Matter and Radiation at Extremes, Volume. 7, Issue 3, 035902(2022)

Numerical performance assessment of double-shell targets for Z-pinch dynamic hohlraum

Y. Y. Chua)... Z. Wang, J. M. Qi, Z. P. Xu and Z. H. Li |Show fewer author(s)
Author Affiliations
  • Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Mianyang 621900, China
  • show less
    Figures & Tables(14)
    Schematics of capsules with different radii: (a) 2 mm; (b) 2.5 mm; (c) 3 mm.
    (a) Implosion flow plot with scaled radiation temperature profile and scaled fusion power. (b) Flow plot near stagnation. (c) Fusion power waveform. The driven radiation temperature profile Tr(t) and the fusion power profile Pf(t) in (a) are both scaled to have a maximum value of 2.5.
    Evolutions of (a) kinetic energies and (b) total energies of different layers. The total energy is the sum of the internal energy and kinetic energy.
    Power analysis for the DT fuel region (a) over a long time span and (b) near the ignition time, and (c) time-integrated power curve. The surface power loss is defined as the sum of all the conductive power losses, namely, the radiative loss, electronic conductive loss, and ionic conductive loss. Negative work loss indicates fuel heating, and positive work loss indicates fuel cooling.
    Radial distributions of fuel densities, pressures, and ion temperatures at five different times around ignition.
    Cross-sectional schematic of the ZPDH load (left), and the input drive current profile (right).
    Density distributions of the ZPDH plasma at 393.3 and 394.5 ns. In the enlarged panels, the black solid line indicates the fuel–pusher interface, and the blue dashed circle indicates a sphere of the same radius.
    Radiation temperature profiles at two different positions on the capsule surface. The red solid line indicates the equatorial radiation temperature profile, and the blue dotted line indicates the polar radiation temperature profile.
    Influence of the radiation temperature profile characteristics on the fusion energy yields (in MJ) with the 2.5 mm-radius double-shell capsule.
    Sensitivities of fusion energy yield to (a) ablator thickness, (b) pusher thickness, (c) fuel density, and (d) cushion density.
    (a) Implosion flow plot of the double-shell capsule surrounded by CH foam with density 50 mg/cm3. (b) Corresponding fusion power released.
    • Table 1. Main features of the three double-shell capsules.

      View table
      View in Article

      Table 1. Main features of the three double-shell capsules.

      Capsule labelIIIIII
      Capsule radius (mm)22.53
      Ablator mass (mg)36.67362.39596.136
      Cushion mass (mg)0.2230.5491.072
      Pusher mass (mg)5.689.61616.762
      Fuel mass (mg)0.2150.3590.637
      Fusion energy (MJ)28.856.1101.6
      Burn efficiency0.400.460.47
    • Table 2. Maximum energy absorbed by the capsule Eabs,capsule, maximum kinetic energy of the pusher layer Ek,pusher, and maximum internal energy of the DT fuel Ei,fuel for different peak values or different FWHM of the driven radiation temperature profile with a Gaussian shape. In the calculation, the fusion process is switched off.

      View table
      View in Article

      Table 2. Maximum energy absorbed by the capsule Eabs,capsule, maximum kinetic energy of the pusher layer Ek,pusher, and maximum internal energy of the DT fuel Ei,fuel for different peak values or different FWHM of the driven radiation temperature profile with a Gaussian shape. In the calculation, the fusion process is switched off.

      Peak (eV)FWHM (ns)Eabs,capsule (MJ)Ek,pusher (kJ)Ei,fuel (kJ)
      280101.63112.865.3
      300102.06173.891.3
      320102.49171.790.0
      340102.82158.586.3
      300122.32201.8103.2
      30081.72124.970.7
    • Table 3. Maximum energy absorbed by the capsule Eabs,capsule, maximum kinetic energy of the pusher layer Ek,pusher, and maximum internal energy of the DT fuel Ei,fuel when the capsule parameters deviate from those shown in Fig. 1(b). The driven radiation takes the form given in Eq. (1), and the fusion process is switched off.

      View table
      View in Article

      Table 3. Maximum energy absorbed by the capsule Eabs,capsule, maximum kinetic energy of the pusher layer Ek,pusher, and maximum internal energy of the DT fuel Ei,fuel when the capsule parameters deviate from those shown in Fig. 1(b). The driven radiation takes the form given in Eq. (1), and the fusion process is switched off.

      Changed propertyValueEabs,capsule (MJ)Ek,pusher (kJ)Ei,fuel (kJ)
      Ablator thickness400 μm1.73121.266.8
      500 μm1.99171.790.1
      600 μm2.17156.986.4
      700 μm2.35132.874.8
      Pusher thickness10 μm2.0172.985.3
      30 μm2.04153.998.2
      50 μm2.07181.886.6
      70 μm2.11186.965.3
      Fuel density0.05 g/cm32.06184.861.4
      0.10 g/cm32.06173.891.3
      0.15 g/cm32.06165.1113.9
      0.20 g/cm32.06157.7128.9
      Cushion density0.05 g/cm32.06175.192.3
      0.10 g/cm32.06168.086.7
      0.15 g/cm32.07157.880.2
      0.20 g/cm32.07149.776.6
    Tools

    Get Citation

    Copy Citation Text

    Y. Y. Chu, Z. Wang, J. M. Qi, Z. P. Xu, Z. H. Li. Numerical performance assessment of double-shell targets for Z-pinch dynamic hohlraum[J]. Matter and Radiation at Extremes, 2022, 7(3): 035902

    Download Citation

    EndNote(RIS)BibTexPlain Text
    Save article for my favorites
    Paper Information

    Category: Inertial Confinement Fusion Physics

    Received: Nov. 17, 2021

    Accepted: Mar. 20, 2022

    Published Online: Jan. 11, 2023

    The Author Email: Y. Y. Chu (chuyanyun1230@163.com)

    DOI:10.1063/5.0079074

    Topics