Laser Fusion

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Jeffery F Latkowski - One of the best experts on this subject based on the ideXlab platform.

  • systems modeling for the Laser Fusion fission energy life power plant
    Fusion Science and Technology, 2009
    Co-Authors: W R Meier, Ryan P Abbott, R J Beach, James A Blink, J A Caird, A C Erlandson, Joseph C Farmer, W Halsey, T Ladran, Jeffery F Latkowski
    Abstract:

    A systems model has been developed for the Laser Inertial Fusion-Fission Energy (LIFE) power plant. It combines cost-performance scaling models for the major subsystems of the plant including the l...

  • systems modeling for the Laser Fusion fission energy life power plant
    Fusion Science and Technology, 2009
    Co-Authors: W R Meier, Ryan P Abbott, R J Beach, James A Blink, J A Caird, A C Erlandson, Joseph C Farmer, W Halsey, T Ladran, Jeffery F Latkowski
    Abstract:

    AbstractA systems model has been developed for the Laser Inertial Fusion-Fission Energy (LIFE) power plant. It combines cost-performance scaling models for the major subsystems of the plant including the Laser, inertial Fusion target factory, engine (i.e., the chamber including the fission and tritium breeding blankets), energy conversion systems and balance of plant. The LIFE plant model is being used to evaluate design trade-offs and to identify high-leverage R&D. At this point, we are focused more on doing self consistent design trades and optimization as opposed to trying to predict a cost of electricity with a high degree of certainty. Key results show the advantage of large scale (>1000 MWe) plants and the importance of minimizing the cost of diodes and balance of plant cost.

  • an overview of the development of the first wall and other principal components of a Laser Fusion power plant
    Journal of Nuclear Materials, 2005
    Co-Authors: J D Sethian, Rene A Raffray, Jeffery F Latkowski, James P Blanchard, L L Snead, Timothy J Renk, S Sharafat
    Abstract:

    This paper introduces the JNM Special Issue on the development of a first wall for the reaction chamber in a Laser Fusion power plant. In this approach to Fusion energy a spherical target is injected into a large chamber and heated to Fusion burn by an array of Lasers. The target emissions are absorbed by the wall and encapsulating blanket, and the resulting heat converted into electricity. The bulk of the energy deposited in the first wall is in the form of X-rays (1.0–100 keV) and ions (0.1–4 MeV). In order to have a practical power plant, the first wall must be resistant to these emissions and suffer virtually no erosion on each shot. A wall candidate based on tungsten armor bonded to a low activation ferritic steel substrate has been chosen as the initial system to be studied. The choice was based on the vast experience with these materials in a nuclear environment and the ability to address most of the key remaining issues with existing facilities. This overview paper is divided into three parts. The first part summarizes the current state of the development of Laser Fusion energy. The second part introduces the tungsten armored ferritic steel concept, the three critical development issues (thermo-mechanical fatigue, helium retention, and bonding) and the research to address them. Based on progress to date the latter two appear to be resolvable, but the former remains a challenge. Complete details are presented in the companion papers in this JNM Special Issue. The third part discusses other factors that must be considered in the design of the first wall, including compatibility with blanket concepts, radiological concerns, and structural considerations. Published by Elsevier B.V.

A J Schmitt - One of the best experts on this subject based on the ideXlab platform.

  • Laser requirements for a Laser Fusion energy power plant
    High Power Laser Science and Engineering, 2013
    Co-Authors: S E Bodner, A J Schmitt, J D Sethian
    Abstract:

    We will review some of the requirements for a Laser that would be used with a Laser Fusion energy power plant, including frequency, spatial beam smoothing, bandwidth, temporal pulse shaping, efficiency, repetition rate, and reliability. The lowest risk and optimum approach uses a krypton fluoride gas Laser. A diode-pumped solid-state Laser is a possible contender.

  • enhanced direct drive implosions with thin high z ablation layers
    Physical Review Letters, 2008
    Co-Authors: A N Mostovych, Max Karasik, D G Colombant, A J Schmitt, James Knauer, J Weaver
    Abstract:

    New direct-drive spherical implosion experiments with deuterium filled plastic shells have demonstrated significant and absolute ($2\text{\hskip-0.22em}\ifmmode\times\else\texttimes\fi{}$) improvements in neutron yield when the shells are coated with a very thin layer ($\ensuremath{\sim}200\char21{}400\text{ }\text{ }\AA{}$) of high-$Z$ material such as palladium. This improvement is interpreted as resulting from increased stability of the imploding shell. These results provide for a possible path to control Laser imprint and stability in Laser-Fusion-energy target designs.

  • high gain direct drive target design for Laser Fusion
    Physics of Plasmas, 2000
    Co-Authors: S E Bodner, D G Colombant, A J Schmitt, M Klapisch
    Abstract:

    A new Laser Fusion target concept is presented with a predicted energy gain of 127 using a 1.3 MJ KrF Laser. This energy gain is sufficiently high for an economically attractive Fusion reactor. X rays from high- and low-Z materials are used in combination with a low-opacity ablator to spatially tune the isentrope, thereby providing both high fuel compression and a reduction of the ablative Rayleigh–Taylor instability.

