A “polar contact” tent for reduced perturbation and improved performance of NIF ignition capsules

• Published in: Physics of plasmas 2018-08, Vol.25 (8)
• Main Authors: Hammel, B. A., Weber, C. R., Stadermann, M., Alday, C. L., Aracne-Ruddle, C., Bigelow, J. R., Clark, D. S., Cortez, J. P., Diaz, S., Döppner, T., Felker, S., Field, J. E., Haan, S. W., Havre, M. O., Heinbockel, C., Hinkel, D. E., Hsing, W. W., Johnson, S. A., Nikroo, A., Pickworth, L. A., Ralph, J. E., Robey, H. F., Smalyuk, V. A.
• Format: Article
• Language: English
• Subjects: Ablative materials; Computer simulation; Deceleration; Deuterium; Ignition; Implosions; Inertial confinement fusion; Laser beam heating; Plasma physics; Support systems; Tritium
• ISSN: 1070-664X; 1089-7674
• DOI: 10.1063/1.5032121

In indirectly driven Inertial Confinement Fusion implosions conducted on the National Ignition Facility (NIF), the imploding capsule is supported in a laser-heated radiation enclosure (called a “hohlraum”) by a pair of very thin (∼15–45 nm) plastic films (referred to as a “tent”). Even though the thickness of these tents is a small fraction of that of the spherical capsule ablator (∼165 μm), both numerical simulations as well as experiments indicate that this capsule support mechanism results in a large areal density (ρR) perturbation on the capsule surface at the contact point where the tent departs from the capsule. As a result, during deceleration of the deuterium-tritium (DT) fuel layer, a jet of the dense ablator material penetrates and cools the fuel hot spot, significantly degrading the neutron yield (resulting in only ∼10%–20% of the unperturbed 1-D yield). In this article, we present a hypothesis and supporting design simulations of a new “polar contact” tent support system, which reduces the contact area between the tent and the capsule and results in a significant improvement in the capsule performance. Simulations predict a ∼70% increase in neutron yield over that for an implosion with a traditional tent support. An initial demonstration experiment was conducted on the NIF and produced highest ever recorded primary DT neutron yield among all layered DT implosions with plastic ablators on the NIF, though more experiments are needed to comprehensively study the effect of the polar tent on implosion performance.