Conferences related to Inertial Confinement

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2021 IEEE Pulsed Power Conference (PPC)

The Pulsed Power Conference is held on a biannual basis and serves as the principal forum forthe exchange of information on pulsed power technology and engineering.


2020 59th IEEE Conference on Decision and Control (CDC)

The CDC is the premier conference dedicated to the advancement of the theory and practice of systems and control. The CDC annually brings together an international community of researchers and practitioners in the field of automatic control to discuss new research results, perspectives on future developments, and innovative applications relevant to decision making, automatic control, and related areas.


2020 IEEE International Conference on Plasma Science (ICOPS)

IEEE International Conference on Plasma Science (ICOPS) is an annual conference coordinated by the Plasma Science and Application Committee (PSAC) of the IEEE Nuclear & Plasma Sciences Society.


2020 IEEE International Power Modulator and High Voltage Conference (IPMHVC)

This conference provides an exchange of technical topics in the fields of Solid State Modulators and Switches, Breakdown and Insulation, Compact Pulsed Power Systems, High Voltage Design, High Power Microwaves, Biological Applications, Analytical Methods and Modeling, and Accelerators.


2020 IEEE Nuclear Science Symposium and Medical Imaging Conference (NSS/MIC)

All areas of ionizing radiation detection - detectors, signal processing, analysis of results, PET development, PET results, medical imaging using ionizing radiation


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Periodicals related to Inertial Confinement

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Applied Superconductivity, IEEE Transactions on

Contains articles on the applications and other relevant technology. Electronic applications include analog and digital circuits employing thin films and active devices such as Josephson junctions. Power applications include magnet design as well asmotors, generators, and power transmission


Lightwave Technology, Journal of

All aspects of optical guided-wave science, technology, and engineering in the areas of fiber and cable technologies; active and passive guided-wave componentry (light sources, detectors, repeaters, switches, fiber sensors, etc.); integrated optics and optoelectronics; systems and subsystems; new applications; and unique field trials.


Magnetics, IEEE Transactions on

Science and technology related to the basic physics and engineering of magnetism, magnetic materials, applied magnetics, magnetic devices, and magnetic data storage. The Transactions publishes scholarly articles of archival value as well as tutorial expositions and critical reviews of classical subjects and topics of current interest.


Nuclear Science, IEEE Transactions on

All aspects of the theory and applications of nuclear science and engineering, including instrumentation for the detection and measurement of ionizing radiation; particle accelerators and their controls; nuclear medicine and its application; effects of radiation on materials, components, and systems; reactor instrumentation and controls; and measurement of radiation in space.


Plasma Science, IEEE Transactions on

Plasma science and engineering, including: magnetofluid dynamics and thermionics; plasma dynamics; gaseous electronics and arc technology; controlled thermonuclear fusion; electron, ion, and plasma sources; space plasmas; high-current relativistic electron beams; laser-plasma interactions; diagnostics; plasma chemistry and colloidal and solid-state plasmas.


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Most published Xplore authors for Inertial Confinement

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Xplore Articles related to Inertial Confinement

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Monochromatic 6.151-keV Radiographs of a Highly Unstable Inertial Confinement Fusion Capsule Implosion

IEEE Transactions on Plasma Science, 2011

Monochromatic 6.151-keV radiographs of a highly unstable inertial confinement fusion capsule are shown. The capsule was driven by a 70-eV peak radiation temperature and exhibits numerous small-scale features down to the resolution of the backlighting diagnostic (about 15 μm ). The capsule experiment was done using the double-ended_Z_-pinch-driven hohlraum on the Sandia Z facility.


Intense ion beams for inertial confinement fusion

IEEE Transactions on Plasma Science, 1997

Intense beams of light and heavy ions are being studied as inertial confinement fusion (ICF) drivers for high yield and energy. Heavy and light ions have common interests in beam transport, targets, and alternative accelerators. Self-pinched transport is being jointly studied. This article reviews the development of intense ion beams for ICF. Light-ion drivers are highlighted because they are compact, ...