  • direct drive Laser Fusion status and prospects
    Physics of Plasmas, 1998
    Co-Authors: S E Bodner, J D Sethian, Stephen P Obenschain, R H Lehmberg, D G Colombant, A J Schmitt, John H Gardner, Lee Phillips, R L Mccrory, W Seka
    Abstract:

    Techniques have been developed to improve the uniformity of the Laser focal profile, to reduce the ablative Rayleigh–Taylor instability, and to suppress the various Laser–plasma instabilities. There are now three direct-drive ignition target designs that utilize these techniques. An evaluation of these designs is still ongoing. Some of them may achieve the gains above 100 that are necessary for a Fusion reactor. Two Laser systems have been proposed that may meet all of the requirements for a Fusion reactor.

S E Bodner - One of the best experts on this subject based on the ideXlab platform.

  • Laser requirements for a Laser Fusion energy power plant
    High Power Laser Science and Engineering, 2013
    Co-Authors: S E Bodner, A J Schmitt, J D Sethian
    Abstract:

    We will review some of the requirements for a Laser that would be used with a Laser Fusion energy power plant, including frequency, spatial beam smoothing, bandwidth, temporal pulse shaping, efficiency, repetition rate, and reliability. The lowest risk and optimum approach uses a krypton fluoride gas Laser. A diode-pumped solid-state Laser is a possible contender.

  • high gain direct drive target design for Laser Fusion
    Physics of Plasmas, 2000
    Co-Authors: S E Bodner, D G Colombant, A J Schmitt, M Klapisch
    Abstract:

    A new Laser Fusion target concept is presented with a predicted energy gain of 127 using a 1.3 MJ KrF Laser. This energy gain is sufficiently high for an economically attractive Fusion reactor. X rays from high- and low-Z materials are used in combination with a low-opacity ablator to spatially tune the isentrope, thereby providing both high fuel compression and a reduction of the ablative Rayleigh–Taylor instability.

  • direct drive Laser Fusion status and prospects
    Physics of Plasmas, 1998
    Co-Authors: S E Bodner, J D Sethian, Stephen P Obenschain, R H Lehmberg, D G Colombant, A J Schmitt, John H Gardner, Lee Phillips, R L Mccrory, W Seka
    Abstract:

    Techniques have been developed to improve the uniformity of the Laser focal profile, to reduce the ablative Rayleigh–Taylor instability, and to suppress the various Laser–plasma instabilities. There are now three direct-drive ignition target designs that utilize these techniques. An evaluation of these designs is still ongoing. Some of them may achieve the gains above 100 that are necessary for a Fusion reactor. Two Laser systems have been proposed that may meet all of the requirements for a Fusion reactor.

J D Sethian - One of the best experts on this subject based on the ideXlab platform.

  • high energy krypton fluoride Lasers for inertial Fusion
    Applied Optics, 2015
    Co-Authors: Stephen P Obenschain, M F Wolford, J D Sethian, F Hegeler, R H Lehmberg, D Kehne, J Weaver, Max Karasik
    Abstract:

    Laser Fusion researchers have realized since the 1970s that the deep UV light from excimer Lasers would be an advantage as a driver for robust high-performance capsule implosions for inertial confinement Fusion (ICF). Most of this research has centered on the krypton-fluoride (KrF) Laser. In this article we review the advantages of the KrF Laser for direct-drive ICF, the history of high-energy KrF Laser development, and the present state of the art and describe a development path to the performance needed for Laser Fusion and its energy application. We include descriptions of the architecture and performance of the multi-kilojoule Nike KrF Laser-target facility and the 700 J Electra high-repetition-rate KrF Laser that were developed at the U.S. Naval Research Laboratory. Nike and Electra are the most advanced KrF Lasers for inertial Fusion research and energy applications.

  • Laser requirements for a Laser Fusion energy power plant
    High Power Laser Science and Engineering, 2013
    Co-Authors: S E Bodner, A J Schmitt, J D Sethian
    Abstract:

    We will review some of the requirements for a Laser that would be used with a Laser Fusion energy power plant, including frequency, spatial beam smoothing, bandwidth, temporal pulse shaping, efficiency, repetition rate, and reliability. The lowest risk and optimum approach uses a krypton fluoride gas Laser. A diode-pumped solid-state Laser is a possible contender.

