the exception of the mirror reactor, for which the output is approximately 200 MWe. In Laser-Pellet reactors, frozen D-T pellets are ignited in a cavity which absorbs the electromagnetic, charged particle, and neutron energy from the fusion reaction. The confinement is "inertial," since the fusion reaction occurs during the disassembly of the heated pellet. A pellet-cavity unit would produce about 200 MWt in pulses with a repetition rate of the order of 10 sec-1. Such units could be clustered to give power plants with outputs in the range of 1000 MWe.

F. L. Ribe

1975-01-01T23:59:59.000Z

290

Quasilinear theory of collisionless Fermi acceleration in a multicusp magnetic confinement geometry  

E-Print Network (OSTI)

Particle motion in a cylindrical multiple-cusp magnetic field configuration is shown to be highly (though not completely) chaotic, as expected by analogy with the Sinai billiard. This provides a collisionless, linear mechanism for phase randomization during monochromatic wave heating. A general quasilinear theory of collisionless energy diffusion is developed for particles with a Hamiltonian of the form $H_0+H_1$, motion in the \\emph{unperturbed} Hamiltonian $H_0$ being assumed chaotic, while the perturbation $H_1$ can be coherent (i.e. not stochastic). For the multicusp geometry, two heating mechanisms are identified --- cyclotron resonance heating of particles temporarily mirror-trapped in the cusps, and nonresonant heating of nonadiabatically reflected particles (the majority). An analytically solvable model leads to an expression for a transit-time correction factor, exponentially decreasing with increasing frequency. The theory is illustrated using the geometry of a typical laboratory experiment.

Robert L. Dewar; Carmen I. Ciubotariu

1999-05-10T23:59:59.000Z

291

Exploring Plasma Science Advances from Fusion Findings to Astrophysica...  

NLE Websites -- All DOE Office Websites (Extended Search)

confinement fusion experiments at the National Ignition Facility (NIF) at the DOE's Lawrence Livermore National Laboratory. Speakers noted that producing fusion by heating a...

292

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

E-Print Network (OSTI)

plasmas for thermonuclear fusion. Because of the Thermonuclear Research (CTR) and the National Magnetic Fusion

Gerber, Richard

2014-01-01T23:59:59.000Z

293

Progress on the FRX-L FRC plasma injector at LANL for magnetized target fusion  

SciTech Connect

The FRX-L Field Reversed Configuration plasma is now operational at Los Alamos National Laboratory. The goal of the project is to demonstrate the production of suitable FRC target plasmas for later MTF (Magnetized Target Fusion) implosion experiments which will first be carried out at the Air Force Research Laboratory in Albuquerque, New Mexico, in a few years' time. Expected plasma parameters in the 4 cm diameter, 30 cm long FRC are ne{approx}1017 cm-3, T{approx}100-300 eV, at 4-5 Tesla fields, with a lifetime of {approx}20 microseconds. The system includes a 0.5 T bias field, 70 kV 250 kHz ringing pre-ionization, and a 1.5 MA, 200 kJ main-theta coil bank. Maxwell rail gap plasma switches are used to start the PI bank, the main theta coil bank, and to crowbar the main bank. Initial results using the first diagnostic set of excluded flux loops, B-dot probes, visible light diodes, a fiber-optically coupled gated intensified visible spectrometer, and a 3.3 micron quadrature interferometer are presented. Future diagnostics include end-on bolometry, Thomson scattering, and a multi-chord fanned HeNe side-on interferometer. Multi-turn cusp and guide coils will be added later this year, to enable translation experiments into a cylindrical metal liner.

Assmus, P. N. (Phillip N.); Feinup, W. J.; Intrator, Thomas; Langner, M. C. (Matthew C.); Maqueda, R. J. (Ricardo J.); Scott, K. J.; Siemon, R. E. (Richard E.); Tejero, E. M. (Erik M.); Taccetti, J. M. (Jose Martin); Tuszewski, M. G. (Michael G.); Wang, Z. (Zhehui); Wurden, G. A. (Glen A.)

2001-01-01T23:59:59.000Z

294

Operating experience of the IFSMTF (International Fusion Superconducting Magnet Test Facility) vapor-cooled lead system  

SciTech Connect

The International Fusion Superconducting Magnet Test Facility (IFSMTF) uses six pairs of vapor-cooled leads (VCLs) to introduce electric power to six test coils. Each VCL is housed in a dewar outside the 11-m vacuum vessel and is connected to the coal via a superconducting bus duct;the various VCLs are rated at 12 to 20 kA. Heat loss through the leads constitutes the single largest source of heat load to the cryogenic system. Concerns about voltage breakdown if a coil quenches have led to precautionary measures such as installation of a N/sub 2/-purged box near the top of the lead and shingles to collect water that condenses on the power buses. A few joints between power buses and VCLs were found to be inadequate during preliminary single-coil tests. This series of tests also pointed to the need for automatic control of helium flow through the leads. This was achieved by using the resistance measurements of the leads to control flow valves automatically. By the time full-array tests were started, a working scheme had developed that required little attention to the leads and that had little impact on the refrigerator between zero and full current to the coils. The operating loss of the VCLs at full current is averaging at about 7.4 gs of warm flow and 360 W of cold-gas return load. These results are compared with predictions that were based on earlier tests. 4 refs., 6 figs

Lue, J.W.; Fehling, D.T.; Fietz, W.A.; Lubell, M.S.; Luton, J.N.; Schwenterly, S.W.; Shen, S.S.; Stamps, R.E.; Thompson, D.H.; Wilson, C.T.

1987-01-01T23:59:59.000Z

295

Stability tests of the Westinghouse coil in the International Fusion Superconducting Magnet Test Facility  

SciTech Connect

The Westinghouse coil is one of three forced-flow coils in the six-coil toroidal array of the International Fusion Superconducting Magnet Test Facility at Oak Ridge National Laboratory. It is wound with an 18-kA, Nb/sub 3/Sn/Cu, cable-in-conduit superconductor structurally supported by aluminum plates and cooled by 4-K, 15-atm supercritical helium. The coil is instrumented to permit measurement of helium temperature, pressure, and flow rate; structure temperature and strain; field; and normal zone voltage. A resistive heater has been installed to simulate nuclear heating, and inductive heaters have been installed to facilitate stability testing. The coil has been tested both individually and in the six-coil array. The tests covered charging to full design current and field, measuring the current-sharing threshold temperature using the resistive heaters, and measuring the stability margin using the pulsed inductive heaters. At least one section of the conductor exhibits a very broad resistive transition (resistive transition index = 4). The broad transition, though causing the appearance of voltage at relatively low temperatures, does not compromise the stability margin of the coil, which was greater than 1.1 J/cm/sup 3/ of strands. In another, nonresistive location, the stability margin was between 1.7 and 1.9 J/cm/sup 3/ of strands. The coil is completely stable in operation at 100% design current in both the single- and six-coil modes.

Dresner, L.; Fehling, D.T.; Lubell, M.S.; Lue, J.W.; Luton, J.N.; McManamy, T.J.; Shen, S.S.; Wilson, C.T.

1987-09-01T23:59:59.000Z

296

Stability tests of the Westinghouse coil in the International Fusion Superconducting Magnet Test Facility  

SciTech Connect

The Westinghouse coil is one of three forced-flow coils in the six-coil toroidal array of the International Fusion Superconducting Magnet Test Facility at Oak Ridge National Laboratory. It is wound with an 18-kA, Nb/sub 3/Sn/Cu, cable-in-conduit superconductor structurally supported by aluminum plates and cooled by 4-K, 15-atm supercritical helium. The coil has been tested both individually and in the six-coil array. The tests covered charging to full design current and field, measuring the current-sharing threshold temperature using the resistive heaters, and measuring the stability margin using the pulsed inductive heaters. At least one section of the conductor exhibits a very broad resistive transition. The broad transition, though causing the appearance of voltage at relatively low temperatures, does not compromise the stability margin of the coil, which was greater than 1.1J/cm/sup 3/ of strands. In another nonresistive location, the stability margin was between 1.7 and 1.9 J/cm/sup 3/ of strands. The coil is completely stable in operation at 100% design current in both the single- and six-coil modes.

Dresner, L.; Fehling, D.T.; Lubell, M.S.; Lue, J.W.; Luton, J.N.; McManamy, T.J.; Shen, S.S.; Wilson, C.T.

1988-03-01T23:59:59.000Z

297

TWO IMPORTANT FUSION PROCESSES CREATING THE CONDITIONS FOR FUSION  

NLE Websites -- All DOE Office Websites (Extended Search)

IMPORTANT FUSION PROCESSES CREATING THE CONDITIONS FOR FUSION F u s i o n Physics of a Fundamental Energy Source C o n f i n e m e n t Q u a l i t y , n τ ( m - 3 s ) 1970-75 1990s 1975-80 1980s Ion Temperature (K) 10 21 10 20 10 19 10 18 10 17 10 6 10 7 10 8 10 9 Inertial Magnetic Expected reactor regime Expected reactor regime Useful Nuclear Masses (The electron's mass is 0.000549 u.) Label Species Mass (u*) n ( 1 n) neutron 1.008665 p ( 1 H) proton 1.007276 D ( 2 H) deuteron 2.013553 T ( 3 H) triton 3.015500 3 He helium-3 3.014932 α ( 4 He) helium-4 4.001505 * 1 u = 1.66054 x 10 -27 kg = 931.466 MeV/c 2 Nuclear Mass (u) B i n d i n g E n e r g y P e r N u c l e o n ( M e V ) 1 200 150 100 50 10 0 5 62 Ni Fusion Reactions Release Energy Fission Reactions Release Energy EXPERIMENTAL RESULTS IN FUSION RESEARCH Fusion requires high tempera- ture plasmas confined long enough at high density

298

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)

2012-05-15T23:59:59.000Z

299

Status of inertial fusion in the United States  

SciTech Connect

This report briefly discusses the concept, progress, and direction of inertial confinement fusion in the United States. (LSP)

Coleman, L.

1991-10-01T23:59:59.000Z

300

COLLABORATIVE: FUSION SIMULATION PROGRAM  

SciTech Connect

New York University, Courant Institute of Mathematical Sciences, participated in the ???¢????????Fusion Simulation Program (FSP) Planning Activities???¢??????? [http://www.pppl.gov/fsp], with C.S. Chang as the institutional PI. FSP???¢????????s mission was to enable scientific discovery of important new plasma phenomena with associated understanding that emerges only upon integration. This requires developing a predictive integrated simulation capability for magnetically-confined fusion plasmas that are properly validated against experiments in regimes relevant for producing practical fusion energy. Specific institutional goal of the New York University was to participate in the planning of the edge integrated simulation, with emphasis on the usage of large scale HPCs, in connection with the SciDAC CPES project which the PI was leading. New York University successfully completed its mission by participating in the various planning activities, including the edge physics integration, the edge science drivers, and the mathematical verification. The activity resulted in the combined report that can be found in http://www.pppl.gov/fsp/Overview.html. Participation and presentations as part of this project are listed in a separation file.

Chang, Choong Seock

2012-06-05T23:59:59.000Z

Note: This page contains sample records for the topic "magnetic confinement fusion" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


301

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.

1995-09-01T23:59:59.000Z

302

Research Needs for Magnetic Fusion Energy Sciences. Report of the Research Needs Workshop (ReNeW) Bethesda, Maryland, June 8-12, 2009  

SciTech Connect

Nuclear fusion - the process that powers the sun - offers an environmentally benign, intrinsically safe energy source with an abundant supply of low-cost fuel. It is the focus of an international research program, including the ITE R fusion collaboration, which involves seven parties representing half the world's population. The realization of fusion power would change the economics and ecology of energy production as profoundly as petroleum exploitation did two centuries ago. The 21st century finds fusion research in a transformed landscape. The worldwide fusion community broadly agrees that the science has advanced to the point where an aggressive action plan, aimed at the remaining barriers to practical fusion energy, is warranted. At the same time, and largely because of its scientific advance, the program faces new challenges; above all it is challenged to demonstrate the timeliness of its promised benefits. In response to this changed landscape, the Office of Fusion Energy Sciences (OFES ) in the US Department of Energy commissioned a number of community-based studies of the key scientific and technical foci of magnetic fusion research. The Research Needs Workshop (ReNeW) for Magnetic Fusion Energy Sciences is a capstone to these studies. In the context of magnetic fusion energy, ReNeW surveyed the issues identified in previous studies, and used them as a starting point to define and characterize the research activities that the advance of fusion as a practical energy source will require. Thus, ReNeW's task was to identify (1) the scientific and technological research frontiers of the fusion program, and, especially, (2) a set of activities that will most effectively advance those frontiers. (Note that ReNeW was not charged with developing a strategic plan or timeline for the implementation of fusion power.) This Report presents a portfolio of research activities for US research in magnetic fusion for the next two decades. It is intended to provide a strategic framework for realizing practical fusion energy. The portfolio is the product of ten months of fusion-community study and discussion, culminating in a Workshop held in Bethesda, Maryland, from June 8 to June 12, 2009. The Workshop involved some 200 scientists from Universities, National Laboratories and private industry, including several scientists from outside the US. Largely following the Basic Research Needs model established by the Office of Basic Energy Sciences (BES ), the Report presents a collection of discrete research activities, here called 'thrusts.' Each thrust is based on an explicitly identified question, or coherent set of questions, on the frontier of fusion science. It presents a strategy to find the needed answers, combining the necessary intellectual and hardware tools, experimental facilities, and computational resources into an integrated, focused program. The thrusts should be viewed as building blocks for a fusion program plan whose overall structure will be developed by OFES , using whatever additional community input it requests. Part I of the Report reviews the issues identified in previous fusion-community studies, which systematically identified the key research issues and described them in considerable detail. It then considers in some detail the scientific and technical means that can be used to address these is sues. It ends by showing how these various research requirements are organized into a set of eighteen thrusts. Part II presents a detailed and self-contained discussion of each thrust, including the goals, required facilities and tools for each. This Executive Summary focuses on a survey of the ReNeW thrusts. The following brief review of fusion science is intended to provide context for that survey. A more detailed discussion of fusion science can be found in an Appendix to this Summary, entitled 'A Fusion Primer.'

None

2009-06-08T23:59:59.000Z

303

Observation of strong electromagnetic fields around laser-entrance holes of ignition-scale hohlraums in inertial-confinement fusion experiments at the National Ignition Facility  

E-Print Network (OSTI)

Science and Fusion Center, Massachusetts Institute of Technology, Cambridge, MA 02139 USA 2 Lawrence Livermore National Laboratory, Livermore, CA 94550 USA 3 Los Alamos National Laboratory, Los Alamos, NM) experiments utilizing ignition-scaled hohlraums at the National Ignition Facility (NIF). A striking

304

To: ! Members of the National Academy of Sciences Committee on the Prospects for Inertial Confinement Fusion Energy Systems, and the Panel  

E-Print Network (OSTI)

, retired, former head of the laser fusion program at the Naval Research Laboratory Date: ! December 9, 2011 Koonin, it was told to assume that the NIF (National Ignition Facility) would reach ignition. Over the past year, Dr. Koonin periodically reviewed the progress towards ignition at the NIF. In his

305

Film Boiling in Magnetic Field in Liquid Metals with Particular Reference to Fusion Reactor Project  

Science Journals Connector (OSTI)

Efficient heat removal at high temperatures is a key issue for blankets in nuclear fusion applications, for example, the EVOLVE (EVaporation...1], Wong etal. [2]). It utilizes the extremely high heat of vaporiza...

F. J. Arias

2010-04-01T23:59:59.000Z

306

ARC: A compact, high-field, fusion nuclear science facility and demonstration power plant with demountable magnets  

E-Print Network (OSTI)

The affordable, robust, compact (ARC) reactor conceptual design study aims to reduce the size, cost, and complexity of a combined fusion nuclear science facility (FNSF) and demonstration fusion Pilot power plant. ARC is a 270 MWe tokamak reactor with a major radius of 3.3 m, a minor radius of 1.1 m, and an on-axis magnetic field of 9.2 T. ARC has rare earth barium copper oxide (REBCO) superconducting toroidal field coils, which have joints to enable disassembly. This allows the vacuum vessel to be replaced quickly, mitigating first wall survivability concerns, and permits a single device to test many vacuum vessel designs and divertor materials. The design point has a plasma fusion gain of Q_p~13.6, yet is fully non-inductive, with a modest bootstrap fraction of only ~63%. Thus ARC offers a high power gain with relatively large external control of the current profile. This highly attractive combination is enabled by the ~23 T peak field on coil with newly available REBCO superconductor technology. External cu...

Sorbom, B N; Palmer, T R; Mangiarotti, F J; Sierchio, J M; Bonoli, P; Kasten, C; Sutherland, D A; Barnard, H S; Haakonsen, C B; Goh, J; Sung, C; Whyte, D G

2014-01-01T23:59:59.000Z

307

Progress and prospect of laser thermonuclear fusion  

Science Journals Connector (OSTI)

Report presented at the International Seminar on Present Status and Future Plan of Inertial Confinement Fusion, Tokyo, Japan, 26 November 1992.

