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Modeling ablator defects as a source of mix in high-performance implosions at the National Ignition Facility

Title: Modeling ablator defects as a source of mix in high-performance implosions at the National Ignition Facility
Authors: Clark, D. S.; Allen, A.; Baxamusa, S. H.; Biener, J.; Biener, M. M.; Braun, T.; Davidovits, S.; Divol, L.; Farmer, W. A.; Fehrenbach, T.; Kong, C.; Millot, M.; Milovich, J.; Nikroo, A.; Nora, R. C.; Pak, A. E.; Rubery, M. S.; Stadermann, M.; Sterne, P.; Weber, C. R.; Wild, C.
Contributors: U.S. Department of Energy; General Atomics
Source: Physics of Plasmas ; volume 31, issue 6 ; ISSN 1070-664X 1089-7674
Publisher Information: AIP Publishing
Publication Year: 2024
Description: Recent indirect drive inertial confinement fusion implosions on the National Ignition Facility (NIF) [Spaeth et al., Fusion Sci. Technol. 69, 25 (2016)] have crossed the threshold of ignition. However, performance has been variable due to several factors. One of the leading sources of variability is the quality of the high-density carbon (HDC) shells used as ablators in these experiments. In particular, these shells can have a number of defects that have been found to correlate with the appearance of ablator mix into the hot spot and a degradation in nuclear yield. These defects include pits on the ablator surface, voids in the ablator bulk, high-Z debris from the Hohlraum wall that adheres to the capsule surface, and finally the inherent granular micro-structure of the crystalline HDC itself. This paper summarizes high-resolution modeling of each of these mix sources in two recent high-performance NIF implosion experiments. The simulated impact from a range of individual capsule defects is found to be broadly consistent with the trends seen in experiment, lending credence to the modeling results and the details of the mixing process that they reveal. Interestingly, modeling of the micro-structure inherent to HDC shows that this perturbation source results in considerable mixing of the deuterium–tritium fuel with ablator material during the implosion. The reduction in fuel compression from this mix results in an approximately factor of two reduction in neutron yield in current implosions and emphasizes the importance of mitigating this significant performance degradation.
Document Type: article in journal/newspaper
Language: English
DOI: 10.1063/5.0200730
DOI: 10.1063/5.0200730/20020856/062706_1_5.0200730.pdf
Availability: https://doi.org/10.1063/5.0200730; https://pubs.aip.org/aip/pop/article-pdf/doi/10.1063/5.0200730/20020856/062706_1_5.0200730.pdf
Rights: https://creativecommons.org/licenses/by/4.0/ ; https://creativecommons.org/licenses/by/4.0/
Accession Number: edsbas.5E4583D
Database: BASE