High-gain direct-drive target design for the Laser Mégajoule

Canaud, B.; Fortin, X.; Garaude, F.; Meyer, C.; Philippe, F.; Temporal, M.; Atzeni, S.; Schiavi, A.

doi:10.1088/0029-5515/44/10/005

Cited by 45 publications

(36 citation statements)

References 33 publications

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“…In Table 1 are shown the parameters [ , m] that provide a minimum of 0 for five irradiation configurations. In the Table 1 are also shown the illumination uniformities 1 [ , m] evaluated assuming a power imbalance PI = 5% and a pointing error PE = 5%. These non-uniformities 1 represent the average value of the non-uniformity evaluated on one thousand of calculations where random power imbalance and the pointing errors follow Gaussian distributions.…”

Section: Illumination Uniformitymentioning

confidence: 99%

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Illumination uniformity of capsules directly driven by a facility with thousands of laser beams

Temporal

Canaud

Brandon

2013

EPJ Web of Conferences

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Abstract. The uniformity of the illumination of a spherical capsule directly driven by laser beams has been assessed numerically. Different schemes characterized by N D = 12, 20, 32, 48 and 60 directions of irradiation associated to a single laser beam or a bundle of N B laser beams have been considered. The laser beams intensity profile is assumed super-Gaussian and the calculations take into account for beam imperfections as power imbalance and pointing errors. These facilities are characterized by a large number of laser beams N tot = N D xN B . Assuming relatively small laser beams with an energy of a few hundred of J (200 J-500 J) it turn out that a few thousand of beamlets (1000-5000) are needed in order to provide a total energy of 0.5-1 MJ. A large parametric study has been performed showing that the optimum laser intensity profile, which minimizes the root-mean-square deviation of the capsule illumination, depends on the values of the power imbalance and pointing error. Moreover, when beams imperfections are taken into account it is found that the uniformity of the illumination is almost the same for all facilities and only depends on the total number of laser beams N tot .

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Section: Illumination Uniformitymentioning

confidence: 99%

“…In Direct Drive (DD) [1,2] Inertial Confinement Fusion (ICF) [3][4][5] a spherical capsule is directly irradiated by laser beams. As a consequence of the fast laser energy deposition the capsule implodes and compresses the thermonuclear Deuterium-Tritium (DT) fuel.…”

Section: Introductionmentioning

confidence: 99%

Illumination uniformity of capsules directly driven by a facility with thousands of laser beams

Temporal

Canaud

Brandon

2013

EPJ Web of Conferences

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“…Fig. 1 shows calculated neutron spectra emitted from a cryogenic DT high-gain direct-drive target-design for LMJ [11,12]. The total spectrum is reported on both plots.…”

Section: Secondary and Tertiary Neutrons As A Hr:ri Measurementmentioning

confidence: 99%

DEMIN: A neutron spectrometer, Micromegas-type, for inertial confinement fusion experiments

Houry

Delagnes

Riz

et al. 2006

Nuclear Instruments and Methods in Physics Research Section A:

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“…That is illustrated in FIG.1 by comparing the principal Hugoniot curves derived from the MP-EoS and the SESAME EoS, that shows a clear difference in compressibility of the DT ice under dynamic loading. The implication of such differences in the DT EoS for the optimization of ICF implosion is discussed below for two ICF targets, the LMJ baseline direct drive design [17] and a shock-ignited (SI) Hiper-like direct drive design [18]. Hydrodynamic calculations were performed with the multidimensional Lagrangian radiationhydrodynamics code FCI2 [19] employed here in its onedimensional version.…”

mentioning

confidence: 99%

“…The Direct-Drive baseline design for LMJ target is a massive 1642 µm outer radius, 1 µm-thick CH-layer, 202 µm-thick wetted-foam and 164 µm-thick DT ice innerlayer capsule [17]. Four hydro-simulations output are performed and presented in FIG.3.…”

mentioning

confidence: 99%

Change in Inertial Confinement Fusion Implosions upon Using anAb InitioMultiphase DT Equation of State

et al. 2011

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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 (ICF) target (Hu et al., PRL 104, 235003 (2010)). We use here an advanced multi-phase equation of state (EoS), based on ab initio calculations, to perform a full optimization of the laser pulse shape with hydrodynamic simulations starting from 19 K 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.PACS numbers: 52.57. Bc, 47.40.Nm, 47.55.Kf, 52.57.Fg The DT EoS, starting from the cryogenic solid and undergoing a wide range of plasma conditions, is a key input to simulate the ICF implosion of the DT pellet and hence to quantify the fusion energy production. The current uncertainty in the EoS of DT, more particularly in the strongly correlated and degenerate regime, is maintaining uncertainties in hydro-simulations for the prediction of ICF thermonuclear gains and also for the shock timing design. Recently, Hu et al. [1] have shown a significant reduction (30 %) of the thermonuclear gain by improving the DT EoS in the strongly coupled and degenerate regime. A direct implication of this work is the reduction of the safety margin in current ICF designs that could be deleterious to achieve high gains. But, no re-optimization of the laser pulse has been performed with this partial ab initio EoS, only valid for T ≥ 1.35 eV. Consequently, that poses two important questions: can the decrease in thermonuclear energy be avoided by re-shaping the laser pulse, and what result would this have on the tuning of shock timing? The aim of the present work is to address these two questions.We use here a recently published Multi-Phase DT EoS[2], dubbed MP-EoS, that is based on ab initio calculations in the strongly coupled and degenerate regime (ρ = 0.5 − 12.5 g/cc and T ≤ 10 eV), and extended here to cover the whole thermodynamical path of DT ice (ρ = 0.25 -4.10 3 g/cc and T=0-10 keV). Hydrosimulations can thus start at the realistic temperature of 19 K for DT ice, that allows to take into account the effect of the solid-liquid transition and to avoid any effect of pre-heating of the shell. Two different target designs are considered, one for shock ignition and the other for self-ignition, corresponding to two different thermodynamic paths for the compression of the DT fuel. It will * Corresponding author: benoit.canaud@cea.fr be shown below that the energy gain of the target is in fact a robust estimate, that can be recovered after optimization of the laser pulse. But the use of a more realistic EoS can lead to large changes in the shock timing.In classical Inertial Confine...

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High-gain direct-drive target design for the Laser Mégajoule

Cited by 45 publications

References 33 publications

Illumination uniformity of capsules directly driven by a facility with thousands of laser beams

Illumination uniformity of capsules directly driven by a facility with thousands of laser beams

DEMIN: A neutron spectrometer, Micromegas-type, for inertial confinement fusion experiments

Change in Inertial Confinement Fusion Implosions upon Using anAb InitioMultiphase DT Equation of State

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