N G Basov

1993-01-01T23:59:59.000Z

308

Potential and desire for HTS application in thermonuclear fusion  

Science Journals Connector (OSTI)

Superconducting magnets are stringent for fusion reactors with magnetic confinement to provide an economic energy balance. Large-scale development programmes have been executed worldwide to achieve in time the needed technology. The ultimate result of this effort, so far, is the ITER magnet system with the most sophisticated LTS. However, if one thinks about the design of a fusion DEMO and later reactors, the option of HTS must be considered seriously in view of the potential advantages of these conductors concerning higher operation temperature, temperature margin, high field properties and cryogenic power saving. Extrapolating from the long period needed for the ITER conductor development, it is time now to start with HTS development for fusion reactors to be able to decide their applicability. It is still a long way for the HTS to become comparable with LTS, however, continuous progress can be seen. Beside the large confinement magnets, HTS will also be of advantage for current leads, bus bars and gyrotron magnets. The state of the art of HTS is such, that already now such components can be constructed with HTS.

P. Komarek

2006-01-01T23:59:59.000Z

309

Inertial fusion energy studies in the UK  

E-Print Network (OSTI)

#12;The types of research - Fusion ·Absorption and partition of laser energy ­ effects of laserInertial fusion energy studies in the UK Dr Kate Lancaster #12;Inertial Confinement Fusion #12 burns because the alpha particles produced deposit more energy and make more fusion reactions happen

310

STOCHASTIC ACCELERATION BY A SINGLE WAVE IN A MAGNETIZED PLASMA  

E-Print Network (OSTI)

An approach to thermonuclear fusion, initiated in the earlyapproaches to thermonuclear fusion by means of magnetic

Smith, G.R.

2010-01-01T23:59:59.000Z

311

Paths to Magne,c Fusion Energy (nature ignores budget austerity)  

E-Print Network (OSTI)

Base Research Program Plasma confinement Materials science/engineering 2020 to fusion energy present DIII-D NSTX CMOD Plasma confinement research program #12

312

Paths to fusion energy The next 30 years, the next 10 years  

E-Print Network (OSTI)

Facility ITER Demonstra9on Power Plant Base Research Program Plasma confinement Plasma confinement research program #12;Issues for a fusion roadmap · Trade

313

Fusion Energy Division annual progress report period ending December 31, 1983  

SciTech Connect

The Fusion Program carries out work in a number of areas: (1) experimental and theoretical research on two magnetic confinement concepts - the ELMO Bumpy Torus (EBT) and the tokamak, (2) theoretical and engineering studies on a third concept - the stellarator, (3) engineering and physics of present-generation fusion devices, (4) development and testing of diagnostic tools and techniques, (5) development and testing of materials for fusion devices, (6) development and testing of the essential technologies for heating and fueling fusion plasmas, (7) development and testing of the superconducting magnets that will be needed to confine these plasmas, (8) design of future devices, (9) assessment of the environmental impact of fusion energy, and (10) assembly and distribution to the fusion community of data bases on atomic physics and radiation effects. The interactions between these activities and their integration into a unified program are major factors in the success of the individual activities, and the ORNL Fusion Program strives to maintain a balance among these activities that will lead to continued growth.

Not Available

1984-09-01T23:59:59.000Z

314

10 IEEE TRANSACTIONS ON PLASMA SCIENCE, VOL. 30, NO. 1, FEBRUARY 2002 Study of Magnetic Helicity Injection via Plasma  

E-Print Network (OSTI)

, spheromak. MAGNETIC helicity [1] is a quantity which describes the amount of twist or writhe in the magnetic-confined plasmas in fusion research (e.g., spheromaks) must be sustained somehow, i.e., via helicity injection a schematic of the experimental setup. A coaxial spheromak gun with large planar geometry is installed on one

Hsu, Scott

315

Development of tritium technology for the United States magnetic fusion energy program  

SciTech Connect

Tritium technology development for the DOE fusion program is taking place principally at three laboratories, Mound Facility, Argonne National Laboratory and the Los Alamos Scientific Laboratory. This paper will review the major aspects of each of the three programs and look at aspects of the tritium technology being developed at other laboratories within the United States. Facilities and experiments to be discussed include the Tritium Effluent Control Laboratory and the Tritium Storage and Delivery System for the Tokamak Fusion Test Reactor at Mound Facility; the Lithium Processing Test Loop and the solid breeder blanket studies at Argonne; and the Tritium Systems Test Assembly at Los Alamos.

Anderson, J.L.; Wilkes, W.R.

1980-01-01T23:59:59.000Z

316

Fusion Engineering and Design 7579 (2005) 2932 First integrated test of the superconducting magnet systems  

E-Print Network (OSTI)

Fusion Engineering and Design 75­79 (2005) 29­32 First integrated test of the superconducting of Applied Physics and Applied Mathematics Room 210 S.W., Mudd Building, New York, NY 10027, USA Available at the center of a 5 m diameter, 3 m tall vacuum chamber. The Floating coil (F-coil) is designed for a maximum

317

Theory of plasma transport in toroidal confinement systems  

Science Journals Connector (OSTI)

The dissipation induced by coulomb-collisional scattering provides an irreducible minimum, and thus a useful standard for comparison, for transport processes in a hot, magnetically confined plasma. The kinetic description of this dissipation is provided by an equation of the Fokker-Planck form. As in the standard transport theory for a neutral gas, approximate solution of the Fokker-Planck equation permits the calculation of transport coefficients, which linearly relate the fluxes of particles, energy, and electric charge, to the density and temperature gradients, and to the electric field. The transport relations are useful in studying the confinement properties of present and future experimental devices for research in controlled thermonuclear fusion. The transport theory for a magnetized plasma (in which the Larmor radius is much smaller than gradient scale lengths describing the plasma fluid) departs from the theory for a neutral gas in several fundamental ways. Thus, transport coefficients for a magnetized plasma can be calculated even when the collisional mean free path is much longer than the gradient scale length (as would pertain in thermonuclear regimes). Such transport coefficients are generally nonlocal, being defined in terms of averages over surfaces with macroscopic dimensions. Furthermore, when the mean free path is long, the magnetized-plasma transport coefficients depend crucially upon the magnetic field geometry, the effects of which must be treated at the kinetic level of the Fokker-Planck equation. The results display several novel couplings between collisional dissipation and the electromagnetic field. The present review of magnetized-plasma transport theory is intended to be as widely accessible as possible. Thus the relevant features of magnetic confinement in closed (toroidal) systems, and of charged particles in spatially varying fields, are derived, at least in outline, from first principles. Although consideration is given to "classical" transport in which most field geometric effects are omitted, major emphasis is placed on the "neoclassical" theory which has been developed over the last decade. Neoclassical transport coefficients are specifically relevant to a magnetically confined plasma, rather than to just a magnetized plasma; their unusual features, such as nonlocality and geometry dependence, become particularly important in the high temperature regime of proposed thermonuclear reactors. The area of neoclassical theory which seems most completeits application to axisymmetric tokamak-type confinement systemsis correspondingly stressed.

F. L. Hinton and R. D. Hazeltine

1976-04-01T23:59:59.000Z

318

Elmo bumpy square plasma confinement device  

DOE Patents (OSTI)

The invention is an Elmo bumpy type plasma confinement device having a polygonal configuration of closed magnet field lines for improved plasma confinement. In the preferred embodiment, the device is of a square configuration which is referred to as an Elmo bumpy square (EBS). The EBS is formed by four linear magnetic mirror sections each comprising a plurality of axisymmetric assemblies connected in series and linked by 90/sup 0/ sections of a high magnetic field toroidal solenoid type field generating coils. These coils provide corner confinement with a minimum of radial dispersion of the confined plasma to minimize the detrimental effects of the toroidal curvature of the magnetic field. Each corner is formed by a plurality of circular or elliptical coils aligned about the corner radius to provide maximum continuity in the closing of the magnetic field lines about the square configuration confining the plasma within a vacuum vessel located within the various coils forming the square configuration confinement geometry.

Owen, L.W.

1985-01-01T23:59:59.000Z

319

The impact of pulsed irradiation upon neutron activation calculations for inertial and magnetic fusion energy power plants  

SciTech Connect

Inertial fusion energy (IFE) and magnetic fusion energy (MFE) power plants will probably operate in a pulsed mode. The two different schemes, however, will have quite different time periods. Typical repetition rates for IFE power plants will be 1-5 Hz. MFE power plants will ramp up in current for about 1 hour, shut down for several minutes, and repeat the process. Traditionally, activation calculations for IFE and MFE power plants have assumed continuous operation and used either the ``steady state`` (SS) or ``equivalent steady state`` (ESS) approximations. It has been suggested recently that the SS and ESS methods may not yield accurate results for all radionuclides of interest. The present work expands that of Sisolak, et al. by applying their formulae to conditions which might be experienced in typical IFE and MFE power plants. In addition, complicated, multi-step reaction/decay chains are analyzed using an upgraded version of the ACAB radionuclide generation/depletion code. Our results indicate that the SS method is suitable for application to MFE power plant conditions. We also find that the ESS method generates acceptable results for radionuclides with half-lives more than a factor of three greater than the time between pulses. For components that are subject to 0.05 Hz (or more frequent) irradiation (such as coolant), use of the ESS method is recommended. For components or materials that are subject to less frequent irradiation (such as high-Z target materials), pulsed irradiation calculations should be used.

Latkowski, J.F. [Lawrence Livermore National Lab., CA (United States); Sanz, J. [Universidad Politecnica de Madrid (Spain); Vujic, J.L. [California Univ., Berkeley, CA (United States)

1996-06-26T23:59:59.000Z

320

Measurements of electromagnetic properties of LCT (Large Coil Task) coils in IFSMTF (International Fusion Superconducting Magnet Test Facility)  

SciTech Connect

Participants in the international Large Coil Task (LCT) have designed, built, and tested six different toroidal field coils. Each coil has a 2.5- by 3.5-m, D-shaped bore and a current between 10 and 18 kA and is designed to demonstrate stable operation at 8 T, with a superimposed averaged pulsed field of 0.14 T in 1.0 s and simulated nuclear heating. Testing of the full six-coil toroidal array began early in 1986 and was successfully completed on September 3, 1987, in the International Fusion Superconducting Magnet Test Facility (IFSMTF) at Oak Ridge National Laboratory (ORNL). This paper summarizes electromagnetic properties of LCT coils measured in different modes of energization and fast dump. Effects of mutual coupling and induced eddy currents are analyzed and discussed. Measurements of the ac loss caused by the superimposed pulsed fields are summarized. Finally, the interpretation of the test results and their relevance to practical fusion are presented. 11 refs., 10 figs., 4 tab.

Shen, S.S.; Baylor, L.R.; Dresner, L.; Fehling, D.T.; Lubell, M.S.; Lue, J.W.; Luton, J.N.; McManamy, T.J.; Wilson, C.T.; Wintenberg, R.E.

1987-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "magnetic confinement fusion" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


321

Cost Accounting System for fusion studies  

SciTech Connect

A Cost Accounting System that is applicable to all magnetic fusion reactor design studies has been developed. This system provides: (1) definitions of the elements of cost and methods for the combination of these elements to form a cost estimate; (2) a Code of Accounts that uses a functional arrangement for identification of the plant components; and (3) definitions and methods to analyze actual cost data so that the data can be directly reported into this Cost Accounting System. The purpose of the Cost Accounting System is to provide the structure for the development of a fusion cost data base and for the development of validated cost estimating procedures. This system has been developed through use at the Fusion Engineering Design Center (FEDC) and has been applied to different confinement concepts (tokamaks and tandem mirrors) and to different types of projects (experimental devices and commercial power plants). The use of this Cost Accounting System by all magnetic fusion projects will promote the development of a common cost data base, allow the direct comparison of cost estimates, and ultimately establish the cost credibility of the program.

Hamilton, W.R.; Keeton, D.C.; Thomson, S.L.

1985-12-01T23:59:59.000Z

322

Analysis of Reccurent Patterns in Toroidal Magnetic Fields  

SciTech Connect

In the development of magnetic confinement fusion which will be a future source for low cost power, physicists must be able to analyze the magnetic field that confines the burning plasma. While the magnetic field can be described as a series of vectors, traditional techniques for analyzing the field s topology can not be used because of its homoclinic nature. In this paper we describe a technique developed as a collaboration between physicists and computer scientists that determines the topology of a toroidal magnetic field using fieldlines with near minimal lengths. More specifically, we analyze the Poincare map of the sampled fieldlines in a Poincare section including identifying critical points and other topological features of interest to physicists. The technique has been deployed into an interactive parallel visualization tool which physicists are using to gain new insight into simulations of magnetically confined buring plasmas.

Sanderson, Allen [University of Utah; Pugmire, Dave [ORNL

2010-11-01T23:59:59.000Z

323

The Spheromak Path to Fusion  

Science Journals Connector (OSTI)

Options for a spheromak fusion-energy reactor are described and provide ... configuration offers. However, the ability of the spheromak to confine plasma energy has not yet ... . These are being studied in the Su...

K. I. Thomassen; E. B. Hooper; D. D. Ryutov

1998-09-01T23:59:59.000Z

324

Fusion neutron generation computations in a stellarator-mirror hybrid with neutral beam injection  

SciTech Connect

In the paper [Moiseenko V.E., Noack K., Agren O. 'Stellarator-mirror based fusion driven fission reactor' J Fusion Energy 29 (2010) 65.], a version of a fusion driven system (FDS), i.e. a sub-critical fast fission assembly with a fusion plasma neutron source, is proposed. The plasma part of the reactor is based on a stellarator with a small mirror part. Hot ions with high perpendicular energy are assumed to be trapped in the magnetic mirror part. The stellarator part which connects to the mirror part and provides confinement for the bulk (deuterium) plasma. In the magnetic well of the mirror part, fusion reactions occur from collisions between a of hot ion component (tritium) with cold background plasma ions. RF heating is one option to heat the tritium. A more conventional method to sustain the hot ions is neutral beam injection (NBI), which is here studied numerically for the above-mentioned hybrid scheme. For these studies, a new kinetic code, KNBIM, has been developed. The code takes into account Coulomb collisions between the hot ions and the background plasma. The geometry of the confining magnetic field is arbitrary for the code. It is accounted for via a numerical bounce averaging procedure. Along with the kinetic calculations the neutron generation intensity and its spatial distribution are computed.

Moiseenko, V. E.; Agren, O. [Institute of Plasma Physics, National Science Center 'Kharkiv Institute of Physics and Technology', Akademichna St. 1, 61108 Kharkiv (Ukraine); Uppsala University, Angstroem Laboratory, Division of Electricity, Box 534, SE-7512 Uppsala (Sweden)

2012-06-19T23:59:59.000Z

325

Field-induced confined states in graphene  

SciTech Connect

We report an approach to confine the carriers in single-layer graphene, which leads to quantum devices with field-induced quantum confinement. We demonstrated that the Coulomb-blockade effect evolves under a uniform magnetic field perpendicular to the graphene device. Our experimental results show that field-induced quantum dots are realized in graphene, and a quantum confinement-deconfinement transition is switched by the magnetic field.

Moriyama, Satoshi, E-mail: MORIYAMA.Satoshi@nims.go.jp [International Center for Materials Nanoarchitectonics (WPI-MANA), National Institute for Materials Science (NIMS), 1-1 Namiki, Tsukuba, Ibaraki 305-0044 (Japan); Morita, Yoshifumi [Faculty of Engineering, Gunma University, Kiryu, Gunma 376-8515 (Japan); Watanabe, Eiichiro; Tsuya, Daiju [Nanotechnology Innovation Station, NIMS, 1-2-1 Sengen, Tsukuba, Ibaraki 305-0047 (Japan)

2014-02-03T23:59:59.000Z

326

Compendium of computer codes for the researcher in magnetic fusion energy  

SciTech Connect

This is a compendium of computer codes, which are available to the fusion researcher. It is intended to be a document that permits a quick evaluation of the tools available to the experimenter who wants to both analyze his data, and compare the results of his analysis with the predictions of available theories. This document will be updated frequently to maintain its usefulness. I would appreciate receiving further information about codes not included here from anyone who has used them. The information required includes a brief description of the code (including any special features), a bibliography of the documentation available for the code and/or the underlying physics, a list of people to contact for help in running the code, instructions on how to access the code, and a description of the output from the code. Wherever possible, the code contacts should include people from each of the fusion facilities so that the novice can talk to someone ''down the hall'' when he first tries to use a code. I would also appreciate any comments about possible additions and improvements in the index. I encourage any additional criticism of this document. 137 refs.

Porter, G.D. (ed.)

