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Dive into the research topics where C. R. Gibson is active.

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Featured researches published by C. R. Gibson.


Physics of Plasmas | 2012

Shock timing experiments on the National Ignition Facility: Initial results and comparison with simulation

H. F. Robey; T. R. Boehly; Peter M. Celliers; Jon H. Eggert; Damien G. Hicks; R.F. Smith; R. Collins; M. W. Bowers; K. Krauter; P. S. Datte; D. H. Munro; J. L. Milovich; O. S. Jones; P. Michel; C. A. Thomas; R.E. Olson; Stephen M. Pollaine; R. P. J. Town; S. W. Haan; D. A. Callahan; D. S. Clark; J. Edwards; J. L. Kline; S. N. Dixit; M. B. Schneider; E. L. Dewald; K. Widmann; J. D. Moody; T. Döppner; H.B. Radousky

Capsule implosions on the National Ignition Facility (NIF) [Lindl et al., Phys. Plasmas 11, 339 (2004)] are underway with the goal of compressing deuterium-tritium (DT) fuel to a sufficiently high areal density (ρR) to sustain a self-propagating burn wave required for fusion power gain greater than unity. These implosions are driven with a carefully tailored sequence of four shock waves that must be timed to very high precision in order to keep the DT fuel on a low adiabat. Initial experiments to measure the strength and relative timing of these shocks have been conducted on NIF in a specially designed surrogate target platform known as the keyhole target. This target geometry and the associated diagnostics are described in detail. The initial data are presented and compared with numerical simulations. As the primary goal of these experiments is to assess and minimize the adiabat in related DT implosions, a methodology is described for quantifying the adiabat from the shock velocity measurements. Results ...


Nuclear Fusion | 2004

A cost-effective target supply for inertial fusion energy

D. T. Goodin; N.B. Alexander; L.C. Brown; D.T. Frey; R. Gallix; C. R. Gibson; J.L. Maxwell; A. Nobile; C.L. Olson; R. Raffray; Gary Eugene Rochau; D. G. Schroen; M. S. Tillack; W.S. Rickman; B. A. Vermillion

A central feature of an inertial fusion energy (IFE) power plant is a target that has been compressed and heated to fusion conditions by the energy input of the driver. This is true whether the driver is a laser system, heavy ion beams or Z-pinch system. The IFE target fabrication, injection and tracking programmes are focusing on methods that will scale to mass production. We are working closely with target designers, and power plant systems specialists, to make specifications and material selections that will satisfy a wide range of required and desirable target characteristics. One-of-a-kind capsules produced for today’s inertial confinement fusion experiments are estimated to cost about US


Fusion Science and Technology | 2009

Design of the NIF Cryogenic Target System

C. R. Gibson; D. P. Atkinson; J. A. Baltz; V. P. Brugman; F. E. Coffield; O. D. Edwards; Benjamin Haid; S. F. Locke; T. N. Malsbury; S. J. Shiromizu; K. M. Skulina

2500 each. Design studies of cost-effective power production from laser and heavy-ion driven IFE have suggested a cost goal of about


Fusion Science and Technology | 2005

Demonstrating a Target Supply for Inertial Fusion Energy

D. T. Goodin; N.B. Alexander; L.C. Brown; D. A. Callahan; Peter S. Ebey; D.T. Frey; R. Gallix; Drew A. Geller; C. R. Gibson; James K. Hoffer; J.L. Maxwell; Barry McQuillan; A. Nikroo; A. Nobile; C.L. Olson; R. Raffray; W.S. Rickman; Gary Eugene Rochau; D. G. Schroen; J. D. Sethian; John D. Sheliak; J. Streit; M. S. Tillack; B. A. Vermillion; E.I. Valmianski

0.25–0.30 for each injected target (corresponding to ∼10% of the ‘electricity value’ in a target). While a four orders of magnitude cost reduction may seem at first to be nearly impossible, there are many factors that suggest this is achievable. This paper summarizes the design, specifications, requirements and proposed manufacturing processes for the future for laser fusion, heavy ion fusion and Z-pinch driven targets. These target manufacturing processes have been developed—and are proposed—based on the unique materials science and technology programmes that are ongoing for each of the target concepts. We describe the paradigm shifts in target manufacturing methodologies that will be needed to achieve orders of magnitude reductions in target costs, and summarize the results of ‘nth-of-a-kind’ plant layouts and cost estimates for future IFE power plant fuelling. These engineering studies estimate the cost of the target supply in a fusion economy, and show that costs are within the range of commercial feasibility for electricity production.


Fusion Science and Technology | 2009

Measurement of Total Condensation on a Shrouded Cryogenic Surface Using a Single Quartz Crystal Microbalance

Benjamin Haid; T. N. Malsbury; C. R. Gibson; C. T. Warren

Abstract The U.S. Department of Energy has embarked on a campaign to conduct credible fusion ignition experiments on the National Ignition Facility (NIF) at the Lawrence Livermore National Laboratory in 2010. The target assembly specified for this campaign requires the formation of a deuterium-tritium fuel ice layer in a 2-mm-diam capsule at the center of a 9-mm-long × 5-mm-diam cylinder, called a hohlraum. The ice layer must be formed and maintained at temperatures below 20 K. At laser shot time, the target is positioned at the center of the NIF target chamber, aligned to the laser beams, and held stable to <7-μm root-mean-square. We have completed the final design of the cryogenic target system and are currently integrating the devices necessary to create, characterize, and position the cryogenic target for ignition experiments.