Target fabrication for inertial confinement fusion and fast ignition

The 30th International Conference on Plasma Science, 2003. ICOPS 2003. IEEE Conference Record - Abstracts., 2003

Summary form only given, as follows. Direct-drive inertial confinement fusion (ICF) offers the potential for high gain and is a leading candidate for an inertial fusion-energy power plant. Laser and target nonuniformities can seed hydrodynamic instabilities during the implosion that, in turn, can compromise target performance. This is the primary target physics issue for direct-drive ICF. Several methods have been ...


Welter weight ion transport for diode generated ion beam inertial confinement fusion

International Conference on Plasma Science (papers in summary form only received), 1995

Summary form only given. The choice of ion species for ion beam inertial confinement fusion is driven by target design, ion beam transport and beam generation. An important question is whether heavy and light ion technologies and be extended into the welter weight regime of intermediate atomic weight. The target defines the total energy in the ion beams, the number ...


The National Ignition Facility for inertial confinement fusion

17th IEEE/NPSS Symposium Fusion Engineering (Cat. No.97CH36131), 1997

The National Ignition Facility for inertial confinement fusion will contain a 1.8 MJ, 500 TW frequency-tripled Ne glass laser system that will be used to explore fusion ignition and other problems in the physics of high temperature and density. We describe the facility briefly. The NIF is scheduled to be completed in 2003.


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Educational Resources on Inertial Confinement

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IEEE-USA E-Books

  • Monochromatic 6.151-keV Radiographs of a Highly Unstable Inertial Confinement Fusion Capsule Implosion

    Monochromatic 6.151-keV radiographs of a highly unstable inertial confinement fusion capsule are shown. The capsule was driven by a 70-eV peak radiation temperature and exhibits numerous small-scale features down to the resolution of the backlighting diagnostic (about 15 μm ). The capsule experiment was done using the double-ended_Z_-pinch-driven hohlraum on the Sandia Z facility.

  • Intense ion beams for inertial confinement fusion

    Intense beams of light and heavy ions are being studied as inertial confinement fusion (ICF) drivers for high yield and energy. Heavy and light ions have common interests in beam transport, targets, and alternative accelerators. Self-pinched transport is being jointly studied. This article reviews the development of intense ion beams for ICF. Light-ion drivers are highlighted because they are compact, modular, efficient and low cost. Issues facing light ions are: (1) decreasing beam divergence; (2) increasing beam brightness; and (3) demonstrating self-pinched transport. Applied-B ion diodes are favored because of efficiency, beam brightness, perceived scalability, achievable focal intensity, and multistage capability. A light-ion concept addressing these issues uses: (1) an injector divergence of /spl les/24 mrad at 9 MeV; (2) two-stage acceleration to reduce divergence to /spl les/12 mrad at 35 MeV; and (3) self-pinched transport accepting divergences up to 12 mrad. Substantial progress in ion-driven target physics and repetitive ion diode technology is also presented. Z-pinch drivers are being pursued as the shortest pulsed power path to target physics experiments and high-yield fusion. However, light ions remain the pulsed power ICF driver of choice for high-yield fusion energy applications that require driver standoff and repetitive operation.

  • Target fabrication for inertial confinement fusion and fast ignition

    Summary form only given, as follows. Direct-drive inertial confinement fusion (ICF) offers the potential for high gain and is a leading candidate for an inertial fusion-energy power plant. Laser and target nonuniformities can seed hydrodynamic instabilities during the implosion that, in turn, can compromise target performance. This is the primary target physics issue for direct-drive ICF. Several methods have been devised to control these seeds and their subsequent growth, including laser beam smoothing, advanced pulse shaping, target design, etc. LLE's baseline direct-drive ignition design for the National Ignition Facility (presently under construction at the Lawrence Livermore National Laboratory) is composed of a thin (3-/spl mu/m) plastic shell enclosing a thick (350-/spl mu/m) deuterium-tritium (DT)-ice layer. It provides a gain of 45 in spherically symmetric calculations (30 m two- dimensional simulations which include the effects of laser and target nonuniformities). Recent improvements to the ignition target design include the addition of a picket to the beginning of the laser pulse shape that reduces both the seeds and growth rate of the hydrodynamic instabilities Experiments performed on the 60-beam, 30-kJ UV OMEGA laser on warm and cryogenic targets are diagnosed using X-rays and nuclear particles. Significant improvements in warm capsule implosion target performance have been observed with improvements in beam smoothing on OMEGA.