1989-03-10T23:59:59.000Z

327

PLT scaling laws for thermonuclear fusion power multiplication  

SciTech Connect

While present experiments are evaluated on the basis of confinement time, it is the fusion power multiplication factor, Q, and the fusion power which will be the parameters that measure the performance of ignition experiments and fusion reactors. We have determined the relationship of Q to tau/sub E/ and the Lawson number, n tau/sub e/, for ohmically heated plasmas from the Princeton Large Tokamak (PLT). Q, tau/sub E/, and n tau/sub E/ all increase with density at low densities. Above anti n/sub e/ approx. = 4 x 10/sup 13/ cm/sup -3/, tau/sub Ee/ approx. = 30 msec, or anti n/sub e/ tau/sub Ee/ approx. = 1.5 x 10/sup 12/ cm/sup -3/s, Q saturates. Q scaling has also been obtained on PLT as a function of toroidal magnetic field, plasma current, and auxiliary heating power.

Grisham, L.R.; Strachan, J.D.

1982-11-01T23:59:59.000Z

328

The path to fusion power  

Science Journals Connector (OSTI)

...proportional to P 2. The energy confinement time...determines the energy gain of the fusion...needed to keep the electric current in the plasma...in France, once planning permission-which...The much higher energy fusion neutrons...essentially the same distributions of energies as those...

2007-01-01T23:59:59.000Z

329

Fusion Lecture Summary Eugene S. Evans  

E-Print Network (OSTI)

March 31, 2010 2 / 15 #12;National Ignition Facility (NIF) location: Lawrence Livermore National. Evans (2010) Fusion Lecture Summary March 31, 2010 1 / 15 #12;Outline 1 Overview of NIF Specifications Timeline Goals 2 Inertial Confinement Fusion (ICF) 3 Science at NIF 4 Fusion and the Future Laser Inertial

Budker, Dmitry

330

A Compact Nuclear Fusion Reactor for Space Flights  

SciTech Connect

A small-scale nuclear fusion reactor is suggested based on the concepts of plasma confinement (with a high pressure gas) which have been patented by the author. The reactor considered can be used as a power setup in space flights. Among the advantages of this reactor is the use of a D3He fuel mixture which at burning gives main reactor products -- charged particles. The energy balance considerably improves, as synchrotron radiation turn out 'captured' in the plasma volume, and dangerous, in the case of classical magnetic confinement, instabilities in the direct current magnetic field configuration proposed do not exist. As a result, the reactor sizes are quite suitable (of the order of several meters). A possibility of making reactive thrust due to employment of ejection of multiply charged ions formed at injection of pellets from some adequate substance into the hot plasma center is considered.

Nastoyashchiy, Anatoly F. [SRC Troitsk Institute for Innovation and Fusion Research, TRINITI 142190 Troitsk Moscow Reg. (Russian Federation)

2006-05-02T23:59:59.000Z

331

Half a century of fusion research towards ITER  

Science Journals Connector (OSTI)

A review is given on plasma physics and controlled thermonuclear fusion research since the late 1950s and up to the present day. Special emphasis is given to various proposed magnetic plasma confinement systems, as well as to the research aiming at the planned International Thermonuclear Experimental Reactor (ITER) project. The latter is based on the tokamak field geometry of a strong toroidal magnetic field, combined with an inductively imposed toroidal plasma current. Experimental and theoretical research has been conducted on the fundamental problems of confinement, equilibrium, stability, plasma transport and plasma heating. During this development two milestones have been passed on the way to ITER, namely the removed threat by Bohm diffusion at the end of the 1960s, and the discovery of the High Mode at the beginning of the 1980s. Finally, some future perspectives are shortly given on this line of research.

Bo Lehnert

2013-01-01T23:59:59.000Z

332

Tritium production potential of beam research and magnetic fusion program technologies  

SciTech Connect

Regular replenishment of tritium in the nuclear weapons stockpile is essential to maintain our nuclear deterrent. Nuclear reactor facilities presently used for the production of tritium are aging, and their operation is being curtailed awaiting the repairs and upgrades needed to meet modern standards of safety and environment. To provide improved capability in the future, DOE plans to construct a new production reactor. Alternatives to nuclear reactor methods for the production of tritium, mainly electrically-driven accelerator or fusion systems, have been proposed many times in the past. Given the critical national security implications of maintaining adequate tritium production facilities, it is clearly worthwhile for political decision-makers to have a clear and accurate picture of the technical options that could be made available at various points in the future. The goal of this white paper is to summarize available technical information on a set of non-nuclear-reactor options for tritium production with a minimum of advocacy for any one system of implicit assumptions about politically desirable attributes. Indeed, these various options differ considerably in aspects such as the maturity of the technology, the development cost and timescales required, and the capital and operating costs of a typical ''optimized'' facility.

Lee, J.D. (comp.)

1989-03-01T23:59:59.000Z

333

Ion Heating in the Field-Reversed Configuration by Rotating Magnetic Fields near the Ion-Cyclotron Resonance  

Science Journals Connector (OSTI)

The trajectories of ions confined in a field-reversed configuration (FRC) equilibrium magnetic geometry and heated with a small-amplitude, odd-parity rotating magnetic field (RMF) have been studied with a Hamiltonian computer code. When the RMF frequency is in the ion-cyclotron range, explosive heating occurs. Higher-energy ions are found to have betatron-type orbits, preferentially localized near the FRC's midplane. These results are relevant to a compact magnetic-fusion-reactor design.

Samuel A. Cohen and Alan H. Glasser

2000-12-11T23:59:59.000Z

334

STUDY OF THE THREE-DIMENSIONAL CORONAL MAGNETIC FIELD OF ACTIVE REGION 11117 AROUND THE TIME OF A CONFINED FLARE USING A DATA-DRIVEN CESE-MHD MODEL  

SciTech Connect

We apply a data-driven magnetohydrodynamics (MHD) model to investigate the three-dimensional (3D) magnetic field of NOAA active region (AR) 11117 around the time of a C-class confined flare that occurred on 2010 October 25. The MHD model, based on the spacetime conservation-element and solution-element scheme, is designed to focus on the magnetic field evolution and to consider a simplified solar atomsphere with finite plasma {beta}. Magnetic vector-field data derived from the observations at the photosphere is inputted directly to constrain the model. Assuming that the dynamic evolution of the coronal magnetic field can be approximated by successive equilibria, we solve a time sequence of MHD equilibria based on a set of vector magnetograms for AR 11117 taken by the Helioseismic and Magnetic Imager on board the Solar Dynamic Observatory around the time of the flare. The model qualitatively reproduces the basic structures of the 3D magnetic field, as supported by the visual similarity between the field lines and the coronal loops observed by the Atmospheric Imaging Assembly, which shows that the coronal field can indeed be well characterized by the MHD equilibrium in most cases. The magnetic configuration changes very little during the studied time interval of 2 hr. A topological analysis reveals that the small flare is correlated with a bald patch (BP, where the magnetic field is tangent to the photosphere), suggesting that the energy release of the flare can be understood by magnetic reconnection associated with the BP separatrices. The total magnetic flux and energy keep increasing slightly in spite of the flare, while the computed magnetic free energy drops during the flare by {approx}10{sup 30} erg, which seems to be adequate in providing the energy budget of a minor C-class confined flare.

Jiang Chaowei; Feng Xueshang [SIGMA Weather Group, State Key Laboratory for Space Weather, Center for Space Science and Applied Research, Chinese Academy of Sciences, Beijing 100190 (China); Wu, S. T.; Hu Qiang, E-mail: cwjiang@spaceweather.ac.cn, E-mail: fengx@spaceweather.ac.cn, E-mail: wus@uah.edu, E-mail: qh0001@uah.edu [Center for Space Plasma and Aeronomic Research, University of Alabama in Huntsville, Huntsville, AL 35899 (United States)

2012-11-10T23:59:59.000Z

335

Compatibility between high energy particle confinement and magnetohydrodynamic stability in the inward-shifted plasmas of the Large Helical Device  

Science Journals Connector (OSTI)

The experimentally optimized magnetic field configuration of the Large Helical Device [A. Iiyoshi et al. Nucl. Fusion39 1245 (1999)] where the magnetic axis is shifted inward by 15 cm from the early theoretical prediction reveals 50% better global energy confinement than the prediction of the scaling law. This configuration has been investigated further from the viewpoints of high energy particle confinement and magnetohydrodynamic(MHD) stability. The confinement of high energy ions is improved as expected. The minority heating of ion cyclotron range of frequency was successful and the heating efficiency was improved by the inward shift. The confinement of passing particles by neutral beam injection was also improved under low magnetic field strength and there could be obtained an almost steady high beta discharge up to 3% in volume average. This was a surprising result because the observed pressure gradient exceeded the Mercier unstable limit. The observed MHD activities became as high as beta but they did not grow enough to deteriorate the confinement of high energy ions or the performance of the bulk plasma which was still 50% better than the scaling. According to these favorable results better performance would be expected by increasing the heating power because the neoclassical transport can also be improved there.

O. Kaneko; A. Komori; H. Yamada; N. Ohyabu; K. Kawahata; Y. Nakamura; K. Ida; S. Murakami; T. Mutoh; S. Sakakibara; S. Masuzaki; N. Ashikawa; M. Emoto; H. Funaba; M. Goto; H. Idei; K. Ikeda; N. Inoue; M. Isobe; K. Khlopenkov; S. Kubo; R. Kumazawa; T. Minami; J. Miyazawa; T. Morisaki; S. Morita; S. Muto; Y. Nagayama; N. Nakajima; H. Nakanishi; K. Narihara; K. Nishimura; N. Noda; T. Notake; T. Kobuchi; Y. Liang; S. Ohdachi; Y. Oka; M. Osakabe; T. Ozaki; B. J. Peterson; A. Sagara; K. Saito; R. Sakamoto; M. Sasao; M. Sato; T. Seki; T. Shimozuma; M. Shoji; H. Suzuki; Y. Takeiri; N. Tamura; K. Tanaka; K. Toi; T. Tokuzawa; Y. Torii; K. Tsumori; I. Yamada; S. Yamamoto; M. Yokoyama; Y. Yoshimura; M. Yoshinuma; K. Y. Watanabe; T. Watari; Y. Xu; K. Itoh; K. Matsuoka; K. Ohkubo; I. Ohtake; T. Satow; S. Sudo; K. Yamazaki; Y. Hamada; O. Motojima; M. Fujiwara

2002-01-01T23:59:59.000Z

336

Impulsive energy release and non-thermal emission in a confined M4.0 flare triggered by rapidly evolving magnetic structures  

E-Print Network (OSTI)

We present observations of a confined M4.0 flare from NOAA 11302 on 2011 September 26. Observations at high temporal, spatial, and spectral resolution from Solar Dynamics Observatory, Reuven Ramaty High Energy Solar Spectroscopic Imager, and Nobeyama Radioheliograph enabled us to explore the possible triggering and energy release processes of this flare despite its very impulsive behavior and compact morphology. The flare light curves exhibit an abrupt rise of non-thermal emission with co-temporal hard X-ray (HXR) and microwave (MW) bursts that peaked instantly without any precursor emission. This stage was associated with HXR emission up to 200 keV that followed a power law with photon spectral index ($\\delta$) $\\sim$3. Another non-thermal peak, observed 32 s later, was more pronounced in the MW flux than the HXR profiles. Dual peaked structure in the MW and HXR light curves suggest a two-step magnetic reconnection process. Extreme ultraviolet (EUV) images exhibit a sequential evolution of the inner and oute...

Kushwaha, Upendra; cho, Kyung-suk; Veronig, Astrid; Tiwari, Sanjiv Kumar; Mathew, S K

2014-01-01T23:59:59.000Z

337

Thermonuclear fusion in dense stars: Electron screening, conductive cooling, and magnetic field effects  

E-Print Network (OSTI)

We study the plasma correlation effects on nonresonant thermonuclear reactions of carbon and oxygen in the interiors of white dwarfs and liquid envelopes of neutron stars. We examine the effects of electron screening on thermodynamic enhancement of thermonuclear reactions in dense plasmas beyond the linear mixing rule. Using these improved enhancement factors, we calculate carbon and oxygen ignition curves in white dwarfs and neutron stars. The energy balance and ignition conditions in neutron star envelopes are evaluated, taking their detailed thermal structure into account. The result is compared to the simplified "one-zone model," which is routinely used in the literature. We also consider the effect of strong magnetic fields on the ignition curves in the ocean of magnetars.

Potekhin, A Y

2012-01-01T23:59:59.000Z

338

Handling and archiving of magnetic fusion data at DIII-D  

SciTech Connect

Recent modifications to the computer network at DIII-D enhance the collection and distribution of newly acquired and archived experimental data. Linked clients and servers route new data from diagnostic computers to centralized mass storage and distribute data on demand to local and remote workstations and computers. Capacity for data handling exceeds the upper limit of DIII-D Tokamak data production of about 4 GBytes per day. Network users have fast access to new data stored on line. An interactive program handles requests for restoration of data archived off line. Disk management procedures retain selected data on line in preference to other data. Redundancy of all components on the archiving path from the network to magnetic media has prevented loss of data. Older data are rearchived as dictated by limited media life.

VanderLaan, J.F.; Miller, S.; McHarg, B.B. Jr.; Henline, P.A.

1995-10-01T23:59:59.000Z

339

DOE Handbook: Supplementary guidance and design experience for the fusion safety standards DOE-STD-6002-96 and DOE-STD-6003-96  

SciTech Connect

Two standards have been developed that pertain to the safety of fusion facilities. These are DOE- STD-6002-96, Safety of Magnetic Fusion Facilities: Requirements, and DOE-STD-6003-96, Safety of Magnetic Fusion Facilities: Guidance. The first of these standards identifies requirements that subscribers to that standard must meet to achieve safety in fusion facilities. The second standard contains guidance to assist in meeting the requirements identified in the first This handbook provides additional documentation on good operations and design practices as well as lessons learned from the experiences of designers and operators of previous fusion facilities and related systems. It is intended to capture the experience gained in the various fields and pass it on to designers of future fusion facilities as a means of enhancing success and safety. The sections of this document are presented according to the physical location of the major systems of a fusion facility, beginning with the vacuum vessel and proceeding to those systems and components outside the vacuum vessel (the "Ex-vessel Systems"). The last section describes administrative procedures that cannot be localized to specific components. It has been tacitly assumed that the general structure of the fusion facilities addressed is that of a tokamak though the same principles would apply to other magnetic confinement options.

none,

1999-01-01T23:59:59.000Z

340

Inertial Confinement Fusion with Light Ion Beams  

Science Journals Connector (OSTI)

...plasma can be formed without significant contribution of the ion thermal velocity to the beam divergence. The large ionization energy...3. P. L. Dreike, C. Eichenberger, S. Humphries, R. Sudan, J. Appi. Phys. 47, 85 (1986). 4. J. D. Lindi and...

J. PACE VANDEVENDER; DONALD L. COOK

1986-05-16T23:59:59.000Z

Note: This page contains sample records for the topic "magnetic confinement fusion" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


341

Weapons Activities/ Inertial Confinement Fusion Ignition  

E-Print Network (OSTI)

a safe, secure, and reliable nuclear weapons stockpile without underground testing. Science-based weapons and certify the stockpile without nuclear testing. The National Ignition Facility (NIF) extends HEDP under extreme conditions that approach the high energy density (HED) environments found in a nuclear

342

Weapons Activities/ Inertial Confinement Fusion Ignition  

E-Print Network (OSTI)

, and reliability of the Nation's nuclear weapons without nuclear testing. The program provides this capability models that are used to assess and certify the stockpile without nuclear testing. The National Ignition that approach the high-energy density (HED) environments found in a nuclear explosion. Virtually all

343

Inertial Confinement Fusion | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

advanced science and technology portfolio, the Office of ICF is working to produce thermonuclear burn conditions in the laboratory, to develop laboratory capabilities that will...

344

FES Science Network Requirements - Report of the Fusion Energy Sciences Network Requirements Workshop Conducted March 13 and 14, 2008  

E-Print Network (OSTI)

the Office of Science started as the Magnetic Fusion EnergyRequirements and Science Process All U.S. magnetic fusionMagnetic Fusion Energy Program 11 MIT Plasma Science &

Dart, Eli

2008-01-01T23:59:59.000Z

345

Experimental Fusion Research | Princeton Plasma Physics Lab  

NLE Websites -- All DOE Office Websites (Extended Search)

confinement. The shiny metal keeps the particles from re-entering the plasma as a cold gas, retains impurities that can cool the plasma and halt fusion reactions, and...

346

INERTIAL FUSION DRIVEN BY INTENSE HEAVY-ION BEAMS  

E-Print Network (OSTI)

Tritium can be bred in a fusion reactor by capturing fusionchamber. Whereas magnetic-fusion reactors typically combineProjected MFE reactors have a toroidal fusion-power core

Sharp, W. M.

