A “polar contact” tent for reduced perturbation and improved performance of NIF ignition capsules
Abstract
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. Overall, an initial demonstration experimentmore »
- Authors:
-
more »
- Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
- General Atomics, San Diego, CA (United States)
- Publication Date:
- Research Org.:
- Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
- Sponsoring Org.:
- USDOE National Nuclear Security Administration (NNSA)
- OSTI Identifier:
- 1765299
- Alternate Identifier(s):
- OSTI ID: 1466077
- Report Number(s):
- LLNL-JRNL-743472
Journal ID: ISSN 1070-664X; 898422; TRN: US2206235
- Grant/Contract Number:
- AC52-07NA27344; NA0001808
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Physics of Plasmas
- Additional Journal Information:
- Journal Volume: 25; Journal Issue: 8; Journal ID: ISSN 1070-664X
- Publisher:
- American Institute of Physics (AIP)
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 70 PLASMA PHYSICS AND FUSION TECHNOLOGY; Plasma confinement
Citation Formats
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., and Smalyuk, V. A. A “polar contact” tent for reduced perturbation and improved performance of NIF ignition capsules. United States: N. p., 2018.
Web. doi:10.1063/1.5032121.
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. A “polar contact” tent for reduced perturbation and improved performance of NIF ignition capsules. United States. https://doi.org/10.1063/1.5032121
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., and Smalyuk, V. A. Thu .
"A “polar contact” tent for reduced perturbation and improved performance of NIF ignition capsules". United States. https://doi.org/10.1063/1.5032121. https://www.osti.gov/servlets/purl/1765299.
@article{osti_1765299,
title = {A “polar contact” tent for reduced perturbation and improved performance of NIF ignition capsules},
author = {Hammel, B. A. and Weber, C. R. and Stadermann, M. and Alday, C. L. and Aracne-Ruddle, C. and Bigelow, J. R. and Clark, D. S. and Cortez, J. P. and Diaz, S. and Döppner, T. and Felker, S. and Field, J. E. and Haan, S. W. and Havre, M. O. and Heinbockel, C. and Hinkel, D. E. and Hsing, W. W. and Johnson, S. A. and Nikroo, A. and Pickworth, L. A. and Ralph, J. E. and Robey, H. F. and Smalyuk, V. A.},
abstractNote = {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. Overall, 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.},
doi = {10.1063/1.5032121},
journal = {Physics of Plasmas},
number = 8,
volume = 25,
place = {United States},
year = {Thu Aug 23 00:00:00 EDT 2018},
month = {Thu Aug 23 00:00:00 EDT 2018}
}
Web of Science
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