DocumentCode
2271992
Title
Target diagnostics for the National Ignition Facility
Author
Cable, M.D.
Author_Institution
Lawrence Livermore Nat. Lab., CA, USA
fYear
1995
fDate
5-8 June 1995
Firstpage
152
Abstract
Summary form only given, as follows. The proposed National Ignition Facility (NIF) is a large (1.8 MJ on target at 0.35 /spl mu/m) multi-beam laser facility that wilt be used for inertial confinement fusion (ICF). ICF implosions at this facility will produce core plasma temperatures over 10 keV and densities over 100 g/cm/sup 3/. Properties of these plasmas can be measured (diagnosed) by a variety of optical, X-ray and nuclear diagnostic techniques such as those used at existing facilities like the Nova laser. Some of these currently used techniques will be directly applicable to NIF. Others, particularly the nuclear based ones due to the expected large increase in nuclear reactions at NIF, will significantly change. An overview of the techniques used at Nova and the plans for diagnostics at NIF will be presented.
Keywords
fusion reactor fuel; fusion reactor ignition; fusion reactors; plasma density; plasma diagnostics; plasma inertial confinement; plasma production by laser; plasma temperature; temperature; 1.8 MJ; 10 keV; National Ignition Facility; Nova laser; X-ray diagnostic techniques; inertial confinement fusion; multi-beam laser facility; nuclear diagnostic techniques; optical diagnostic techniques; plasma density; plasma temperature; target diagnostics; Ignition; Inertial confinement; Laser fusion; Plasma confinement; Plasma density; Plasma diagnostics; Plasma measurements; Plasma properties; Plasma temperature; X-ray lasers;
fLanguage
English
Publisher
ieee
Conference_Titel
Plasma Science, 1995. IEEE Conference Record - Abstracts., 1995 IEEE International Conference on
Conference_Location
Madison, WI, USA
ISSN
0730-9244
Print_ISBN
0-7803-2669-5
Type
conf
DOI
10.1109/PLASMA.1995.531598
Filename
531598
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