2011-01-01T23:59:59.000Z

347

Alternative pathways to fusion energy (focus on Department of Energy  

E-Print Network (OSTI)

Alternative pathways to fusion energy (focus on Department of Energy Innovative Confinement for a restructured fusion energy science program [5] 1996 | FESAC: Opportunities in Alternative Confinement Concepts, suggests program for Innovative Concepts [1] 1995 | OTA TPX and the Alternates [2] 1995 | PCAST (given flat

348

Critical Heat Flux -CHF in Liquid Metal in Presence of a Magnetic Field with Particular Reference to Fusion Reactor Project  

Science Journals Connector (OSTI)

Knowledge of the critical heat flux q??crit is a cornerstone of reactor design fission, but as will demonstrate also in fusion reactors. This quantity cannot be deduced directly,...

F. J. Arias

2010-04-01T23:59:59.000Z

349

SciDAC Fusiongrid Project--A National Collaboratory to Advance the Science of High Temperature Plasma Physics for Magnetic Fusion  

SciTech Connect

This report summarizes the work of the National Fusion Collaboratory (NFC) Project funded by the United States Department of Energy (DOE) under the Scientific Discovery through Advanced Computing Program (SciDAC) to develop a persistent infrastructure to enable scientific collaboration for magnetic fusion research. A five year project that was initiated in 2001, it built on the past collaborative work performed within the U.S. fusion community and added the component of computer science research done with the USDOE Office of Science, Office of Advanced Scientific Computer Research. The project was a collaboration itself uniting fusion scientists from General Atomics, MIT, and PPPL and computer scientists from ANL, LBNL, Princeton University, and the University of Utah to form a coordinated team. The group leveraged existing computer science technology where possible and extended or created new capabilities where required. Developing a reliable energy system that is economically and environmentally sustainable is the long-term goal of Fusion Energy Science (FES) research. In the U.S., FES experimental research is centered at three large facilities with a replacement value of over $1B. As these experiments have increased in size and complexity, there has been a concurrent growth in the number and importance of collaborations among large groups at the experimental sites and smaller groups located nationwide. Teaming with the experimental community is a theoretical and simulation community whose efforts range from applied analysis of experimental data to fundamental theory (e.g., realistic nonlinear 3D plasma models) that run on massively parallel computers. Looking toward the future, the large-scale experiments needed for FES research are staffed by correspondingly large, globally dispersed teams. The fusion program will be increasingly oriented toward the International Thermonuclear Experimental Reactor (ITER) where even now, a decade before operation begins, a large portion of national program efforts are organized around coordinated efforts to develop promising operational scenarios. Substantial efforts to develop integrated plasma modeling codes are also underway in the U.S., Europe and Japan. As a result of the highly collaborative nature of FES research, the community is facing new and unique challenges. While FES has a significant track record for developing and exploiting remote collaborations, with such large investments at stake, there is a clear need to improve the integration and reach of available tools. The NFC Project was initiated to address these challenges by creating and deploying collaborative software tools. The original objective of the NFC project was to develop and deploy a national FES 'Grid' (FusionGrid) that would be a system for secure sharing of computation, visualization, and data resources over the Internet. The goal of FusionGrid was to allow scientists at remote sites to participate as fully in experiments and computational activities as if they were working on site thereby creating a unified virtual organization of the geographically dispersed U.S. fusion community. The vision for FusionGrid was that experimental and simulation data, computer codes, analysis routines, visualization tools, and remote collaboration tools are to be thought of as network services. In this model, an application service provider (ASP) provides and maintains software resources as well as the necessary hardware resources. The project would create a robust, user-friendly collaborative software environment and make it available to the US FES community. This Grid's resources would be protected by a shared security infrastructure including strong authentication to identify users and authorization to allow stakeholders to control their own resources. In this environment, access to services is stressed rather than data or software portability.

SCHISSEL, D.P.; ABLA, G.; BURRUSS, J.R.; FEIBUSH, E.; FREDIAN, T.W.; GOODE, M.M.; GREENWALD, M.J.; KEAHEY, K.; LEGGETT, T.; LI, K.; McCUNE, D.C.; PAPKA, M.E.; RANDERSON, L.; SANDERSON, A.; STILLERMAN, J.; THOMPSON, M.R.; URAM, T.; WALLACE, G.

2006-08-31T23:59:59.000Z

350

Inelastic neutron scattering from confined molecular oxygen  

Science Journals Connector (OSTI)

Inelastic neutron-scattering measurements were carried out on condensed bulk and confined molecular oxygen. The phase transitions of the oxygen confined in cylindrical pores with diameter of ?94? are suppressed below their bulk temperatures or in the case of the lowest-temperature transition to the ? phase are suppressed entirely. This last observation is possibly due to the low latent heat of transition for this transition. Both elastic and inelastic neutron-scattering data indicate a mixing of oxygen crystal phases upon confinement. Magnetic ordering fluctuations in the ? phase are found to have similar energy-dependent profiles for confined and bulk excitations showing that the magnetic correlation function decay is unaffected by the finite crystal size in confinement.

Duncan Kilburn; Paul E. Sokol; Craig M. Brown

2008-12-29T23:59:59.000Z

351

Fusion Reactor Plasmas with Polarized Nuclei  

Science Journals Connector (OSTI)

Nuclear fusion rates can be enhanced or suppressed by polarization of the reacting nuclei. In a magnetic fusion reactor, the depolarization time is estimated to be longer than the reaction time.

R. M. Kulsrud; H. P. Furth; E. J. Valeo; M. Goldhaber

1982-10-25T23:59:59.000Z

352

Splenogonadal Fusion  

Science Journals Connector (OSTI)

Splenogonadal fusion is a very rare congenital malformation. It is characterized by fusion of the spleen and gonad. The first case of splenogonadal fusion was described by Bostroem in 1883. There are two types: c...

Ahmed H. Al-Salem

2014-01-01T23:59:59.000Z

353

Type Fusion  

Science Journals Connector (OSTI)

Fusion is an indispensable tool in the arsenal ... Less well-known, but equally valuable is type fusion, which states conditions for fusing an application ... algebra. We provide a novel proof of type fusion base...

Ralf Hinze

2011-01-01T23:59:59.000Z

354

MIT Plasma Science & Fusion Center: research>alcator>  

NLE Websites -- All DOE Office Websites (Extended Search)

Physics Research Physics Research High-Energy- Density Physics Waves & Beams Technology & Engineering Useful Links earl marmar head of alcator reviewing data Dr. Earl Marmar, leader of the Alcator Project, studies C-Mod data. Today, we are closer than ever to realizing the dream of harnessing the nuclear process that powers our sun. This stellar process, called fusion, produces minimal waste and offers the hope of an almost limitless supply of safe, dependable energy. Among fusion research groups, MIT's Alcator C-Mod project is unique in its dedication to compact size and high performance. It is the world's highest magnetic field tokamak plasma confinement experiment. As a result, Alcator experiments have performed at levels rivaling the largest fusion experiments in the world.

355

Views on inertial fusion energy development  

Science Journals Connector (OSTI)

A memorial lecture reviews the inertial fusion developments. The issues of the world energy consumption the atmospheric concentration of carbon dioxide and the necessity of an advanced nuclear fission technology are considered. A real world wide collaboration is very important for the inertial confinement fusion program. (AIP)

S. Nakai

1994-01-01T23:59:59.000Z

356

Accelerator Fusion Research Division 1991 summary of activities  

SciTech Connect

This report discusses research projects in the following areas: Heavy-ion fusion accelerator research; magnetic fusion energy; advanced light source; center for x-ray optics; exploratory studies; superconducting magnets; and bevalac operations.

Not Available

1991-12-01T23:59:59.000Z

357

Accelerator & Fusion Research Division 1991 summary of activities  

SciTech Connect

This report discusses research projects in the following areas: Heavy-ion fusion accelerator research; magnetic fusion energy; advanced light source; center for x-ray optics; exploratory studies; superconducting magnets; and bevalac operations.

Not Available

1991-12-01T23:59:59.000Z

358

Accelerator and fusion research division. 1992 Summary of activities  

SciTech Connect

This report contains brief discussions on research topics in the following area: Heavy-Ion Fusion Accelerator Research; Magnetic Fusion Energy; Advanced Light Source; Center for Beam Physics; Superconducting Magnets; and Bevalac Operations.

Not Available

1992-12-01T23:59:59.000Z

359

Finding Fusion  

Science Journals Connector (OSTI)

Finding Fusion ... Study of these reactions will advance understanding of the workings of stars and giant planets, fusion energy, and nuclear weapon stockpiles. ...

JYLLIAN KEMSLEY

2012-09-10T23:59:59.000Z

360

Parametic Study of the current limit within a single driver-scale transport beam line of an induction Linac for Heavy Ion Fusion  

E-Print Network (OSTI)

Physics of Magnetic Fusion Reactors, Rev. of Modern Physicsheavy ion beam driven fusion reactor study, Technical Reporta toroidally shaped fusion reactor (tokamak) such as shown

Prost, Lionel Robert

2007-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "magnetic confinement fusion" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


361

Score Fusion and Decision Fusion  

Science Journals Connector (OSTI)

Score fusion is a paradigm, which calculates similarity scores ... then combines the two scores according to a fusion formula, e.g., the overall score ... mean of the two modality scores. Decision fusion is a par...

2009-01-01T23:59:59.000Z

362

MIT Plasma Science & Fusion Center: research, alcator, publications & news,  

NLE Websites -- All DOE Office Websites (Extended Search)

1st Annual Meeting of the APS Division of Plasma Physics, Atlanta, 2009 1st Annual Meeting of the APS Division of Plasma Physics, Atlanta, 2009 Invited Orals I. Cziegler Structures and Velocities of the Edge Turbulence in Alcator C-Mod M. Greenwald Verification and Validation for Magnetic Fusion: Moving Toward Predictive Capability J. Hughes Edge Pedestal and Confinement Regulation on Alcator C-Mod L. Lin Comparison of Experimental Measurements and Gyrokinetic Turbulent Electron Transport Models in Alcator C-Mod Plasmas M. Porkolab Taming Magnetically Confined Plasmas with RF Waves: a Historical Perspective S. Shiraiwa Plasma Wave Simulation Based on a Versatile FEM Solver on Alcator C-Mod D. Whyte Runaway Electron Transport & Disruption Mitigation Optimization on Alcator C-Mod Contributed Orals B. Bose Studies of Filament Formation during Lithium Pellet Injection in Alcator C-Mod

363

Scientific and Computational Challenges of the Fusion Simulation Program (FSP)  

SciTech Connect

This paper highlights the scientific and computational challenges facing the Fusion Simulation Program (FSP) a major national initiative in the United States with the primary objective being to enable scientific discovery of important new plasma phenomena with associated understanding that emerges only upon integration. This requires developing a predictive integrated simulation capability for magnetically-confined fusion plasmas that are properly validated against experiments in regimes relevant for producing practical fusion energy. It is expected to provide a suite of advanced modeling tools for reliably predicting fusion device behavior with comprehensive and targeted science-based simulations of nonlinearly-coupled phenomena in the core plasma, edge plasma, and wall region on time and space scales required for fusion energy production. As such, it will strive to embody the most current theoretical and experimental understanding of magnetic fusion plasmas and to provide a living framework for the simulation of such plasmas as the associated physics understanding continues to advance over the next several decades. Substantive progress on answering the outstanding scientific questions in the field will drive the FSP toward its ultimate goal of developing the ability to predict the behavior of plasma discharges in toroidal magnetic fusion devices with high physics fidelity on all relevant time and space scales. From a computational perspective, this will demand computing resources in the petascale range and beyond together with the associated multi-core algorithmic formulation needed to address burning plasma issues relevant to ITER - a multibillion dollar collaborative experiment involving seven international partners representing over half the world's population. Even more powerful exascale platforms will be needed to meet the future challenges of designing a demonstration fusion reactor (DEMO). Analogous to other major applied physics modeling projects (e.g., Climate Modeling), the FSP will need to develop software in close collaboration with computers scientists and applied mathematicians and validated against experimental data from tokamaks around the world. Specific examples of expected advances needed to enable such a comprehensive integrated modeling capability and possible "co-design" approaches will be discussed. __________________________________________________

William M. Tang

2011-02-09T23:59:59.000Z

364

The path to fusion power  

Science Journals Connector (OSTI)

...cost-effective neutron and plasma source for a component...at Culham and NSTX at Princeton, are beginning to reach...that requires no driven plasma current to confine the...achieved near fusion plasma conditions at very modest...Experiment (NSTX) at Princeton in the USA also operates...

2010-01-01T23:59:59.000Z

365

Quark confinement mechanism for baryons  

E-Print Network (OSTI)

The confinement mechanism proposed earlier and then successfully applied to meson spectroscopy by the author is extended over baryons. For this aim the wave functions of baryons are built as tensorial products of those corresponding to the 2-body problem underlying the confinement mechanism of two quarks. This allows one to obtain the Hamiltonian of the quark interactions in a baryon and, accordingly, the possible energy spectrum of the latter. Also one may construct the electric and magnetic form factors of baryon in a natural way which entails the expressions for the root-mean-square radius and anomalous magnetic moment. To ullustrate the formalism in the given Chapter for the sake of simplicity only symmetrical baryons (i.e., composed from three quarks of the same flavours) $\\Delta^{++}$, $\\Delta^{-}$, $\\Omega^-$ are considered. For them the masses, the root-mean-square radii and anomalous magnetic moments are expressed in an explicit analytical form through the parameters of the confining SU(3)-gluonic field among quarks and that enables one to get a number of numerical estimates for the mentioned parameters from experimental data. We also discuss chiral limit for the baryons under consideration and estimate the purely gluonic contribution to their masses. Further the problem of masses in particle physics is shortly discussed within the framework of the given approach. Finally, a few remarks are made about the so-called Yang-Mills Millennium problem and a possible way for proving it is outlined.

Yu. P. Goncharov

2013-12-14T23:59:59.000Z

366

World's largest laser misses nuclear fusion deadline  

Science Journals Connector (OSTI)

The 192-beam laser in California was an ambitious attempt to pip a magnetic fusion technique to the post but that now looks unlikely

2012-01-01T23:59:59.000Z

367

US ITER - Why Fusion?  

NLE Websites -- All DOE Office Websites (Extended Search)

US Fusion Research Sites US Fusion Research Sites DOE Office of Science: US Fusion Energy Sciences Program Fusion Power Associates General Atomics DIIII-D National Fusion Facility...

368

A Compact Torus Fusion Reactor Utilizing a Continuously Generated Strings of CT's. The CT String Reactor, CTSR.  

SciTech Connect

A fusion reactor is described in which a moving string of mutually repelling compact toruses (alternating helicity, unidirectional Btheta) is generated by repetitive injection using a magnetized coaxial gun driven by continuous gun current with alternating poloidal field. An injected CT relaxes to a minimum magnetic energy equilibrium, moves into a compression cone, and enters a conducting cylinder where the plasma is heated to fusion-producing temperature. The CT then passes into a blanketed region where fusion energy is produced and, on emergence from the fusion region, the CT undergoes controlled expansion in an exit cone where an alternating poloidal field opens the flux surfaces to directly recover the CT magnetic energy as current which is returned to the formation gun. The CT String Reactor (CTSTR) reactor satisfies all the necessary MHD stability requirements and is based on extrapolation of experimentally achieved formation, stability, and plasma confinement. It is supported by extensive 2D, MHD calculations. CTSTR employs minimal external fields supplied by normal conductors, and can produce high fusion power density with uniform wall loading. The geometric simplicity of CTSTR acts to minimize initial and maintenance costs, including periodic replacement of the reactor first wall.

Hartman, C W; Reisman, D B; McLean, H S; Thomas, J

2007-05-30T23:59:59.000Z

369

Characterization of Crude Oil Products Using Data Fusion of Process Raman, Infrared, and Nuclear Magnetic Resonance (NMR) Spectra  

Science Journals Connector (OSTI)

Process Raman, infrared (IR), and nuclear magnetic resonance (NMR) analyses are currently being performed in industrial settings for the monitoring of large scale reactions. These...

Dearing, Thomas I; Thompson, Wesley J; Rechsteiner, Carl E; Marquardt, Brian J

2011-01-01T23:59:59.000Z

370

Status of the US National Inertial Fusion ProgramSNL Z Facility UR/LLE OMEGA  

E-Print Network (OSTI)

Status of the US National Inertial Fusion ProgramSNL Z Facility UR/LLE OMEGA Presentation to the Fusion Energy Sciences Advisory Committee Meeting by: Dr. Allan A. Hauer Director, Office of Inertial Confinement Fusion March 1, 2006 #12;2 The US Inertial Fusion Program has 3 principal components · The first

371

Tail-ion transport and Knudsen layer formation in the presence of magnetic fields  

SciTech Connect

Knudsen layer losses of tail fuel ions could reduce significantly the fusion reactivity of highly compressed cylindrical and spherical targets in inertial confinement fusion (ICF). With the class of magnetized ICF targets in mind, the effect of embedded magnetic fields on Knudsen layer formation is investigated for the first time. The modified energy scaling of ion diffusivity in magnetized hot spots is found to suppress the preferential losses of tail-ions perpendicular to the magnetic field lines to a degree that the tail distribution can be at least partially, if not fully, restored. Two simple threshold conditions are identified leading to the restoration of fusion reactivity in magnetized hot spots. A kinetic equation for tail-ion transport in the presence of a magnetic field is derived, and solutions to the equation are obtained numerically in simulations. Numerical results confirm the validity of the threshold conditions for restored reactivity and identify two different asymptotic regimes of the fusion fuel. While Knudsen layer formation is shown to be suppressed entirely in strongly magnetized cylindrical hot spot cavities, uniformly magnetized spherical cavities demonstrate remnant, albeit reduced, levels of tail-ion depletion.