  • conceptual study of integrated chamber core for Laser Fusion with magnetic intervention
    IEEE Symposium on Fusion Engineering, 2007
    Co-Authors: A R Raffray, J D Sethian, L L Snead, F Dahlgren, C Gentile, C Priniski, A E Robson, D V Rose, M E Sawan, G Sviatoslavsky
    Abstract:

    The possibility of utilizing magnetic intervention (MI) in a Laser-driven inertial Fusion energy (IFE) dry wall chamber is being considered to steer away the ions from the chamber wall to more readily accessible and replaceable dump regions at the equator and poles. This paper summarizes the current status of this study, describing the overall MI chamber core configuration and layout and highlighting the key design and analysis results for the different components.

  • an overview of the development of the first wall and other principal components of a Laser Fusion power plant
    Journal of Nuclear Materials, 2005
    Co-Authors: J D Sethian, Rene A Raffray, Jeffery F Latkowski, James P Blanchard, L L Snead, Timothy J Renk, S Sharafat
    Abstract:

    This paper introduces the JNM Special Issue on the development of a first wall for the reaction chamber in a Laser Fusion power plant. In this approach to Fusion energy a spherical target is injected into a large chamber and heated to Fusion burn by an array of Lasers. The target emissions are absorbed by the wall and encapsulating blanket, and the resulting heat converted into electricity. The bulk of the energy deposited in the first wall is in the form of X-rays (1.0–100 keV) and ions (0.1–4 MeV). In order to have a practical power plant, the first wall must be resistant to these emissions and suffer virtually no erosion on each shot. A wall candidate based on tungsten armor bonded to a low activation ferritic steel substrate has been chosen as the initial system to be studied. The choice was based on the vast experience with these materials in a nuclear environment and the ability to address most of the key remaining issues with existing facilities. This overview paper is divided into three parts. The first part summarizes the current state of the development of Laser Fusion energy. The second part introduces the tungsten armored ferritic steel concept, the three critical development issues (thermo-mechanical fatigue, helium retention, and bonding) and the research to address them. Based on progress to date the latter two appear to be resolvable, but the former remains a challenge. Complete details are presented in the companion papers in this JNM Special Issue. The third part discusses other factors that must be considered in the design of the first wall, including compatibility with blanket concepts, radiological concerns, and structural considerations. Published by Elsevier B.V.

  • direct drive Laser Fusion status and prospects
    Physics of Plasmas, 1998
    Co-Authors: S E Bodner, J D Sethian, Stephen P Obenschain, R H Lehmberg, D G Colombant, A J Schmitt, John H Gardner, Lee Phillips, R L Mccrory, W Seka
    Abstract:

    Techniques have been developed to improve the uniformity of the Laser focal profile, to reduce the ablative Rayleigh–Taylor instability, and to suppress the various Laser–plasma instabilities. There are now three direct-drive ignition target designs that utilize these techniques. An evaluation of these designs is still ongoing. Some of them may achieve the gains above 100 that are necessary for a Fusion reactor. Two Laser systems have been proposed that may meet all of the requirements for a Fusion reactor.

D G Colombant - One of the best experts on this subject based on the ideXlab platform.

  • enhanced direct drive implosions with thin high z ablation layers
    Physical Review Letters, 2008
    Co-Authors: A N Mostovych, Max Karasik, D G Colombant, A J Schmitt, James Knauer, J Weaver
    Abstract:

    New direct-drive spherical implosion experiments with deuterium filled plastic shells have demonstrated significant and absolute ($2\text{\hskip-0.22em}\ifmmode\times\else\texttimes\fi{}$) improvements in neutron yield when the shells are coated with a very thin layer ($\ensuremath{\sim}200\char21{}400\text{ }\text{ }\AA{}$) of high-$Z$ material such as palladium. This improvement is interpreted as resulting from increased stability of the imploding shell. These results provide for a possible path to control Laser imprint and stability in Laser-Fusion-energy target designs.

  • high gain direct drive target design for Laser Fusion
    Physics of Plasmas, 2000
    Co-Authors: S E Bodner, D G Colombant, A J Schmitt, M Klapisch
    Abstract:

    A new Laser Fusion target concept is presented with a predicted energy gain of 127 using a 1.3 MJ KrF Laser. This energy gain is sufficiently high for an economically attractive Fusion reactor. X rays from high- and low-Z materials are used in combination with a low-opacity ablator to spatially tune the isentrope, thereby providing both high fuel compression and a reduction of the ablative Rayleigh–Taylor instability.

  • direct drive Laser Fusion status and prospects
    Physics of Plasmas, 1998
    Co-Authors: S E Bodner, J D Sethian, Stephen P Obenschain, R H Lehmberg, D G Colombant, A J Schmitt, John H Gardner, Lee Phillips, R L Mccrory, W Seka
    Abstract:

    Techniques have been developed to improve the uniformity of the Laser focal profile, to reduce the ablative Rayleigh–Taylor instability, and to suppress the various Laser–plasma instabilities. There are now three direct-drive ignition target designs that utilize these techniques. An evaluation of these designs is still ongoing. Some of them may achieve the gains above 100 that are necessary for a Fusion reactor. Two Laser systems have been proposed that may meet all of the requirements for a Fusion reactor.