J. Phys. IV France
Volume 133, June 2006
|Page(s)||925 - 927|
|Publié en ligne||16 juin 2006|
J.-C. Gauthier, et al.
J. Phys. IV France 133 (2006) 925-927
Imploded capsule fuel temperature and density measurement by energy-dependent neutron imagingM.J. Moran1, J. Koch1, O.L. Landen1, S.W. Haan1, C.A. Barrera2 and E.C. Morse2
1 LLNL, PO Box 808, L-481, Livermore, CA 94550, USA
2 University of California, Dept. of Nuclear Engineering, Berkeley, CA 94720, USA
Neutron imaging systems measure the spatial distribution of neutron emission from burning inertial confinement fusion (ICF) targets. These systems use a traditional pinhole geometry to project an image of the source onto a two-dimensional scintillator array, and a CCD records the resulting scintillation image. The recent history of ICF neutron images has produced images with qualities that have improved as the fusion neutron yields have increased to nearly 1014 neutrons. Anticipated future neutron yields in excess of 1016 at the National Ignition Facility and LMJ have raised the prospect of neuron imaging diagnostics which simultaneously probe several different characteristics of burning fusion targets. The new measurements rely on gated-image recording to select images corresponding to specific bands of neutron energies. Gated images of downscattered neutrons with energies from 5 to 8 MeV can emphasize regions of the target which contain DT fuel which is not burning. At the same time, gated images which select different portions of the 14-MeV spectral peak can produce spatial temperature maps of a burning target. Since the neutron production depends on the DT fuel density and temperature, simultaneous images of temperature and neutron emission can be combined to infer the an image of the source density using an Abel inversion method that is analogous to the method that has been used in x-ray imaging. Thus, with higher-yield sources, neutron imaging offers the potential to record simultaneously several critical features that characterize the performance of an ICF target: the neutron emission distribution, the temperature and density distributions, and the distribution of nonburning fuel within the target.
© EDP Sciences 2006