Schmit, P. F. [Sandia National Laboratories, MS 1186, P.O. Box 5800, Albuquerque, New Mexico 87185-1186 (United States)] [Sandia National Laboratories, MS 1186, P.O. Box 5800, Albuquerque, New Mexico 87185-1186 (United States); Molvig, Kim; Nakhleh, C. W. [Los Alamos National Laboratory, MS B259, P.O. Box 1663, Los Alamos, New Mexico 87545 (United States)] [Los Alamos National Laboratory, MS B259, P.O. Box 1663, Los Alamos, New Mexico 87545 (United States)

2013-11-15T23:59:59.000Z

372

American Fusion News | Princeton Plasma Physics Lab  

NLE Websites -- All DOE Office Websites (Extended Search)

American Fusion News American Fusion News General Atomics (GA) December 4, 2012 The Scorpion's Strategy: "Catch and Subdue" December 4, 2012 Frozen Bullets Tame Unruly Edge Plasmas in Fusion Experiment February 15, 2012 General Atomics (GA) Fusion News: A New Spin on Understanding Plasma Confinement See All Massachusetts Institute of Technology (MIT) April 5, 2013 Applying physics, teamwork to fusion energy science February 22, 2013 A Tour of Plasma Physics in Downtown Cambridge December 4, 2012 Placing Fusion Power on a Pedestal September 21, 2012 MASSACHUSETTS INSTITUTUE OF TECHNOLOGY See All National Ignition Facility February 22, 2013 Summary of Assessment of Prospects for Inertial Fusion Energy February 16, 2012 National Ignition Facility (NIF): Under Pressure: Ramp-Compression Smashes

373

JET and the Prospect for Nuclear Fusion  

Science Journals Connector (OSTI)

This paper describes the Joint European Torus (JET) device which was built as a European collaboration effort, with the aim of testing the scientific feasibility of producing controlled thermonuclear reactions between light nuclei with a net yield of energy. JET is the largest magnetic confinement machine in the world both in physical size and in the magnitude of the plasma current (5 ? 106 Amperes). The machine came into operation in mid-1983 and has followed the first stages of a planned evolution, in which the performance is progressively increased mainly by adding more heating power and which will culminate in eventual operation in a deuterium-tritium mixture. This will permit study of the plasma performance when there is a substantial power input from the ?-particle fusion products. So far operating in deuterium gas with 8 MW of additional heating by neutral beams, a peak ion temperature of 12 keV has been obtained with a corresponding fusion product (density ? confinement time) of 8 ? 1018 m-3 s. If the same conditions were to be achieved in a deuterium-tritium mixture, then the ratio of thermonuclear power output to the heating power input, Q, would be ~ 0.1. It is expected that following further technical improvements to JET, "scientific breakthrough" (namely Q = 1) will be achieved. The next step after JET will be to study a burning or ignited plasma in which no power input is required because energy losses are balanced by ?-particle heating. The requirements for such an experiment will become increasingly clear as more data is obtained from JET. At present it seems likely that a larger apparatus will be needed with a plasma current capability of 12-15 MA. These requirements for the thermonuclear furnace remain broadly consistent with the known technological constraints on an eventual power reactor.

R J Bickerton

1988-01-01T23:59:59.000Z

374

Fusion alpha-particle losses in a high-beta rippled tokamak  

SciTech Connect

In tokamak plasmas, the confinement of energetic ions depends on the magnetic field structure. If the plasma pressure is finite, the equilibrium current (i.e., the Pfirsch-Schlter current and diamagnetic current) flows in the plasma to maintain the magnetohydrodynamic (MHD) equilibrium. These plasma currents generate poloidal and toroidal magnetic field and alter the field structure. Moreover, if we consider the non-axisymmetry of magnetic field structures such as toroidal field (TF) ripples, the non-axisymmetric component of the equilibrium current can alter TF ripples themselves. When the plasma beta becomes high, the changes in the field structure due to the equilibrium current might affect the confinement of energetic ions significantly. We intend to clarify how these currents alter the field structure and affect the confinement of alpha particles in high-beta plasma. The MHD equilibrium is calculated using VMEC and the orbits of fusion alpha particles are followed by using the fully three-dimensional magnetic field orbit-following Monte Carlo code. In relatively low-beta plasma (e.g., the volume-averaged beta value ?2%), the changes in the magnetic field component due to the plasma current negligibly affect the confinement of alpha particles except for the Shafranov shift effect. However, for ?3%, the diamagnetic effect reduces the magnetic field strength and significantly increases alpha-particle losses. In these high-beta cases, the non-axisymmetric field component generated by the equilibrium current also increases these losses, but not as effectively as compared to the diamagnetic effect.

Bunno, M.; Nakamura, Y. [Graduate School of Energy Science, Kyoto University, Gokasho, Uji, Kyoto 611-0011 (Japan)] [Graduate School of Energy Science, Kyoto University, Gokasho, Uji, Kyoto 611-0011 (Japan); Suzuki, Y. [National Institute for Fusion Science, Toki 509-5292 (Japan)] [National Institute for Fusion Science, Toki 509-5292 (Japan); Shinohara, K.; Matsunaga, G. [Japan Atomic Energy Agency, Naka, Ibaraki 311-0193 (Japan)] [Japan Atomic Energy Agency, Naka, Ibaraki 311-0193 (Japan); Tani, K. [Nippon Advanced Technology, Naka, Ibaraki 311-0102 (Japan)] [Nippon Advanced Technology, Naka, Ibaraki 311-0102 (Japan)

2013-08-15T23:59:59.000Z

375

Study of the interplay between magnetic shear and resonances using Hamiltonian models for the magnetic field lines  

SciTech Connect

The issue of magnetic confinement in magnetic fusion devices is addressed within a purely magnetic approach. Using some Hamiltonian models for the magnetic field lines, the dual impact of low magnetic shear is shown in a unified way. Away from resonances, it induces a drastic enhancement of magnetic confinement that favors robust internal transport barriers (ITBs) and stochastic transport reduction. When low shear occurs for values of the winding of the magnetic field lines close to low-order rationals, the amplitude thresholds of the resonant modes that break internal transport barriers by allowing a radial stochastic transport of the magnetic field lines may be quite low. The approach can be applied to assess the robustness versus magnetic perturbations of general (almost) integrable magnetic steady states, including nonaxisymmetric ones such as the important single-helicity steady states. This analysis puts a constraint on the tolerable mode amplitudes compatible with ITBs and may be proposed as a possible explanation of diverse experimental and numerical signatures of their collapses.

Firpo, M.-C. [Laboratoire de Physique des Plasmas, CNRS--Ecole Polytechnique, 91128 Palaiseau Cedex (France); Constantinescu, D. [Department of Applied Mathematics, Association Euratom-MECI, University of Craiova, Craiova 200585 (Romania)

2011-03-15T23:59:59.000Z

376

Nuclear Fusion  

Science Journals Connector (OSTI)

Although not yet developed at the commercial stage, nuclear fusion technology is still being considered as a ... used in nuclear warfare. Since research in nuclear fusion for the production of energy started abou...

Ricardo Guerrero-Lemus; Jos Manuel Martnez-Duart

2013-01-01T23:59:59.000Z

377

Fusion Energy  

Science Journals Connector (OSTI)

Nuclear fusion was discovered in 1932, which is earlier ... than 400 fission power plants are operated to provide base load of electricity worldwide now. In contrast, nuclear fusion was used for a hydrogen bomb i...

Prof. Hiroshi Yamada

2012-01-01T23:59:59.000Z

378

Fusion Inhibitors  

Science Journals Connector (OSTI)

(T-20, Fuzeon) was introduced as the first fusion inhibitor at the beginning of 2003. It works by blocking the cells' viral uptake. Disadvantages of fusion inhibitors are their production difficulties, high...

2008-01-01T23:59:59.000Z

379

Fusion Policy Advisory Committee (FPAC)  

SciTech Connect

This document is the final report of the Fusion Policy Advisory Committee. The report conveys the Committee's views on the matters specified by the Secretary in his charge and subsequent letters to the Committee, and also satisfies the provisions of Section 7 of the Magnetic Fusion Energy Engineering Act of 1980, Public Law 96-386, which require a triennial review of the conduct of the national Magnetic Fusion Energy program. Three sub-Committee's were established to address the large number of topics associated with fusion research and development. One considered magnetic fusion energy, a second considered inertial fusion energy, and the third considered issues common to both. For many reasons, the promise of nuclear fusion as a safe, environmentally benign, and affordable source of energy is bright. At the present state of knowledge, however, it is uncertain that this promise will become reality. Only a vigorous, well planned and well executed program of research and development will yield the needed information. The Committee recommends that the US commit to a plan that will resolve this critically important issue. It also outlines the first steps in a development process that will lead to a fusion Demonstration Power Plant by 2025. The recommended program is aggressive, but we believe the goal is reasonable and attainable. International collaboration at a significant level is an important element in the plan.

Not Available

1990-09-01T23:59:59.000Z

380

Possibility of using active secondary charge-exchange particle diagnostics for measuring the magnetic field direction in the plasma of a magnetic fusion reactor  

Science Journals Connector (OSTI)

An active particle diagnostic method based on the secondary charge exchange of hydrogen atoms of a probing (diagnostic) beam is proposed for local measurements of the magnetic field direction in the plasma of a t...

A. A. Medvedev; V. S. Strelkov

2006-05-01T23:59:59.000Z

Note: This page contains sample records for the topic "magnetic confinement fusion" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


381

Free magnetized knots of parity-violating deconfined matter in heavy-ion collisions  

E-Print Network (OSTI)

We show that the local parity violation in the quark-gluon plasma supports existence of free (meta)stable knots of deconfined hot quark matter stabilized by superstrong magnetic fields. The magnetic field in the knots resembles the spheromak plasma state of the magnetic confinement approach to nuclear fusion. The size of the knot is quantized, being inversely proportional to the chiral conductivity of the quark-gluon plasma. The parity symmetry is broken inside the knot. Particles produced in the decays of the knots have unusual azimuthal distribution and specific flavor content. We argue that these knots may be created in noncentral heavy-ion collisions.

M. N. Chernodub

2010-02-07T23:59:59.000Z

382

Free magnetized knots of parity-violating deconfined matter in heavy-ion collisions  

E-Print Network (OSTI)

We show that the local parity violation in the quark-gluon plasma supports existence of free (meta)stable knots of deconfined hot quark matter stabilized by superstrong magnetic fields. The magnetic field in the knots resembles the spheromak plasma state of the magnetic confinement approach to nuclear fusion. The size of the knot is quantized, being inversely proportional to the chiral conductivity of the quark-gluon plasma. The parity symmetry is broken inside the knot. Particles produced in the decays of the knots have unusual azimuthal distribution and specific flavor content. We argue that these knots may be created in noncentral heavy-ion collisions.

Chernodub, M N

2010-01-01T23:59:59.000Z

383

Status of the US program in magneto-inertial fusion  

Science Journals Connector (OSTI)

A status report of the current U.S. program in magneto-inertial fusion (MIF) conducted by the Office of Fusion Energy Sciences (OFES) of the U.S. Department of Energy is given. Magneto-inertial fusion is an emerging concept for inertial fusion and a pathway to the study of dense plasmas in ultrahigh magnetic fields (magnetic fields in excess of 500 T). The presence of magnetic field in an inertial fusion target suppresses cross-field thermal transport and potentially could enable more attractive inertial fusion energy systems. The program is part of the OFES program in high energy density laboratory plasmas (HED-LP).

Y C F Thio

2008-01-01T23:59:59.000Z

384

Condensed hydrogen for thermonuclear fusion  

SciTech Connect

Inertial confinement fusion (ICF) power, in either pure fusion or fission-fusion hybrid reactors, is a possible solution for future world's energy demands. Formation of uniform layers of a condensed hydrogen fuel in ICF targets has been a long standing materials physics challenge. Here, we review the progress in this field. After a brief discussion of the major ICF target designs and the basic properties of condensed hydrogens, we review both liquid and solid layering methods, physical mechanisms causing layer nonuniformity, growth of hydrogen single crystals, attempts to prepare amorphous and nanostructured hydrogens, and mechanical deformation behavior. Emphasis is given to current challenges defining future research areas in the field of condensed hydrogens for fusion energy applications.

Kucheyev, S. O.; Hamza, A. V. [Nanoscale Synthesis and Characterization Laboratory, Lawrence Livermore National Laboratory, Livermore, California 94551 (United States)

2010-11-15T23:59:59.000Z

385

Genetic fusion  

Science Journals Connector (OSTI)

Genetic fusion is introduced as a model for evolution. In the fusion two genomes are combined to generate a longer genome. Representing each species by a binary genetic sequence, we introduce a fitness function on the bit sequence. As the evolutionary dynamics, we incoroporate mutation, genetic fusion, and reproduction in proportion to fitness. It is found that genetic fusion leads to the appearance of module-type sequences and duplicated genes. The time necessary to find a sequence with large fitness is largely reduced by the inclusion of genetic fusion, which suggests the application of our algorithm to optimization problems.

Takashi Ikegami and Kunihiko Kaneko

1990-12-24T23:59:59.000Z

386

Requested Information Provided by the Three Major United States Toroidal Magnetic Fusion Facilities: Report of the 2005 FESAC Facilities Panel, Vol. 2  

Science Journals Connector (OSTI)

This is Volume 2 of a report of a panel established by the U.S. Department of Energy Fusion Energy Sciences Advisory Committee (FESAC) charged to review the three major U.S. fusion facilities. The Panel requested...

Jill Dahlburg; Steven L. Allen; Riccardo Betti

2005-12-01T23:59:59.000Z

387

Steady improved confinement in FTU high field plasmas sustained by deep pellet injection  

E-Print Network (OSTI)

major adverse MHD events and no impurity accumulation (an outflow of Nuclear Fusion, Vol. 41, No. 11 c to the input power due to particle concentration in the well confined hot core. Deep pellet injection (e

Vlad, Gregorio

388

Military in clash over US nuclear fusion research  

Science Journals Connector (OSTI)

... the appropriate strategy for pursuing one of the most promising paths towards a commercially-viable nuclear fusion energy programme - namely the use of inertial confinement techniques, which would harness the ...

1979-10-11T23:59:59.000Z

389

MIT Plasma Science & Fusion Center: research, alcator, publications...  

NLE Websites -- All DOE Office Websites (Extended Search)

Reversal and Energy Confinement Saturation in Alcator C-Mod (APS 2011) Getting a Fusion Plasma to Take Out the Trash (APS 2011) Hot and Dense Plasmas with Low Power Loads on...

390

Establishment of an Institute for Fusion Studies. Technical progress report, November 1, 1994--October 31, 1995  

SciTech Connect

The Institute for Fusion Studies is a national center for theoretical fusion plasma physics research. Its purposes are to (1) 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) serve as a national and international center for information exchange by hosting exchange visits, conferences, and workshops; and (3) train students and postdoctoral research personnel for the fusion energy program and plasma physics research areas. During FY 1995, a number of significant scientific advances were achieved at the IFS, both in long-range fundamental problems as well as in near-term strategic issues, consistent with the Institute`s mandate. Examples of these achievements include, for example, tokamak edge physics, analytical and computational studies of ion-temperature-gradient-driven turbulent transport, alpha-particle-excited toroidal Alfven eigenmode nonlinear behavior, sophisticated simulations for the Numerical Tokamak Project, and a variety of non-tokamak and non-fusion basic plasma physics applications. Many of these projects were done in collaboration with scientists from other institutions. Research discoveries are briefly described in this report.

NONE

1995-07-01T23:59:59.000Z

391

The M3D-C1 Approach to Simulating 3D 2-fluid Magnetohydrodynamics in Magnetic Fusion Experiments  

SciTech Connect

A new approach for solving the 3D MHD equations in a strongly magnetized toroidal plasma is presented which uses high-order 2D finite elements with C1 continuity. The vector fields use a physics-based decomposition. An efficient implicit time advance separates the velocity and field advance. ITAPS (SCOREC) adaptivity software and TOPS solvers are used.

S. C. Jardin, N. Ferraro, X. Luo, J. Chen, J. Breslau, K.E. Jansen, and M. S. Shephard

2008-06-24T23:59:59.000Z

392

HIGH-ENERGY HEAVY-ION BEAMS AS IGNITERS FOR COMMERCIAL-SCALE INTERTIAL-FUSION POWER PLANTS  

E-Print Network (OSTI)

confined controlled thermonuclear fusion has been David L.steady succession of thermonuclear microexplosions of smallwas the detonation of thermonuclear bombs. I t was proposed

Judd, D.L.

