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Holzrichter, J.F.; Eimerl, D.; George, E.V.; Trenholme, J.B.; Simmons, W.W.; Hunt, J.T.
Lawrence Livermore National Lab., CA (USA)1982
Lawrence Livermore National Lab., CA (USA)1982
AbstractAbstract
[en] High-power pulsed lasers can deliver sufficient energy on inertial-confinement fusion (ICF) time scales (0.1 to 10 ns) to heat and compress deuterium-tritium fuel to fusion-reaction conditions. Several laser systems have been examined, including Nd:glass, CO2, KrF, and I2, for their ICF applicability. A great deal of developmental effort has been applied to the Nd:glass laser and the CO2 gas laser systems; these systems now deliver > 104 J and 20 x 1012 W to ICF targets. We are constructing the Nova Nd:glass laser at LLNL to provide > 100 kJ and > 100 x 1012 W of 1-μm radiation for fusion experimentation in the mid-1980s. For ICF target gain > 100 times the laser input, we expect that the laser driver must deliver approx. 3 to 5 MJ of energy on a time scale of 10 to 20 ns. In this paper we review the technological status of fusion-laser systems and outline approaches to constructing high-power pulsed laser drivers
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Sep 1982; 61 p; Available from NTIS, PC A04/MF A01 as DE83012564
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