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. 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.
Performance scaling with an applied magnetic field in indirect-drive inertial confinement fusion implosions
H. Sio, J. D. Moody, B. B. Pollock, D. J. Strozzi, D. D.-M. Ho, C. A. Walsh, G. E. Kemp, B. Lahmann, S. O. Kucheyev, B. Kozioziemski, E. G. Carroll, J. Kroll, D. K. Yanagisawa, J. Angus, B. Bachmann, A. A. Baker, L. B. Bayu Aji, S. D. Bhandarkar, J. D. Bude, L. Divol, A. M. Engwall, B. Ferguson, J. Fry, L. Hagler, E. Hartouni, M. C. Herrmann, W. Hsing, D. M. Holunga, J. Javedani, A. Johnson, S. Khan, D. Kalantar, T. Kohut, B. G. Logan, N. Masters, A. Nikroo, N. Izumi, N. Orsi, K. Piston, C. Provencher, A. Rowe, J. Sater, S. J. Shin, K. Skulina, W. A. Stygar, V. Tang, S. E. Winters, G. Zimmerman, J. P. Chittenden, B. Appelbe, A. Boxall, A. Crilly, S. O'Neill, D. Barnak, J. Davies, J. Peebles, J. H. Bae, K. Clark, M. Havre, M. Mauldin, M. Ratledge, S. Vonhof, P. Adrian, B. Reichelt, S. Fujioka, M. Fraenkel; Performance scaling with an applied magnetic field in indirect-drive inertial confinement fusion implosions. Phys. Plasmas 1 July 2023; 30 (7): 072709. https://doi.org/10.1063/5.0150441
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