2011-01-01T23:59:59.000Z

393

Final Report for DoE Grant DE-FG02-06ER54878, Laboratory Studies of Reconnection in Magnetically Confined Plasmas  

SciTech Connect

The study of the collisionless magnetic reconnection constituted the primary work carried out under this grant. The investigations utilized two magnetic configurations with distinct boundary conditions. Both configurations were based upon the Versatile Toroidal Facility (VTF). The first configuration is characterized by open boundary conditions where the magnetic field lines interface directly with the vacuum vessel walls. The reconnection dynamics for this configuration has been methodically characterized and it has been shown that kinetic effects related to trapped electron trajectories are responsible for the high rates of reconnection observed. This type of reconnection has not been investigated before. Nevertheless, the results are directly relevant to observations by the Wind spacecraft of fast reconnection deep in the Earth magnetotail. The second configuration was developed to be specifically relevant to numerical simulations of magnetic reconnection, allowing the magnetic field-lines to be contained inside the device. The configuration is compatible with the presence of large current sheets in the reconnection region and reconnection is observed in fast powerful bursts. These reconnection events facilitate the first experimental investigations of the physics governing the spontaneous onset of fast reconnection. In this Report we review the general motivation of this work, the experimental set-up, and the main physics results.

Jan Egedal-Pedersen

2010-01-29T23:59:59.000Z

394

23rd IAEA Fusion Energy Conference: Summary Of Sessions EX/C and ICC  

SciTech Connect

An overview is given of recent experimental results in the areas of innovative confinement concepts, operational scenarios and confinement experiments as presented at the 2010 IAEA Fusion Energy Conference. Important new findings are presented from fusion devices worldwide, with a strong focus towards the scientific and technical issues associated with ITER and W7-X devices, presently under construction.

Richard J. Hawryluk

2011-01-05T23:59:59.000Z

395

Electromagnetic confinement and movement of thin sheets of molten metal  

DOE Patents (OSTI)

An apparatus capable of producing a combination of magnetic fields that can retain a metal in liquid form in a region having a smooth vertical boundary including a levitation magnet that produces low frequency magnetic field traveling waves to retain the metal and a stabilization magnet that produces a high frequency magnetic field to produce a smooth vertical boundary. As particularly adapted to the casting of solid metal sheets, a metal in liquid form can be continuously fed into one end of the confinement region produced by the levitation and stabilization magnets and removed in solid form from the other end of confinement region. An additional magnet may be included for support at the edges of the confinement region where eddy currents loop.

Lari, Robert J. (Aurora, IL); Praeg, Walter F. (Palos Park, IL); Turner, Larry R. (Naperville, IL)

1990-01-01T23:59:59.000Z

396

Macron Formed Liner Compression as a Practical Method for Enabling Magneto-Inertial Fusion  

SciTech Connect

The entry of fusion as a viable, competitive source of power has been stymied by the challenge of finding an economical way to provide for the confinement and heating of the plasma fuel. The main impediment for current nuclear fusion concepts is the complexity and large mass associated with the confinement systems. To take advantage of the smaller scale, higher density regime of magnetic fusion, an efficient method for achieving the compressional heating required to reach fusion gain conditions must be found. The very compact, high energy density plasmoid commonly referred to as a Field Reversed Configuration (FRC) provides for an ideal target for this purpose. To make fusion with the FRC practical, an efficient method for repetitively compressing the FRC to fusion gain conditions is required. A novel approach to be explored in this endeavor is to remotely launch a converging array of small macro-particles (macrons) that merge and form a more massive liner inside the reactor which then radially compresses and heats the FRC plasmoid to fusion conditions. The closed magnetic field in the target FRC plasmoid suppresses the thermal transport to the confining liner significantly lowering the imploding power needed to compress the target. With the momentum flux being delivered by an assemblage of low mass, but high velocity macrons, many of the difficulties encountered with the liner implosion power technology are eliminated. The undertaking to be described in this proposal is to evaluate the feasibility achieving fusion conditions from this simple and low cost approach to fusion. During phase I the design and testing of the key components for the creation of the macron formed liner have been successfully carried out. Detailed numerical calculations of the merging, formation and radial implosion of the Macron Formed Liner (MFL) were also performed. The phase II effort will focus on an experimental demonstration of the macron launcher at full power, and the demonstration of megagauss magnetic field compression by a small array of full scale macrons. In addition the physics of the compression of an FRC to fusion conditions will be undertaken with a smaller scale MFL. The timescale for testing will be rapidly accelerated by taking advantage of other facilities at MSNW where the target FRC will be created and translated inside the MFL just prior to implosion of the MFL. Experimental success would establish the concept at the â??proof of principleâ? level and the following phase III effort would focus on the full development of the concept into a fusion gain device. Successful operation would lead to several benefits in various fields. It would have application to high energy density physics, as well as nuclear waste transmutation and alternate fission fuel cycles. The smaller scale device could find immediate application as an intense source of neutrons for diagnostic imaging and non-invasive object interrogation.

Slough, John

2011-12-10T23:59:59.000Z

397

Nuclear Fusion Award 2010 speech  

Science Journals Connector (OSTI)

Following the suggestion of Earl Marmar in 1995, I installed a compact von Hamos type x-ray spectrometer (originally built with Elisabeth Rachlew and Jan Kallne) on a tangentially viewing port on the Alcator C-Mod tokamak. The spectrometer views the plasma through a 2 cm diameter hole, and is tuned to H-like argon, suitable for passive measurement of the core toroidal rotation velocity from the Doppler shift. It soon became evident that the rotation in Ohmic L-mode discharges, while for the most part directed counter-current, depends in a very complicated fashion on plasma parameters, notably the electron density, current and magnetic configuration. The rotation can even flip sign for almost no apparent reason! In Ohmic and ion cyclotron range of frequencies (ICRF) heated H-mode plasmas the rotation is in the co-current direction and has a relatively simple dependence on plasma parameters, proportional to the stored energy normalized to the current. Rotation velocities as high as 130 km s-1 have been observed without external momentum input. In dimensionless terms this intrinsic (or spontaneous rotation) depends on the normalized plasma pressure. The association of toroidal rotation with plasma pressure in ICRF H-modes was first observed by Lars-Goran Eriksson in JET discharges. Similar results were subsequently reported for Tore Supra enhanced confinement plasmas. In the early 2000s concerns began to surface about the lack of substantial neutral beam driven rotation in ITER, and intrinsic rotation became a topic of interest in the ITPA Transport Group. Through that connection, similar observations from DIII-D, TCV and JT-60U were added to the growing list. A database of intrinsic rotation observations was assembled with the goal of extrapolating to the expected values for ITER. Both dimensional and dimensionless scalings were developed and formed the backbone of the 2007 Nuclear Fusion paper. I gratefully acknowledge the important contributions to this paper from Alex Ince-Cushman, John deGrassie, Lars-Goran Eriksson, Yoshiteru Sakamoto, Andrea Scarabosio and Yuri Podpaly, as well as the other coauthors. I would like to express my sincere appreciation to Earl Marmar, Martin Greenwald and Miklos Porkolab at MIT for continued support of this work, as well as to the entire C-Mod team. This award was made possible due to the insight of Mitsuru Kikuchi and the support of the IAEA through Werner Burkhart, and I am truly grateful to both of them. Many thanks as well to the outstanding staff at Nuclear Fusion. It is a distinct honor to be included in the group of previous winners: Tim Luce, Clemente Angioni, Todd Evans and Steve Sabbagh. It is also a great honor to be considered alongside the 2010 nominees: Phil Snyder, Sibylle Guenter, Maiko Yoshida, Hajime Urano, Fulvio Zonca, Erik Garcia, Costanza Maggi, Hartmut Zohm, Thierry Loarer and Bruce Lipschultz. Finally, I would like to thank the readers of Nuclear Fusion for the many citations. John Rice 2010 Nuclear Fusion Award winner Plasma Science and Fusion Center, MIT, Cambridge, MA, USA

John Rice

2011-01-01T23:59:59.000Z

398

Magnetic Braids Anthony Yeates  

E-Print Network (OSTI)

flux function Main result Conclusion 2. Thermonuclear confinement devices. ITER (Internat'l Thermonuclear Experimental Reactor). Inside the KSTAR tokamak. Correspond to periodic magnetic braids. 4 / 22

Dundee, University of

399

Fusion Website  

NLE Websites -- All DOE Office Websites (Extended Search)

Fusion Basics Fusion Intro Fusion Education Research DIII-D Internal Site Opportunities Virtual DIII-D Collaborators Countries Physics Eng Physics Operations Diagnostics Computing IFT IFT Site ITER ITER Site FDF Theory Collaborators Conferences GA-Hosted Room Reservations Fusion Meetings Plasma Publications Presentations Images Brochures Posters Movies Corporate General Atomics Products Visitor GA Fusion Hotels Internal Users GA Internal Site DIII-D General Experimental Science Experimental Science Home 2013 Experimental Campaign Burning Plasma Physics Dynamics & Control Boundary and Pedestal ELM Control Operations Diagnostics Computing Support Visitors DIII-D Web Access Help IFT ITER-GA Theory Research Highlights Personnel Links Policies Safety Comp Support Trouble Ticket Eng/Design Fusion Webmail Phone Book

400

Experimental validation of Mueller-Stokes theory and investigation of the influence of the Cotton-Mouton effect on polarimetry in a magnetized fusion plasma  

SciTech Connect

Mueller-Stokes theory can be used to calculate the polarization evolution of an electromagnetic (EM) wave as it propagates through a magnetized plasma. Historically, the theory has been used to interpret polarimeter signals from systems operating on fusion plasmas. These interpretations have mostly employed approximations of Mueller-Stokes theory in regimes where either the Faraday rotation (FR) or the Cotton-Mouton (CM) effect is dominant. The current paper presents the first systematic comparison of polarimeter measurements with the predictions of full Mueller-Stokes theory where conditions transition smoothly from a FR-dominant (i.e., weak CM effect) plasma to one where the CM effect plays a significant role. A synthetic diagnostic code, based on Mueller-Stokes theory accurately reproduces the trends evident in the experimentally measured polarimeter phase over this entire operating range, thereby validating Mueller-Stokes theory. The synthetic diagnostic code is then used to investigate the influence of the CM effect on polarimetry measurements. As expected, the measurements are well approximated by the FR effect when the CM effect is predicted to be weak. However, the code shows that as the CM effect increases, it can compete with the FR effect in rotating the polarization of the EM-wave. This results in a reduced polarimeter response to the FR effect, just as observed in the experiment. The code also shows if sufficiently large, the CM effect can even reverse the handedness of a wave launched with circular polarization. This helps to understand the surprising experimental observations that the sensitivity to the FR effect can be nearly eliminated at high enough B{sub T} (2.0 T). The results also suggest that the CM effect on the plasma midplane can be exploited to potentially measure magnetic shear in tokamak plasmas. These results establish increased confidence in the use of such a synthetic diagnostic code to guide future polarimetry design and interpret the resultant experimental data.

Zhang, J.; Peebles, W. A.; Crocker, N. A.; Carter, T. A.; Doyle, E. J.; Rhodes, T. L.; Wang, G.; Zeng, L. [Department of Physics and Astronomy, University of California, Los Angeles, California 90095-7099 (United States)] [Department of Physics and Astronomy, University of California, Los Angeles, California 90095-7099 (United States); Hyatt, A. W. [General Atomics, P.O. Box 85608, San Diego, California 92186-5608 (United States)] [General Atomics, P.O. Box 85608, San Diego, California 92186-5608 (United States)

2013-10-15T23:59:59.000Z

Note: This page contains sample records for the topic "magnetic confinement fusion" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


401

Ceramics for fusion devices  

SciTech Connect

Ceramics are required for a number of applications in fusion devices, among the most critical of which are magnetic coil insulators, windows for RF heating systems, and structural uses. Radiation effects dominate consideration of candidate materials, although good pre-irradiation properties are a requisite. Materials and components can be optimized by careful control of chemical and microstructural content, and application of brittle material design and testing techniques. Future directions for research and development should include further extension of the data base in the areas of electrical, structural, and thermal properties; establishment of a fission neutron/fusion neutron correlation including transmutation gas effects; and development of new materials tailored to meet the specific needs of fusion reactors.

Clinard, F.W. Jr.

1984-01-01T23:59:59.000Z

402

Magnetism  

Science Journals Connector (OSTI)

Historically, magnetism is related to rock magnetism, due to a few minerals exhibiting spontaneous magnetization. Attractive properties of magnetite were already known in Antiquity and were used for navigation...

Guillaume Morin

1998-01-01T23:59:59.000Z

403

Regarding Confinement Resonances  

NLE Websites -- All DOE Office Websites (Extended Search)

Regarding Confinement Resonances Regarding Confinement Resonances Regarding Confinement Resonances Print Wednesday, 27 July 2011 00:00 When an atom is encapsulated inside a hollow spherical carbon buckyball, the complex is called an "endofullerene." Theoretically, if the atom is an unreactive noble gas like xenon, it should be centered within the cage. If one or more of the atom's electrons are boosted out of the cage by an x-ray photon, the electron waves may be transmitted through or reflected off the carbon cage, giving rise to an interference effect similar to waves in a water tank. These so-called "confinement resonances" were predicted theoretically a decade ago but have never been observed. In the first experimental test of this theory, members of an international team led by Ronald Phaneuf, University of Nevada, and working at ALS Beamline 10.0.1 produced and isolated xenon endofullerenes and observed confinement resonances.

404

magnetism  

Science Journals Connector (OSTI)

magnetism [A class of physical phenomena associated with moving electricity, including the mutual mechanical forces among magnets and electric currents] ? Magnetismus m

2014-08-01T23:59:59.000Z

405

Plasma physics: A promising advance in nuclear fusion  

Science Journals Connector (OSTI)

... Formidable challenges face the decades-long quest to achieve nuclear fusion the power source of stars in the laboratory. For a plasma to ... power source of stars in the laboratory. For a plasma to undergo self-heating nuclear fusion (ignition), it must be both hot and well confined. The facilities that hope ...

Mark Herrmann

2014-02-12T23:59:59.000Z

406

STOCHASTIC ACCELERATION BY A SINGLE WAVE IN A MAGNETIZED PLASMA  

E-Print Network (OSTI)

diffusion An approach to thermonuclear fusion, initiated intemperature, or for a given thermonuclear output too largemagnetic confinement Q = thermonuclear output v systems in

Smith, G.R.

2010-01-01T23:59:59.000Z

407

Fusion Power  

Science Journals Connector (OSTI)

...present cost of coal, on a per-unit-of-energy basis. Nuclear fusion is nuclear combustion, the process that heats the sun and...enough for the release of fusion energy to exceed the heat input; and third, convert the energy released to useful form...

R. F. Post

1971-01-01T23:59:59.000Z

408

High Core Electron Confinement Regimes in FTU Plasmas with Low- or Reversed-Magnetic Shear and High Power Density Electron-Cyclotron-Resonance Heating  

Science Journals Connector (OSTI)

Electron temperatures in excess of 8 keV have been obtained by electron-cyclotron-resonance heating on FTU plasmas at peak densities up to 81019 m -3. The magnetic shear in the plasma core is low or negative, and the electron heat diffusivity remains at, or below, the Ohmic level (0.2 m 2/s), in spite of the very large heating power density (1020 MW/m 3) which produces extremely high temperature gradients (up to 120 keV/m). The ion heat transport remains at the neoclassical level.

P. Buratti et al.

1999-01-18T23:59:59.000Z

409

Advanced fusion concepts: project summaries  

SciTech Connect

This report contains descriptions of the activities of all the projects supported by the Advanced Fusion Concepts Branch of the Office of Fusion Energy, US Department of Energy. These descriptions are project summaries of each of the individual projects, and contain the following: title, principle investigators, funding levels, purpose, approach, progress, plans, milestones, graduate students, graduates, other professional staff, and recent publications. Information is given for each of the following programs: (1) reverse-field pinch, (2) compact toroid, (3) alternate fuel/multipoles, (4) stellarator/torsatron, (5) linear magnetic fusion, (6) liners, and (7) Tormac. (MOW)

None

1980-12-01T23:59:59.000Z

410

Plasma Magnetic Insulation  

Science Journals Connector (OSTI)

29 June 1987 research-article Plasma Magnetic Insulation B. B. Kadomtsev Theoretically the strong magnetic field of a tokamak should confine electrons and ions in a high-temperature...

1987-01-01T23:59:59.000Z

411

Regarding Confinement Resonances  

NLE Websites -- All DOE Office Websites (Extended Search)

Regarding Confinement Resonances Print Regarding Confinement Resonances Print When an atom is encapsulated inside a hollow spherical carbon buckyball, the complex is called an "endofullerene." Theoretically, if the atom is an unreactive noble gas like xenon, it should be centered within the cage. If one or more of the atom's electrons are boosted out of the cage by an x-ray photon, the electron waves may be transmitted through or reflected off the carbon cage, giving rise to an interference effect similar to waves in a water tank. These so-called "confinement resonances" were predicted theoretically a decade ago but have never been observed. In the first experimental test of this theory, members of an international team led by Ronald Phaneuf, University of Nevada, and working at ALS Beamline 10.0.1 produced and isolated xenon endofullerenes and observed confinement resonances.

