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(IF-1) Progress in Direct-Drive Inertial Confinement Fusion Research at the Laboratory for Laser Energetics

R.L. McCrory1), D.D. Meyerhofer1), S.J. Loucks1), S. Skupsky1), R.E. Bahr1), R. Betti1), T.R. Boehly1), R.S. Craxton1), T.J.B. Collins1), J.A. Delettrez1), W.R. Donaldson1), R. Epstein1), J.A. Frenje2), V.YU. Glebov1), V.N. Goncharov1), D.R. Harding1), P.A. Jaanimagi1), R.L. Keck1), J.H. Kelly1), T.J. Kessler1), J.P. Knauer1), C.K. Li2), L.D. Lund1), J.A. Marozas1), P.W. McKenty1), F.J. Marshall1), S.F.B. Morse1), R.D. Petrasso2), P.B. Radha1), S.P. Regan1), S. Roberts1), T.C. Sangster1), F.H. Séguin2), W. Seka1), V.A. Smalyuk1), C. Sorce*)1), J.M. Soures1), C. Stoeckl1), K.A. Thorp1), B. Yaakobi1), J.D. Zuegel1)
1) University of Rochester, Laboratory for Laser Energetics, Rochester, USA
2) Plasma Science and Fusion Center, MIT, Cambridge, MA, USA
* Currently at Lawrence Livermore National Laboratory, USA

Abstract.  Significant theoretical and experimental progress towards the validation of direct-drive inertial confinement fusion (ICF) has been recently made at the Laboratory for Laser Energetics (LLE). Direct-drive ICF offers the potential for high-gain implosions and is a leading candidate for an inertial fusion energy power plant. LLE’s base-line direct-drive ignition design for NIF is an ``all-DT'' design that has a 1-D gain of $ \sim$45. Recent calculations show that targets composed of foam shells, wicked with DT, can potentially achieve 1-D gains of $ \sim$100. LLE experiments are conducted on the OMEGA 60-beam, 30-kJ, UV laser system. Beam smoothing of OMEGA includes 1-THz, 2-D SSD and polarization smoothing. Cryogenic D2 and plastic shell (warm) spherical targets and a comprehensive suite of x-ray, nuclear, charged particle and optical diagnostics are used in these experiments. Future experiments will use cryogenic DT targets.

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IAEA 2003