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Performance scaling with an applied magnetic field in indirect-drive inertial confinement fusion implosions

Journal Article · · Physics of Plasmas
DOI:https://doi.org/10.1063/5.0150441· OSTI ID:1989991
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  1. Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States)
  2. Imperial College, London (United Kingdom)
  3. Univ. of Rochester, NY (United States)
  4. General Atomics, San Diego, CA (United States)
  5. Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)
  6. Osaka Univ. (Japan)
  7. Israel Atomic Energy Commission (IAEC), Yavne (Israel). Soreq Nuclear Research Centre (Soreq NRC)
+ Show Author Affiliations
Magnetizing a cryogenic deuterium–tritium (DT)-layered inertial confinement fusion (ICF) implosion can improve performance by reducing thermal conduction and improving DT-alpha confinement in the hot spot. A room-temperature, magnetized indirect-drive ICF platform at the National Ignition Facility has been developed, using a high-Z, high-resistivity AuTa4 alloy as the hohlraum wall material. Experiments show a 2.5× increase in deuterium–deuterium (DD) neutron yield and a 0.8-keV increase in hot-spot temperature with the application of a 12-T B-field. Further, for an initial 26-T B-field, we observed a 2.9× yield increase and a 1.1-keV temperature increase, with the inferred burn-averaged B-field in the compressed hot spot estimated to be 7.1 ± 1.8 kT using measured primary DD-n and secondary DT-n neutron yields.
Research Organization:
Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States)
Sponsoring Organization:
USDOE Laboratory Directed Research and Development (LDRD) Program; USDOE National Nuclear Security Administration (NNSA)
Grant/Contract Number:
89233119CNA000063; AC52-07NA27344
OSTI ID:
1989991
Report Number(s):
LLNL-JRNL-845574; 1068929
Journal Information:
Physics of Plasmas, Journal Name: Physics of Plasmas Journal Issue: 7 Vol. 30; ISSN 1070-664X
Publisher:
American Institute of Physics (AIP)Copyright Statement
Country of Publication:
United States
Language:
English

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Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
Fusion experiments
Magnetic fields
Plasma confinement
Thermal conductivity