Performance scaling with an applied magnetic field in indirect-drive inertial confinement fusion implosions
Author:
Sio H.1ORCID, Moody J. D.1ORCID, Pollock B. B.1ORCID, Strozzi D. J.1ORCID, Ho D. D.-M.1ORCID, Walsh C. A.1ORCID, Kemp G. E.1ORCID, Lahmann B.1ORCID, Kucheyev S. O.1ORCID, Kozioziemski B.1ORCID, Carroll E. G.1ORCID, Kroll J.1ORCID, Yanagisawa D. K.1, Angus J.1ORCID, Bachmann B.1ORCID, Baker A. A.1ORCID, Bayu Aji L. B.1, Bhandarkar S. D.1ORCID, Bude J. D.1, Divol L.1ORCID, Engwall A. M.1ORCID, Ferguson B.1ORCID, Fry J.1, Hagler L.1ORCID, Hartouni E.1ORCID, Herrmann M. C.1ORCID, Hsing W.1, Holunga D. M.1ORCID, Javedani J.1, Johnson A.1ORCID, Khan S.1ORCID, Kalantar D.1ORCID, Kohut T.1, Logan B. G.1, Masters N.1ORCID, Nikroo A.1ORCID, Izumi N.1ORCID, Orsi N.1, Piston K.1ORCID, Provencher C.1, Rowe A.1ORCID, Sater J.1ORCID, Shin S. J.1ORCID, Skulina K.1, Stygar W. A.1ORCID, Tang V.1ORCID, Winters S. E.1, Zimmerman G.1ORCID, Chittenden J. P.2ORCID, Appelbe B.2ORCID, Boxall A.2ORCID, Crilly A.2ORCID, O'Neill S.2ORCID, Barnak D.3ORCID, Davies J.3ORCID, Peebles J.3ORCID, Bae J. H.4ORCID, Clark K.4ORCID, Havre M.4, Mauldin M.4, Ratledge M.4ORCID, Vonhof S.4ORCID, Adrian P.5ORCID, Reichelt B.5ORCID, Fujioka S.6ORCID, Fraenkel M.7ORCID
Affiliation:
1. Lawrence Livermore National Laboratory 1 , Livermore, California 94550, USA 2. Centre for Inertial Fusion Studies, The Blackett Laboratory, Imperial College 2 , London SW7 2AZ, United Kingdom 3. Laboratory for Laser Energetics, University of Rochester 3 , New York 14623, USA 4. General Atomics 4 , San Diego, California 92121, USA 5. Massachusetts Institute of Technology 5 , Cambridge, Massachusetts 02139, USA 6. Institute for Laser Engineering, Osaka University 6 , 2-6 Yamada-Oka, Suita, Osaka 565-0871, Japan 7. Plasma Physics Department, Soreq NRC 7 , Yavne 81800, Israel
Abstract
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.
Funder
U.S. Department of Energy Lawrence Livermore National Laboratory
Subject
Condensed Matter Physics
Cited by
1 articles.
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