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Callahan, D.A.; Herrmann, M.C.; Tabak, M.
Lawrence Livermore National Lab., Livermore, CA (United States). Funding organisation: USDOE Office of Defense Programs (DP) (United States)2002
Lawrence Livermore National Lab., Livermore, CA (United States). Funding organisation: USDOE Office of Defense Programs (DP) (United States)2002
AbstractAbstract
[en] Progress in heavy ion target design over the past few years has focused on relaxing the target requirements for the driver and for target fabrication. We have designed a plastic (CH) ablator capsule that is easier to fabricate and fill than the beryllium ablator we previously used. In addition, 2-d Rayleigh-Taylor instability calculations indicate that this capsule can tolerate ablator surface finishes up to ten times rougher than the NIF specification. We have also explored the trade-off between surface roughness and yield as a method for finding the optimum capsule. We have also designed two new hohlraums: a ''hybrid'' target and a large angle, distributed radiator target. The hybrid target allows a beam spot radius of almost 5 mm while giving gain of 55 from 6.7 MJ of beam energy in integrated Lasnex calculations. To achieve the required symmetry with the large beam spot, internal shields were used in the target to control the P2 and P4 asymmetry. The large-angle, distributed radiator target is a variation on the distributed radiator target that allows large beam entrance angles (up to 24 degrees). Integrated calculations have produced 340 MJ from 6.2 MJ of beam energy in a design that is not quite optimal. In addition, we have done a simple scaling to understand the peak ion beam power required to compress fuel for fast ignition using a short pulse laser
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8 May 2002; 760 Kilobytes; 14. International Symposium on Heavy Ion Inertial Fusion HIF2002; Moscow (Russian Federation); 26-31 May 2002; W-7405-ENG-48; Available from PURL: https://www.osti.gov/servlets/purl/803176-C0LZwQ/native/
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