  • Welter weight ion transport for diode generated ion beam inertial confinement fusion

    Summary form only given. The choice of ion species for ion beam inertial confinement fusion is driven by target design, ion beam transport and beam generation. An important question is whether heavy and light ion technologies and be extended into the welter weight regime of intermediate atomic weight. The target defines the total energy in the ion beams, the number of beams, and the temporal shape of the beams. Of the several possible methods of ion beam transport, self-pinched propagation is potentially the most attractive. This mode requires that the beam current is only partially neutralized by a background gas and uses the net current to generate a confining azimuthal magnetic field. The net current required is determined by the diode design. A formalism for comparing the beam generation and propagation has been constructed from known relations. Beam ions from Li to Cs are compared within this formalism. As the beam ion atomic number and energy increase, the anode surfaces in the diodes become smaller and the required neutralization fraction decreases. Higher than some atomic mass, the combined use of magnetically insulated diodes and self-pinched transport is no longer a useful concept and ion beam generation with a linear accelerator might be more attractive.

  • The National Ignition Facility for inertial confinement fusion

    The National Ignition Facility for inertial confinement fusion will contain a 1.8 MJ, 500 TW frequency-tripled Ne glass laser system that will be used to explore fusion ignition and other problems in the physics of high temperature and density. We describe the facility briefly. The NIF is scheduled to be completed in 2003.

  • Inertial confinement fusion target insertion via augmented mass free fall

    A critical concern in the fabrication of targets for inertial confinement fusion (ICF) is ensuring that the hydrogenic (D/sub 2/ or DT) fuel layer maintains spherical symmetry. Solid layered targets have structural integrity, but lack the needed surface smoothness. Liquid targets are inherently smooth, but suffer from gravitationally induced sagging. One method to reduce the effective gravitational field environment is freefall insertion into the target chamber. Calculations of London-Van der Waals forces between liquid deuterium and plastic indicate that the maximum thickness of the equilibrium liquid layer in reduced gravitational environments is dependent on the net gravitational acceleration. Deceleration from gas drag limits the effective gravitational acceleration to >10/sup -6/ g thus restricting the symmetric fuel layer thickness to 3 /spl mu/m. We show that augmented mass methods (mounting the target to a high density mass) can further reduce the net acceleration, increasing the permissible thickness of the symmetric liquid layer.

  • Inertial confinement fusion using the OMEGA laser

    Summary form only given. The OMEGA/OMEGA EP Laser System is being used to study a variety of approaches to direct-drive inertial confinement fusion-the traditional central hot-spot (CHS) approach, fast ignition (FI), and shock ignition (SI). To achieve ignition, CHS requires the highly uniform compression of a solid deuterium-tritium (DT) layered target on a low-adiabat (defined as the ratio of the pressure to the Fermi-degenerate pressure) and with an implosion velocity, v > 3.5 × 107cm/s. A laser-pulse shape with multiple pickets produces this low adiabat. The timing of multiple shocks launched by the pickets and the main laser pulse is optimized in experiments using cone-in-shell geometry. Cryogenic targets imploded with optimally timed, low-adiabat multiple-picket pulses have demonstrated near 1-D compression with an areal density, ρR = 290 mg/cm2, at v = 3.1 × 107cm/s. These are by far the highest DT areal densities demonstrated in the laboratory. FI and SI relax energy and uniformity requirements on the compression laser by separating fuel assembly from ignition. Integrated FI experiments have been performed on the OMEGA/OMEGA EP Laser System. A 10-ps, 1-kJ OMEGA EP beam is pointed into the tip of a gold cone inserted into a thick plastic converging and compressing shell. The neutron yield increased by more than a factor of 2 when the OMEGA EP beam was optimally delayed, indicating ~10% conversion efficiency from laser energy to core heating. Shock-ignition experiments, where a shock is launched by a picket at the end of the laser pulse into the compressing capsule, have been performed on low-adiabat warm plastic targets. Both yield and areal density improve significantly when a spike is used at the end of the laser pulse, indicating that energy from the shock is coupled into the compressing target. This talk will discuss these results, compare them to simulations, and identify future work necessary to demonstrate ignition relevance for all these schemes.