412

Regarding Confinement Resonances  

NLE Websites -- All DOE Office Websites (Extended Search)

Regarding Confinement Resonances Print Regarding Confinement Resonances Print When an atom is encapsulated inside a hollow spherical carbon buckyball, the complex is called an "endofullerene." Theoretically, if the atom is an unreactive noble gas like xenon, it should be centered within the cage. If one or more of the atom's electrons are boosted out of the cage by an x-ray photon, the electron waves may be transmitted through or reflected off the carbon cage, giving rise to an interference effect similar to waves in a water tank. These so-called "confinement resonances" were predicted theoretically a decade ago but have never been observed. In the first experimental test of this theory, members of an international team led by Ronald Phaneuf, University of Nevada, and working at ALS Beamline 10.0.1 produced and isolated xenon endofullerenes and observed confinement resonances.

413

Regarding Confinement Resonances  

NLE Websites -- All DOE Office Websites (Extended Search)

Regarding Confinement Resonances Print Regarding Confinement Resonances Print When an atom is encapsulated inside a hollow spherical carbon buckyball, the complex is called an "endofullerene." Theoretically, if the atom is an unreactive noble gas like xenon, it should be centered within the cage. If one or more of the atom's electrons are boosted out of the cage by an x-ray photon, the electron waves may be transmitted through or reflected off the carbon cage, giving rise to an interference effect similar to waves in a water tank. These so-called "confinement resonances" were predicted theoretically a decade ago but have never been observed. In the first experimental test of this theory, members of an international team led by Ronald Phaneuf, University of Nevada, and working at ALS Beamline 10.0.1 produced and isolated xenon endofullerenes and observed confinement resonances.

414

Accelerator development for heavy ion fusion  

SciTech Connect

Accelerator technology development is presented for heavy ion drivers used in inertial confinement fusion. The program includes construction of low-velocity ''test bed'' accelerator facilities, development of analytical and experimental techniques to characterize ion beam behavior, and the study of ion beam energy deposition.

Talbert, W.L. Jr.; Sawyer, G.A.

1980-01-01T23:59:59.000Z

415

Fusion Power Associates 34th Annual Meeting  

E-Print Network (OSTI)

for Inertial Confinement Fusion R. Betti and D. D. Meyerhofer Departments of Mechanical Engineering and Physics us to do that? Betti et al Phys. Plasmas 17, 058102 (2010) Chang et al, Phys. Rev. Lett 104, 135002 (2010) Zhou-Betti, Phys. Plasmas 15, 102707 (2008) Can't do it Can't do it #12;Increasing the IFAR

416

MIT Plasma Science & Fusion Center: research>alcator>introduction  

NLE Websites -- All DOE Office Websites (Extended Search)

Publications & News Meetings & Seminars Contact Information Physics Research High-Energy- Density Physics Waves & Beams Fusion Technology & Engineering Francis Bitter Magnet...

417

Linear electric field frequency shift (important for next generation electric dipole moment searches) induced in confined gases by a magnetic field gradient  

E-Print Network (OSTI)

The search for particle electric dipole moments (edm) represents a most promising way to search for physics beyond the standard model. A number of groups are planning a new generation of experiments using stored gases of various kinds. In order to achieve the target sensitivities it will be necessary to deal with the systematic error resulting from the interaction of the well-known $\\overrightarrow{v}\\times \\overrightarrow{E}$ field with magnetic field gradients (often referred to as the geometric phase effect (Commins, ED; Am. J. Phys. \\QTR{bf}{59}, 1077 (1991), Pendlebury, JM \\QTR{em}{et al;} Phys. Rev. \\QTR{bf}{A70}, 032102 (2004)). This interaction produces a frequency shift linear in the electric field, mimicking an edm. In this work we introduce an analytic form for the velocity auto-correlation function which determines the velocity-position correlation function which in turn determines the behavior of the frequency shift (Lamoreaux, SK and Golub, R; Phys. Rev \\QTR{bf}{A71}, 032104 (2005)) and show how it depends on the operating conditions of the experiment. We also discuss some additional issues.

Authors A. L. Barabanov; R. Golub; S. K. Lamoreaux

2006-07-17T23:59:59.000Z

418

Fusion Prospects  

Science Journals Connector (OSTI)

...Ermesto Mazzucato Princeton Plasma Physics Laboratory, Princeton University, Princeton, NJ 08543, USA E-mail: mazzucato@pppl.gov Several recent letters proclaim once again the superior promise that thermonuclear fu-sion offers for future large-scale...

Ernesto Mazzucato

1996-02-16T23:59:59.000Z

419

Fusion energy  

SciTech Connect

Larry Baylor explains how the US ITER team is working to prevent solar flare-like events at a fusion energy reactor that will be like a small sun on earth

Baylor, Larry

2014-05-02T23:59:59.000Z

420

Fusion energy  

ScienceCinema (OSTI)

Larry Baylor explains how the US ITER team is working to prevent solar flare-like events at a fusion energy reactor that will be like a small sun on earth

Baylor, Larry

2014-05-23T23:59:59.000Z

Note: This page contains sample records for the topic "magnetic confinement fusion" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


421

Preface to Special Topic: Advances in Radio Frequency Physics in Fusion Plasmas  

SciTech Connect

It has long been recognized that auxiliary plasma heating will be required to achieve the high temperature, high density conditions within a magnetically confined plasma in which a fusion burn may be sustained by copious fusion reactions. Consequently, the application of radio and microwave frequency electromagnetic waves to magnetically confined plasma, commonly referred to as RF, has been a major part of the program almost since its inception in the 1950s. These RF waves provide heating, current drive, plasma profile control, and Magnetohydrodynamics (MHD) stabilization. Fusion experiments employ electromagnetic radiation in a wide range of frequencies, from tens of MHz to hundreds of GHz. The fusion devices containing the plasma are typically tori, axisymmetric or non, in which the equilibrium magnetic fields are composed of a strong toroidal magnetic field generated by external coils, and a poloidal field created, at least in the symmetric configurations, by currents flowing in the plasma. The waves are excited in the peripheral regions of the plasma, by specially designed launching structures, and subsequently propagate into the core regions, where resonant wave-plasma interactions produce localized heating or other modification of the local equilibrium profiles. Experimental studies coupled with the development of theoretical models and advanced simulation codes over the past 40+ years have led to an unprecedented understanding of the physics of RF heating and current drive in the core of magnetic fusion devices. Nevertheless, there are serious gaps in our knowledge base that continue to have a negative impact on the success of ongoing experiments and that must be resolved as the program progresses to the next generation devices and ultimately to demo and fusion power plant. A serious gap, at least in the ion cyclotron (IC) range of frequencies and partially in the lower hybrid frequency ranges, is the difficulty in coupling large amount of power to the plasma while minimizing the interaction between the plasma and launching structures. These potentially harmful interactions between the plasma and the vessel and launching structures are challenging: (i) significant and variable loss of power in the edge regions of confined plasmas and surrounding vessel structures adversely affect the core plasma performance and lifetime of a device; (ii) the launcher design is partly trial and error, with the consequence that launchers may have to be reconfigured after initial tests in a given device, at an additional cost. Over the broader frequency range, another serious gap is a quantitative lack of understanding of the combined effects of nonlinear wave-plasma processes, energetic particle interactions and non-axisymmetric equilibrium effects on determining the overall efficiency of plasma equilibrium and stability profile control techniques using RF waves. This is complicated by a corresponding lack of predictive understanding of the time evolution of transport and stability processes in fusion plasmas.

Tuccillo, Angelo A.; Ceccuzzi, Silvio [Unit Tecnica Fusione ENEA, C. R. Frascati, 00044 RM (Italy); Phillips, Cynthia K. [Princeton Plasma Physics Laboratory, Princeton, New Jersey 08543 (United States)

2014-06-15T23:59:59.000Z

422

Magnetism  

Science Journals Connector (OSTI)

... dipoles in applied fields". It deals with the classical (Langevin) theory of para-magnetism, anisotropy fields and magnetic measurements. In the next chapter "Atomic structure" the author ... special relevance to ferrites and the inclusion of a quite lengthy discussion of Pauli para-magnetism and of Stoner's treatment of itinerant electron ferromagnetism, though it does much to ...

E. W. LEE

1972-03-31T23:59:59.000Z

423

Control of Hamiltonian chaos as a possible tool to control anomalous transport in fusion plasmas  

Science Journals Connector (OSTI)

It is shown that a relevant control of Hamiltonian chaos is possible through suitable small perturbations whose form can be explicitly computed. In particular, it is possible to control (reduce) the chaotic diffusion in the phase space of a Hamiltonian system with 1.5 degrees of freedom which models the diffusion of charged test particles in a turbulent electric field across the confining magnetic field in controlled thermonuclear fusion devices. Though still far from practical applications, this result suggests that some strategy to control turbulent transport in magnetized plasmas, in particular, tokamaks, is conceivable. The robustness of the control is investigated in terms of a departure from the optimum magnitude, of a varying cutoff at large wave vectors, and of random errors on the phases of the modes. In all three cases, there is a significant region of maximum efficiency in the vicinity of the optimum control term.

Guido Ciraolo; Franoise Briolle; Cristel Chandre; Elena Floriani; Ricardo Lima; Michel Vittot; Marco Pettini; Charles Figarella; Philippe Ghendrih

2004-05-18T23:59:59.000Z

424

Control of stochasticity in magnetic field lines  

E-Print Network (OSTI)

We present a method of control which is able to create barriers to magnetic field line diffusion by a small modification of the magnetic perturbation. This method of control is based on a localized control of chaos in Hamiltonian systems. The aim is to modify the perturbation locally by a small control term which creates invariant tori acting as barriers to diffusion for Hamiltonian systems with two degrees of freedom. The location of the invariant torus is enforced in the vicinity of the chosen target. Given the importance of confinement in magnetic fusion devices, the method is applied to two examples with a loss of magnetic confinement. In the case of locked tearing modes, an invariant torus can be restored that aims at showing the current quench and therefore the generation of runaway electrons. In the second case, the method is applied to the control of stochastic boundaries allowing one to define a transport barrier within the stochastic boundary and therefore to monitor the volume of closed field lines.

Cristel Chandre; Michel Vittot; Guido Ciraolo; Philippe Ghendrih; Ricardo Lima

2005-04-14T23:59:59.000Z

425

Cable test raises fears at fusion project  

Science Journals Connector (OSTI)

... Scientists on three continents are scrambling to understand a potentially serious problem with superconducting cables destined for ITER, the world's largest fusion experiment. Nature has learned that preliminary ... ITER, the world's largest fusion experiment. Nature has learned that preliminary tests of cable for ITER's powerful central magnet show that it degrades too quickly to be used ...

Geoff Brumfiel

2011-03-08T23:59:59.000Z

426

2011 Confined Space Program Update  

NLE Websites -- All DOE Office Websites (Extended Search)

Confined Space Entry Program Update Confined Space Entry Program Update IMPORTANT: After reading this document, click the "Get Course Credit" link at the bottom of the page. You will then log in to the EHS training system using your LDAP to get course credit. LBNL's confined space entry program was substantially improved this year. Several new features have been included which improve overall safety for Confined Space Entrants and better align the confined space entry program with the OSHA requirements. As an Activity Lead, Confined Space Entrant or Entry Supervisor, you should be aware of the following: We improved the procedures for safely working in confined spaces. Please review the new Chapter 34 in Publication 3000. Additionally, we have a new planning tool known as the confined space inventory which is a registry of LBNL's confined spaces, their potential hazards and safe work procedures unique to a particular confined space.

427

First Observations of Nonhydrodynamic Mix at the Fuel-Shell Interface in Shock-Driven Inertial Confinement Implosions  

E-Print Network (OSTI)

A strong nonhydrodynamic mechanism generating atomic fuel-shell mix has been observed in strongly shocked inertial confinement fusion implosions of thin deuterated-plastic shells filled with [superscript 3]He gas. These ...

Amendt, P.

428

Fusion Power Associates Awards  

NLE Websites -- All DOE Office Websites (Extended Search)

Fusion Power Associates Awards Fusion Power Associates is "a non-profit, tax-exempt research and educational foundation, providing information on the status of fusion development...

429

Minimal fusion systems.  

E-Print Network (OSTI)

??We define minimal fusion systems in a way that every non-solvable fusion system has a section which is minimal. Minimal fusion systems can also be (more)

Henke, Ellen

2010-01-01T23:59:59.000Z

430

Dynamic Instruction Fusion  

E-Print Network (OSTI)

SANTA CRUZ DYNAMIC INSTRUCTION FUSION A thesis submitted in4 2.2 Instruction Fusion & Complex10 3.1 Fusion Selection

Lee, Ian

2012-01-01T23:59:59.000Z

431

Dust Divertor for a Tokamak Fusion Reactor  

Science Journals Connector (OSTI)

The conventional tokamak fusion reactor deploys a magnetic divertor design which channels...1], or covered by flowing liquid metals [2...]. A typical estimate for the plasma heat flux to the divertor for a tokama...

X. Z. Tang; G. L. Delzanno

2010-10-01T23:59:59.000Z

432

RSNA 2002: Image Fusion Image Fusion  

E-Print Network (OSTI)

of anatomical feature #12;RSNA 2002: Image Fusion Types of Data to be Registered Anatomic CT, MRI, US DigitizedRSNA 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

Pelizzari, Charles A.

433

Fusion Ignition Research Experiment Princeton Plasma Physics Laboratory  

E-Print Network (OSTI)

Fusion Ignition Research Experiment Dale Meade Princeton Plasma Physics Laboratory Abstract Understanding the properties of high gain (alpha­dominated) fusion plasmas in an advanced toroidal configuration­dominated plasmas in advanced toroidal systems. Technical Challenges for Major Next Steps in Magnetic Fusion Energy

434

Fusion pumped laser  

DOE Patents (OSTI)

The apparatus of this invention may comprise a system for generating laser radiation from a high-energy neutron source. The neutron source is a tokamak fusion reactor generating a long pulse of high-energy neutrons and having a temperature and magnetic field effective to generate a neutron flux of at least 10/sup 15/ neutrons/cm/sup 2//center dot/s. Conversion means are provided adjacent the fusion reactor at a location operable for converting the high-energy neutrons to an energy source with an intensity and energy effective to excite a preselected lasing medium. A lasing medium is spaced about and responsive to the energy source to generate a population inversion effective to support laser oscillations for generating output radiation. 2 figs., 2 tabs.

Pappas, D.S.

1987-07-31T23:59:59.000Z

435

Fusion Ignition Research Experiment Highlights  

E-Print Network (OSTI)

objectives for FIRE are to address the critical burning plasma issues of an attractive magnetic fusion power plant as envisioned by the Advanced Reactor Innovation Evaluation Studies (ARIES). The FIRE Design study. institutions, and is managed through the Virtual Laboratory for Technology. The technical work on FIRE has been

436

Magnetism  

Science Journals Connector (OSTI)

... THIS is a good book, and we are glad to see the subject of magnetism fully treated in a popularly written text-book. It is a second edition of ... of importance, accuracy, and exhaustiveness, places the present treatise, as far as terrestrial magnetism is concerned, much before any similar book with which we are acquainted. The correction ...

JAMES STUART

1872-03-07T23:59:59.000Z

437

Magnetic Divertor for Low Plasma Recycling in Tokamaks Ernesto Mazzucato |  

NLE Websites -- All DOE Office Websites (Extended Search)

Magnetic Divertor for Low Plasma Recycling in Tokamaks Ernesto Mazzucato Magnetic Divertor for Low Plasma Recycling in Tokamaks Ernesto Mazzucato Existing experiments indicate that low recycling of exhausted particles can improve the energy confinement in tokamaks, very likely by preventing the cooling of the plasma edge and thereby causing a reduction in the level of plasma turbulence. This can reduce the size of a tokamak fusion reactor, making the latter a more viable source of energy. The necessary conditions for low recycling can be achieved with the use of a new magnetic divertor, where the exhausted particles are injected through a narrow aperture into a large chamber. Exhausting the particles into a large chamber prevents their return to the plasma, resulting in a reduction in plasma recycling to a level where existing experiments have shown a large enhancement in plasma

438

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)

2012-05-25T23:59:59.000Z

439

First Observations of Nonhydrodynamic Mix at the Fuel-Shell Interface in Shock-Driven Inertial Confinement Implosions  

E-Print Network (OSTI)

. Wilks,2 A. Greenwood,4 and A. Nikroo4 1 Plasma Science and Fusion Center, Massachusetts Institute, California 94550, USA 3 Laboratory for Laser Energetics, University of Rochester, Rochester, New York 14623 shocked inertial confinement fusion implosions of thin deuterated-plastic shells filled with 3 He gas

440

Edge Stability and Transport Control with Resonant Magnetic Perturbations in Collisionless Tokamak Plasmas  

SciTech Connect

A critical issue for fusion plasma research is the erosion of the first wall of the experimental device due to impulsive heating from repetitive edge magneto-hydrodynamic (MHD) instabilities known as 'edge-localized modes' (ELMs). Here, we show that the addition of small resonant magnetic field perturbations completely eliminates ELMs while maintaining a steady-state high-confinement (H-mode) plasma. These perturbations induce a chaotic behavior in the magnetic field lines, which reduces the edge pressure gradient below the ELM instability threshold. The pressure gradient reduction results from a reduction in particle content of the plasma, rather than an increase in the electron thermal transport. This is inconsistent with the predictions of stochastic electron heat transport theory. These results provide a first experimental test of stochastic transport theory in a highly rotating, hot, collisionless plasma and demonstrate a promising solution to the critical issue of controlling edge instabilities in fusion plasma devices.

