Tritium Inventory of Inertial Fusion Energy Target Fabrication Facilities: Effect of Foam Density and Consideration of Target Yield of Direct Drive Targets

Schwendt, Ana M.; Nobile, A.; Gobby, P. L.; Steckle, Warren P.; Colombant, D.; Sethian, J. D.; Goodin, Dana; Besenbruch, G. E.

doi:10.13182/fst03-a262

Cited by 12 publications

(10 citation statements)

References 17 publications

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“…This means that the ultra-fine fuel layers have an adequate thermal and mechanical stability which supports the fuel layer survivability under target injection and transport through the reaction chamber. Additionally, such short layering times are also promising in terms of tritium inventory reduction in the target fabrication facilities [15].…”

Section: Discussion Of the Obtained Resultsmentioning

confidence: 99%

Estimation of the FST-Layering Time for Shock Ignition ICF Targets

Александрова

Koresheva

2022

Symmetry

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The challenge in the field of inertial confinement fusion (ICF) research is related to the study of alternative schemes for fuel ignition on laser systems of medium and megajoule scales. At the moment, it is considered promising to use the method of shock ignition of fuel in a pre-compressed cryogenic target using a focused shock wave (shock- or self-ignition (SI) mode). To confirm the applicability of this scheme to ICF, it is necessary to develop technologies for mass-fabrication of the corresponding targets with a spherically symmetric cryogenic layer (hereinafter referred to as SI-targets). These targets have a low initial aspect ratio Acl (Acl = 3 and Acl = 5) because they are expected to be more hydrodynamically stable during implosion. The paper discusses the preparation of SI-targets for laser experiments using the free-standing target (FST) layering method developed at the Lebedev Physical Institute (LPI). It is shown that, based on FST, it is possible to build a prototype layering module for in-line production of free-standing SI-targets, and the layering time, τform, does not exceed 30 s both for deuterium and deuterium-tritium fuel. Very short values of τform make it possible to obtain layers with a stable isotropic fuel structure to meet the requirements of implosion physics.

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Section: Discussion Of the Obtained Resultsmentioning

confidence: 99%

Estimation of the FST-Layering Time for Shock Ignition ICF Targets

Александрова

Koresheva

2022

Symmetry

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“…The tritium inventory of an IFE power plant has been estimated by Schwendt et al 895 to be less than 1 kg.…”

Section: Target Fabricationmentioning

confidence: 99%

Direct-drive inertial confinement fusion: A review

et al. 2015

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The direct-drive, laser-based approach to inertial confinement fusion (ICF) is reviewed from its inception following the demonstration of the first laser to its implementation on the present generation of high-power lasers. The review focuses on the evolution of scientific understanding gained from target-physics experiments in many areas, identifying problems that were demonstrated and the solutions implemented. The review starts with the basic understanding of laser–plasma interactions that was obtained before the declassification of laser-induced compression in the early 1970s and continues with the compression experiments using infrared lasers in the late 1970s that produced thermonuclear neutrons. The problem of suprathermal electrons and the target preheat that they caused, associated with the infrared laser wavelength, led to lasers being built after 1980 to operate at shorter wavelengths, especially 0.35 μm—the third harmonic of the Nd:glass laser—and 0.248 μm (the KrF gas laser). The main physics areas relevant to direct drive are reviewed. The primary absorption mechanism at short wavelengths is classical inverse bremsstrahlung. Nonuniformities imprinted on the target by laser irradiation have been addressed by the development of a number of beam-smoothing techniques and imprint-mitigation strategies. The effects of hydrodynamic instabilities are mitigated by a combination of imprint reduction and target designs that minimize the instability growth rates. Several coronal plasma physics processes are reviewed. The two-plasmon–decay instability, stimulated Brillouin scattering (together with cross-beam energy transfer), and (possibly) stimulated Raman scattering are identified as potential concerns, placing constraints on the laser intensities used in target designs, while other processes (self-focusing and filamentation, the parametric decay instability, and magnetic fields), once considered important, are now of lesser concern for mainline direct-drive target concepts. Filamentation is largely suppressed by beam smoothing. Thermal transport modeling, important to the interpretation of experiments and to target design, has been found to be nonlocal in nature. Advances in shock timing and equation-of-state measurements relevant to direct-drive ICF are reported. Room-temperature implosions have provided an increased understanding of the importance of stability and uniformity. The evolution of cryogenic implosion capabilities, leading to an extensive series carried out on the 60-beam OMEGA laser [Boehly et al., Opt. Commun. 133, 495 (1997)], is reviewed together with major advances in cryogenic target formation. A polar-drive concept has been developed that will enable direct-drive–ignition experiments to be performed on the National Ignition Facility [Haynam et al., Appl. Opt. 46(16), 3276 (2007)]. The advantages offered by the alternative approaches of fast ignition and shock ignition and the issues associated with these concepts are described. The lessons learned from target-physics and implosion experiments are taken into account in ignition and high-gain target designs for laser wavelengths of 1/3 μm and 1/4 μm. Substantial advances in direct-drive inertial fusion reactor concepts are reviewed. Overall, the progress in scientific understanding over the past five decades has been enormous, to the point that inertial fusion energy using direct drive shows significant promise as a future environmentally attractive energy source.

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“…12,13 Estimates of the DT filling (and layering) time and models to predict its effect on tritium inventory in the Target Fabrication Facility have been prepared. 14 The principal issue regarding permeation filling with DT is minimizing the tritium inventory "at risk", and thus maximizing the attractiveness of the power plant. Layering, 15,16 is the process of redistributing the a A proposed, large ZFE power plant has 12 chambers, with 10 chambers operating at any one time, each chamber at 0.1Hz to produce a total of about 1000 MW(e).…”

Section: Laser Fusionmentioning

confidence: 99%

“…Using cryogenic assembly, the HIF inventory models indicate that operating with less than ~ 1 kg tritium in the TFF will be feasible. 14 The challenge of the HIF target that is unique for fabrication is its distributed radiators. To fabricate these materials, a new process, high-pressure laser chemical vapor deposition (LCVD), is being experimentally demonstrated 27 LCVD utilizes a laser to catalyze a chemical vapor deposition in a controlled manner.…”

Section: Fig 2 Llnl Distributed Radiator Target Is Driven By Heavy mentioning

confidence: 99%

Demonstrating a Target Supply for Inertial Fusion Energy

Goodin

Alexander

Brown

et al. 2005

Fusion Science and Technology

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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 futureIFE 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 18 K. 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 xrays to implode the capsule. For either target, it must be accurately delivered to the target chamber center at a rate of about 5-10 Hz, with a precisely predicted target location. Future successful fabrication and injection systems must operate at the low cost required for energy production (about $0.25/target, about 10 4 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

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Tritium Inventory of Inertial Fusion Energy Target Fabrication Facilities: Effect of Foam Density and Consideration of Target Yield of Direct Drive Targets

Cited by 12 publications

References 17 publications

Estimation of the FST-Layering Time for Shock Ignition ICF Targets

Estimation of the FST-Layering Time for Shock Ignition ICF Targets

Direct-drive inertial confinement fusion: A review

Demonstrating a Target Supply for Inertial Fusion Energy

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