  • The petawatt laser and its application to inertial confinement fusion

    Summary form only given. A project to develop a 1000 TW (petawatt) class laser began in 1992 in order to provide the capability to examine the fast ignitor concept for inertial confinement fusion (ICF). The laser was designed to produce 1 kilojoule pulses with a duration less than 500 fsec and be focusable to a high irradiance. Near-diffraction-limited beams require large-scale pulse compression and sophisticated adaptive optics. Metallic gratings are capable of compressing near 1 kT pulses.

  • Cluster ion beam polishing for inertial confinement fusion target capsules

    Targets for Inertial Confinement Fusion (ICF) typically consist of a hollow, spherical capsule filled with a mixture of hydrogen isotopes. Typically, these capsules are irradiated by short, intense pulses of either laser light ("direct drive") or laser-generated X-rays ("indirect drive"), causing them to implode. This compresses and heats the fuel, leading to thermonuclear fusion. This process is highly sensitive to hydrodynamic (e.g., Rayleigh-Taylor) instabilities, which can be initiated by imperfections in the target. Thus, target capsules must be extremely spherical and smooth. One of the lead capsule designs for the National Ignition Facility, a 1.8 MJ laser being built at Livermore, calls for a 2-mm-diam capsule with a 150-/spl mu/m-thick copper- doped beryllium wall. These capsules can be fabricated by sputter depositing the metal onto a spherical plastic mandrel. This results in surfaces with measured R/sub q/'s of 50 to 150 nm, as measured with an atomic force microscope. For optimal performance the roughness should be below 10 nm rms. We have begun studying the use of ion cluster beam polishing as a means of improving the surface finish of as-deposited capsules. In this approach, a batch of capsules would be agitated in a bounce pan inside a vacuum chamber during exposure to the cluster beam. This would ensure a uniform beam dose around the capsule. We have performed preliminary experiments on both Be flats and on a stationary Be capsule. On the capsule, the measured R/sub q/ went from 64 nm before polishing to 15 nn after. This result was obtained without any effort at process optimization. Similar smoothing was observed on the planar samples.

  • High-gain inertial confinement fusion by volume ignition, avoiding the complexities of fusion detonation fronts of spark ignition

    Summary form only given, as follows. The main approach to inertial confinement fusion (ICF) uses a high-temperature, low-density core and a high-density, low-temperature outer region of the laser(or ion beam-) compressed deuterium- tritium (D-T) fuel, in order to ignite a fusion detonation wave at the interface. This is an extremely delicate, unstable configuration which is very difficult to achieve, even with a carefully programmed time dependence of the deposition of the driver energy. This approach was devised in order to reach the high gains needed for low-efficiency lasers. Since 1978, several teams have developed an alternative scheme using volume ignition, where a natural and simple adiabatic compression, starting from a low initial temperature of 3 keV or less, is used. The high gains are obtained by self-heating due to the fusion reaction products plus self-absorption of Bremsstrahlung. Fortunately, a strong deviation from LTE occurs at ion temperatures above 100 keV, with much lower electron and even lower radiation temperatures. We report here how the gains calculated by different groups are relatively large, and despite detailed differences in the stopping power models, do not differ greatly.



Standards related to Inertial Confinement

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Jobs related to Inertial Confinement

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