Evans, T E; Moyer, R A; Burrell, K H; Fenstermacher, M E; Joseph, I; Leonard, A W; Osborne, T H; Porter, G D; Schaffer, M J; Snyder, P B; Thomas, P R; Watkins, J G; West, W P

2006-06-13T23:59:59.000Z

Note: This page contains sample records for the topic "magnetic confinement fusion" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


441

IOP PUBLISHING PLASMA PHYSICS AND CONTROLLED FUSION Plasma Phys. Control. Fusion 55 (2013) 085015 (7pp) doi:10.1088/0741-3335/55/8/085015  

E-Print Network (OSTI)

IOP PUBLISHING PLASMA PHYSICS AND CONTROLLED FUSION Plasma Phys. Control. Fusion 55 (2013) 085015), single-crystal LaB6 cathode to inject a low-voltage electron beam into a strongly magnetized, cold

California at Los Angles, University of

442

Fusion Power  

Science Journals Connector (OSTI)

...later) of fusion fuel above its ignition point-about 100 million degrees...closely, so that prediction based on theory is becoming much more...new-generation experiments, based on the successes of the old...substantially lower than that of steam turbine-alternator conversion...

R. F. Post

1971-01-01T23:59:59.000Z

443

Inertial fusion in the nineties  

SciTech Connect

The 1980s has proven to be an exicting time for the inertial confinement fusion (ICF) program. Major new laser and light-ion drivers have been constructed and have produced some encouraging results. The 1990s will be a crucial time for the ICF program. A decision for proceeding with the next facility is scheduled for the early 1990s. If the decision is positive, planning and construction of this facility will occur. Depending on the time required for design and construction, this next-generation facility could become operational near the turn of the century. 21 refs., 4 figs.

Harris, D.B.; Dudziak, D.J.; Cartwright, D.C.

1987-01-01T23:59:59.000Z

444

PREPARED FOR THE U.S. DEPARTMENT OF ENERGY, UNDER CONTRACT DE-AC02-76CH03073  

E-Print Network (OSTI)

of applications. One of their applications is in RF heating for magnetically confined plasma fusion research

445

RECENT PROGRESS IN HEAVY ION SOURCES  

E-Print Network (OSTI)

beams of hydrogen into thermonuclear fusion reactors. Ain magnetic confinement thermonuclear devices, such as

Clark, D.J.

2010-01-01T23:59:59.000Z

446

Fusion spin-offs: An important part of the Oak Ridge National Laboratory Fusion Program  

SciTech Connect

At the Oak Ridge National Laboratory (ORNL) there is a broadly based, interactive fusion program, encompassing theory and atomic physics, computing, the technology of heating and fueling plasmas, superconducting magnets, robotics, materials developments, design studies, and experiments and diagnostics.

Berry, L.A.; Foster, C.A.; Lubell, M.S.; Nelson, W.D.; Rome, J.A.; Sheffield, J.; White, T.L. [Oak Ridge National Lab., TN (United States)

1993-12-01T23:59:59.000Z

447

Vlasov simulations of kinetic enhancement of Raman backscatter in laser fusion plasmas  

E-Print Network (OSTI)

Stimulated Raman scattering (SRS) is studied in plasmas relevant to inertial confinement fusion (ICF). The Eulerian Vlasov-Maxwell code ELVIS was developed and run for this purpose. Plasma waves are heavily Landau damped ...

Strozzi, D. J. (David J.)

2006-01-01T23:59:59.000Z

448

A time-delay approach for the modeling and control of plasma instabilities in thermonuclear fusion  

E-Print Network (OSTI)

1 A time-delay approach for the modeling and control of plasma instabilities in thermonuclear for thermonuclear fusion plasmas. Indeed, advanced plasma confinement scenarios, such as the ones considered

Sipahi, Rifat

449

INSTITUTE OF PHYSICS PUBLISHING PLASMA PHYSICS AND CONTROLLED FUSION Plasma Phys. Control. Fusion 49 (2007) 4367 doi:10.1088/0741-3335/49/1/004  

E-Print Network (OSTI)

INSTITUTE OF PHYSICS PUBLISHING PLASMA PHYSICS AND CONTROLLED FUSION Plasma Phys. Control. Fusion profile to access regimes with an improved confinement and detecting instabilities for plasma diagnostics plasmas A Jaun1,4 , E R Tracy2 and A N Kaufman3 1 NADA, Royal Institute of Technology, 100 44 Stockholm

Jaun, André

450

Confined plasma gliding arc discharges  

Science Journals Connector (OSTI)

A confined plasma gliding arc is produced in a reactor with two-electrodes contained within a very narrow channel and water spray injected into the discharge. The evolution of pH and conductivity and the formation of hydrogen peroxide in pure water with different carrier gases and the decolourisation and mineralisation of an organic dye were compared with results for a non-confined three-electrode gliding arc reactor. The energy efficiency for the decolourisation of an organic blue dye in the confined reactor is twice that of the non-confined reactor. Significant levels of total organic carbon are removed in the confined plasma reactor.

Radu Burlica; Bruce R. Locke

2008-01-01T23:59:59.000Z

451

Fusion Power Demonstration III  

SciTech Connect

This is the third in the series of reports covering the Fusion Power Demonstration (FPD) design study. This volume considers the FPD-III configuration that incorporates an octopole end plug. As compared with the quadrupole end-plugged designs of FPD-I and FPD-II, this octopole configuration reduces the number of end cell magnets and shortens the minimum ignition length of the central cell. The end-cell plasma length is also reduced, which in turn reduces the size and cost of the end cell magnets and shielding. As a contiuation in the series of documents covering the FPD, this report does not stand alone as a design description of FPD-III. Design details of FPD-III subsystems that do not differ significantly from those of the FPD-II configuration are not duplicated in this report.

Lee, J.D. (ed.)

1985-07-01T23:59:59.000Z

452

Inertial Confinement Fusion Program. Progress report FY 1980  

SciTech Connect

Brief description of work progress during this report period are given for: (1) acceleration of disc targets, (2) laser upgrade, (3) diagnostic development, and (4) stimulated brillouin backscatter theory.

Not Available

1980-12-31T23:59:59.000Z

453

Inertial confinement fusion quarterly report, October-December 1996  

SciTech Connect

The articles in this issue report progress on: Supernova Hydrodynamics Experiments on the Nova Laser; Characterization of Laser-Driven Shock Waves Using Interferometry; Absolute Equation of State Measurements of Compressed Liquid Deuterium Using Nova; Low-Density-Foam Shells; Tetrahedral Hohlraums; The Rosseland Mean Opacity of a Composite Material at High Temperatures.

Hammer, J.

1997-01-01T23:59:59.000Z

454

Inertial Confinement Fusion: steady progressInertial Confinement Fusion: steady progress towards ignition and high gaintowards ignition and high gain  

E-Print Network (OSTI)

, Vilamoura, Portugal. #12;Main route to ignition: indirect laser drive with central hot-spot ignition and ignition implosion DT capsule hohlraum case ~ 30 m of Au (or Pb)µ laser beams 5.5 mm 9.5 mm ablator DT ice constantly accumulated on currently operating non- ignition-scale lasers at Rochester, LANL, ILE, UK

455

FUSION03, Concluding Remarks  

Science Journals Connector (OSTI)

......studies of subbarrier fusion of light nuclei are needed as input into the calculation of dynamics and evolution of various...in this conference. 7. Fusion in astrophysical settings Nuclear fusion reactions play a very important role in astrophysical settings......

A. B. Balantekin

2004-02-01T23:59:59.000Z

456

THE CONCEPT OF ISOCHORIC CENTRAL SPARK IGNITION AND ITS FUEL GAIN IN INERTIAL FUSION  

E-Print Network (OSTI)

1 THE CONCEPT OF ISOCHORIC CENTRAL SPARK IGNITION AND ITS FUEL GAIN IN INERTIAL FUSION of the best methods in inertial confinement fusion (ICF) is the concept of central spark ignition, consisting of two distinct regions named as hot and cold regions and formed by hydro-dynamical implosion of fuel

Boyer, Edmond

457

MIT Plasma Fusion Sciences Center IAP Seminar! Jan 10th, 2012!  

E-Print Network (OSTI)

MIT Plasma Fusion Sciences Center IAP Seminar! Jan 10th, 2012! ! ! ! ! ! Otto Landen! Associate-07NA27344 Inertial Confinement Fusion Physics and Challenges*! #12;The NIF ignition experiments-degenerate fuel Spherical collapse of the shell produces a central hot spot surrounded by cold, dense main fuel

458

data fusion 15 June 2012  

E-Print Network (OSTI)

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

459

magnets  

NLE Websites -- All DOE Office Websites (Extended Search)

I I Painless Physics Articles BEAM COOLING August 2, 1996 By Leila Belkora, Office of Public Affairs ACCELERATION August 16, 1996 By Dave Finley, Accelerator Division Head RF August 30, 1996 By Pat Colestock, Accelerator Division FIXED TARGET PHYSICS September 20, 1996 By Peter H. Garbincius, Physics Section FIXED TARGET PHYSICS PART DEUX October 16, 1996 By Peter H. Garbincius, Physics Section and Leila Belkora, Office of Public Affaris CROSS SECTION November 1, 1996 By Doreen Wackeroth, Theoretical Physics Edited by Leila Belkora, Office of Public Affaris MAGNETS PART I November 15, 1996 By Hank Glass, Technical Support Section Edited by Donald Sena, Office of Public Affairs MAGNETS PART II January 10, 1997 By Hank Glass, Technical Support Section Edited by Donald Sena, Office of Public Affairs

460

Physics analyses on the core plasma properties in the helical fusion DEMO reactor FFHR-d1  

Science Journals Connector (OSTI)

Physics assessments on magnetohydrodynamics equilibrium, neoclassical transport and alpha particle confinement have been carried out for the helical fusion DEMO reactor FFHR-d1, using radial profiles extrapolated from the Large Helical Device. Large Shafranov shift is foreseen in FFHR-d1 due to its high-beta property. This leads to deterioration in neoclassical transport and alpha particle confinement. Plasma position control using vertical magnetic field has been examined and shown to be effective for Shafranov shift mitigation. In particular, in the high-aspect-ratio configuration, it is possible to keep the magnetic surfaces similar to those in vacuum with high central beta of ~8% by applying a proper vertical magnetic field. As long as the Shafranov shift is mitigated, the neoclassical heat loss can be kept at a level compatible with the alpha heating power. The alpha particle loss can also be kept at a low level if the loss boundary of alpha particles is on the blanket surface and the plasma position control is properly applied. The lost positions of alpha particles are localized around the divertor region that is located behind the blanket in FFHR-d1.

J. Miyazawa; Y. Suzuki; S. Satake; R. Seki; Y. Masaoka; S. Murakami; M. Yokoyama; Y. Narushima; M. Nunami; T. Goto; C. Suzuki; I. Yamada; R. Sakamoto; H. Yamada; A. Sagara; the FFHR Design Group

2014-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "magnetic confinement fusion" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


461

Three-dimensional effects on energetic particle confinement and stability  

SciTech Connect

Energetic particle populations in magnetic confinement systems are sensitive to symmetry-breaking effects due to their low collisionality and long confined path lengths. Broken symmetry is present to some extent in all toroidal devices. As such effects preclude the existence of an ignorable coordinate, a fully three-dimensional analysis is necessary, beginning with the lowest order (equilibrium) magnetic fields. Three-dimensional techniques that have been extensively developed for stellarator configurations are readily adapted to other devices such as rippled tokamaks and helical states in reversed field pinches. This paper will describe the methods and present an overview of recent examples that use these techniques for the modeling of energetic particle confinement, Alfven mode structure and fast ion instabilities.

Spong, D. A. [One Bethel Valley Road, Bldg. 5700, P. O. Box 2008, MS-6169, Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831-6169 (United States)

2011-05-15T23:59:59.000Z

462

Braided Fusion Categories First Conjecture  

E-Print Network (OSTI)

Braided Fusion Categories First Conjecture Second Conjecture Braided Weakly Integral Fusion Fusion Categories #12;Braided Fusion Categories First Conjecture Second Conjecture Outline 1 Braided Fusion Categories Preliminaries Dimensions and Braid Representations 2 First Conjecture Finiteness

Rowell, Eric C.

463

Suppression of drift waves in a linear magnetized plasma column  

SciTech Connect

In magnetically confined fusion plasmas, drift wave driven turbulence can lead to enhanced particle transport from the plasma. Because of this, a significant research emphasis has been placed on the suppression of drift waves in the plasma edge. However, the combination of the toroidal geometry and short plasma lifetimes can make it difficult to fully characterize the properties of these instabilities. Because linear magnetized plasma devices offer a combination of simpler geometry and steady state plasma generation, it is possible to perform detailed studies of many types of plasma instabilities-including drift waves. This paper reports on a recent experiment in which low frequency instabilities ({omega} {<=} {omega}{sub ci}) in the Auburn Linear EXperiment for Instability Studies plasma device were characterized as drift waves and through changes in the parallel current, it is shown that it is possible to suppress these instabilities.

DuBois, A. M.; Eadon, A. C.; Thomas, E. Jr. [Physics Department, Auburn University, Auburn, Alabama 36849 (United States)

2012-07-15T23:59:59.000Z

464

The Gasdynamic Mirror Fusion Propulsion System -- Revisited  

SciTech Connect

Many of the previous studies assessing the capability of the gasdynamic mirror (GDM) fusion propulsion system employed analyses that ignored the 'ambipolar' potential. This electrostatic potential arises as a result of the rapid escape of the electrons due to their small mass. As they escape, they leave behind an excess positive charge which manifests itself in an electric field that slows down the electrons while speeding up the ions until their respective axial diffusions are equalized. The indirect effect on the ions is that their confinement time is reduced relative to that of zero potential, and hence the plasma length must be increased to accommodate that change. But as they emerge from the thruster mirror - which serves as a magnetic nozzle - the ions acquire an added energy equal to that of the potential energy, and that in turn manifests itself in increased specific impulse and thrust. We assess the propulsive performance of the GDM thruster, based on the more rigorous theory, by applying it to a round trip Mars mission employing a continuous burn acceleration/deceleration type of trajectory. We find that the length of the device and travel time decrease with increasing plasma density, while the total vehicle mass reaches a minimum at a plasma density of 3 x 1016 cm-3. At such a density, and an initial DT ion temperature of 10 keV, a travel time of 60 days is found to be achievable at GDM propulsion parameters of about 200,000 seconds of specific impulse and approximately 47 kN of thrust.

Kammash, Terry [Department of Nuclear Engineering and Radiological Sciences, University of Michigan, 2355 Bonisteel Blvd, Ann Arbor, MI 48109 (United States); Tang, Ricky [Department of Aerospace Engineering, University Michigan, 1320 Beal Ave, Ann Arbor, MI 48109 (United States)

2005-02-06T23:59:59.000Z

465

Confinement of neutral fermions by a pseudoscalar double-step potential in (1+1) dimensions  

E-Print Network (OSTI)

The problem of confinement of neutral fermions in two-dimensional space-time is approached with a pseudoscalar double-step potential in the Dirac equation. Bound-state solutions are obtained when the coupling is of sufficient intensity. The confinement is made plausible by arguments based on effective mass and anomalous magnetic interaction.

Antonio S. de Castro; Wiliam G. Pereira

2003-01-09T23:59:59.000Z

466

Motion of a Charged Particle in a Static Magnetic Field with Axial Symmetry  

Science Journals Connector (OSTI)

......Aspects of Controlled Fusion Research (1959...Problems of Controlled Thermonuclear Reactions (1958...magnetic machines for fusion or acceleration devices...Aspects of Controlled Fusion Research (Gatlinburg...Problem$ of Controlled Thermonuclear Re- actions, (Acad......

Haruo Obayashi

1961-02-01T23:59:59.000Z

467

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 (OSTI)

INSTITUTE OF PHYSICS PUBLISHING PLASMA PHYSICS AND CONTROLLED FUSION Plasma Phys. Control. Fusion.1088/07