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ORIGINAL RESEARCH article

Front. Chem.

Sec. Analytical Chemistry

Volume 13 - 2025 | doi: 10.3389/fchem.2025.1632948

Using radiochemistry to diagnose fuel-ablator mix in inertial confinement fusion studies at the National Ignition Facility: Measurement of Tc/Mo isotopic ratios for the Pushered Single Shell Campaign

Provisionally accepted
Kelly  Nora KmakKelly Nora Kmak*John  DespotopulosJohn DespotopulosTony  HuynhTony HuynhBrian  SammisBrian SammisKeenan  ThomasKeenan ThomasTodd  WooddyTodd WooddyEduard  DewaldEduard DewaldStephan  MacLarenStephan MacLaren
  • Lawrence Livermore National Laboratory (DOE), Livermore, United States

The final, formatted version of the article will be published soon.

The development of radiochemical measurement techniques as a diagnostic for fusion experiments at the National Ignition Facility enables a new method for assessing fuel-ablator mix and the impact of this mix on capsule performance. Diagnosing capsule mix in internal confinement fusion studies is difficult due to the small spatial scales (10s of µm) and short-time frames (100s of ps) over which the mix typically evolves in these experiments. For the Pushered Single Shell campaign, radiochemical measurements on debris collected from fusion experiments can be used to determine isotopic ratios of activation products, particularly 96gTc/99Mo and 95gTc/99Mo, to provide vital information on nuclear reactions in the burning plasma that can inform simulations that seek to understand the degree of capsule-fuel mix and the impact on the capsule performance. These radiochemical measurements have been conducted regularly since November 2023 providing data on a range of capsule designs and neutron yields. Data from eight NIF experiments is presented, the measured 96gTc/99Mo and 95gTc/99Mo range from (0.5 - 5) × 10-4 to (0.3 - 3) × 10-4, respectively. The development of radiochemical diagnostics aids in understanding and optimizing the design of fusion experiments, providing unique and valuable insights into capsule behavior and directly measuring fuel-ablator mix.

Keywords: National Ignition Facility, inertial confinement fusion, Radiochemical separations, Mo, TC

Received: 21 May 2025; Accepted: 28 Aug 2025.

Copyright: © 2025 Kmak, Despotopulos, Huynh, Sammis, Thomas, Wooddy, Dewald and MacLaren. This is an open-access article distributed under the terms of the Creative Commons Attribution License (CC BY). The use, distribution or reproduction in other forums is permitted, provided the original author(s) or licensor are credited and that the original publication in this journal is cited, in accordance with accepted academic practice. No use, distribution or reproduction is permitted which does not comply with these terms.

* Correspondence: Kelly Nora Kmak, Lawrence Livermore National Laboratory (DOE), Livermore, United States

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