Fusion Science and Technology | 2016

A Flexure-Based Mechanism for Precision Adjustment of National Ignition Facility Target Shrouds in Three Rotational Degrees of Freedom

Kurt Boehm; C. R. Gibson; J. R. Hollaway; Francisco Espinosa-Loza

Abstract A central feature of an Inertial Fusion Energy (IFE) power plant is a target that has been compressed and heated to fusion conditions by the energy input of the driver. The technology to economically manufacture and then position cryogenic targets at chamber center is at the heart of future IFE power plants. For direct drive IFE (laser fusion), energy is applied directly to the surface of a spherical CH polymer capsule containing the deuterium-tritium (DT) fusion fuel at approximately 18K. For indirect drive (heavy ion fusion, HIF), the target consists of a similar fuel capsule within a cylindrical metal container or ’’hohlraum’’ which converts the incident driver energy into x-rays to implode the capsule. For either target, it must be accurately delivered to the target chamber center at a rate of about 5-10Hz, with a precisely predicted target location. Future successful fabrication and injection systems must operate at the low cost required for energy production (about


Fusion Science and Technology | 2018

The National Direct-Drive Program: OMEGA to the National Ignition Facility

S. P. Regan; V.N. Goncharov; T. C. Sangster; E. M. Campbell; R. Betti; Karen S. Anderson; T. Bernat; Arijit Bose; T. R. Boehly; M. J. Bonino; D. Cao; R. Chapman; T.J.B. Collins; R. S. Craxton; A. K. Davis; J. A. Delettrez; D. H. Edgell; R. Epstein; M. Farrell; C.J. Forrest; J. A. Frenje; D. H. Froula; M. Gatu Johnson; C. R. Gibson; V. Yu. Glebov; A. L. Greenwood; D. R. Harding; M. Hohenberger; S. X. Hu; H. Huang

0.25/target, about 104 less than current costs). Z-pinch driven IFE (ZFE) utilizes high current pulses to compress plasma to produce x-rays that indirectly heat a fusion capsule. ZFE target technologies utilize a repetition rate of about 0.1 Hz with a higher yield. This paper provides an overview of the proposed target methodologies for laser fusion, HIF, and ZFE, and summarizes advances in the unique materials science and technology development programs.


Nuclear Fusion | 2001

Developing target injection and tracking for inertial fusion energy power plants

D. T. Goodin; N.B. Alexander; C. R. Gibson; A. Nobile; Nathan P. Siegel; L. Thompson

Abstract A single quartz crystal microbalance (QCM) is cooled to 18 K to measure condensation rates inside of a retractable shroud enclosure. The shroud is designed to minimize condensate on fusion targets to be fielded at the National Ignition Facility (NIF). The shroud has a double-walled construction with an inner wall that may be cooled to 75 to 100 K. The QCM and the shroud system were mounted in a vacuum chamber and cooled using a cryocooler. Condensation rates were measured at various vacuum levels and compositions and with the shroud open or closed. A technique for measuring total condensate during the cooldown of the system with an accuracy of >1 × 10-6 g/cm2 was also demonstrated. The technique involves a separate measurement of the condensate-free crystal frequency as a function of temperature that is compared to the measurement for the cooldown trend of interest. The shroud significantly reduces the condensation rates of all gases and effectively eliminates H2O condensation.


Presented at: 7th International Conference on Inertial Fusion Sciences and Applications, Bordeaux, France, Sep 12 - Sep 16, 2011 | 2011

Shock timing on the National Ignition Facility: First Experiments

Peter M. Celliers; H. F. Robey; T. R. Boehly; E. T. Alger; S. Azevedo; L. V. Berzins; S. D. Bhandarkar; M. W. Bowers; S.J. Brereton; D. A. Callahan; C. Castro; H. Chandrasekaran; C. Choate; D. S. Clark; K.R. Coffee; P. S. Datte; E. L. Dewald; P. DiNicola; S. N. Dixit; T. Doeppner; E. G. Dzenitis; M. J. Edwards; Jon H. Eggert; J. Fair; D. R. Farley; G. Frieders; C. R. Gibson; E. Giraldez; S. W. Haan; B. J. Haid

Abstract This paper presents the design of a flexure-based mount allowing adjustment in three rotational degrees of freedom (DOFs) through high-precision set-screw actuators. The requirements of the application called for small but controlled angular adjustments for mounting a cantilevered beam. The proposed design is based on an array of parallel beams to provide sufficiently high stiffness in the translational directions while allowing angular adjustment through the actuators. A simplified physical model in combination with standard beam theory was applied to estimate the deflection profile and maximum stresses in the beams. A finite element model was built to calculate the stresses and beam profiles for scenarios in which the flexure is simultaneously actuated in more than one DOF.


IAEA Technical Committee Meeting | 2002

Developing the basis for target injection and tracking in inertial fusion energy power plants

D. T. Goodin; C. R. Gibson; Nathan P. Siegel; Larry D. Thompson; A. Nobile; G. E. Besenbruch; K.R. Schultz

Abstract The goal of the National Direct-Drive Program is to demonstrate and understand the physics of laser direct drive (LDD). Efforts are underway on OMEGA for the 100-Gbar Campaign to demonstrate and understand the physics for hot-spot conditions and formation relevant for ignition at the 1-MJ scale, and on the National Ignition Facility to develop an understanding of the direct-drive physics at long scale lengths for the MJ Direct-Drive Campaign. The strategy of the National Direct-Drive Program is described; the requirements for the deuterium-tritium cryogenic fill-tube target being developed for OMEGA are presented; and preliminary LDD implosion measurements of hydrodynamic mixing seeded by laser imprint, the target-mounting stalk, and microscopic surface debris are reported.

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A. Nobile

Los Alamos National Laboratory

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D. A. Callahan

Lawrence Livermore National Laboratory

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T. R. Boehly

University of Rochester

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Benjamin Haid

Massachusetts Institute of Technology

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C.L. Olson

Sandia National Laboratories

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D. S. Clark

Lawrence Livermore National Laboratory

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