ICF power plants, such as the LIFE scheme at LLNL, may employ a high-Z, target-chamber gas-fill to moderate the
first-wall heat-pulse due to x-rays and energetic ions released during target detonation.
To reduce the uncertainties of cooling and beam/target propagation through such gas-filled chambers, we present a
pulsed plasma source producing 2-5 eV plasma comprised of high-Z gases. We use a 5-kJ, 100-ns theta discharge for
high peak plasma-heating-power, an electrode-less discharge for minimizing impurities, and unobstructed axial access
for diagnostics and beam (and/or target) propagation studies. We will report on the plasma source requirements, design
process, and the system design.
The LIFE minichamber experiment will investigate cooling of the strongly radiating Xe buffer gas protecting the LIFE
chamber wall. A theta pinch will inductively heat a few cc of Xe at ion density 2e16/cc to several eV. Thomson
scattering will be used to determine electron temperature and ionization state. Modeled is being done using the
magnetohydrodynamic code HYDRA with an external circuit model and inductive feedback from the plasma to the
external circuit. Coil stresses are being assessed using the 3D MHD code ALE3D. A major challenge to the design is the
paucity of opacity and conductivity data for Xe in the buffer gas regime. Results of the modeling will be presented.
*This work performed under the auspices of the U.S. Department of Energy by Lawrence Livermore National
Laboratory under Contract DE-AC52-07NA27344.
The NIF target chamber interior materials and target designs themselves have to be compatible with survival of the final- optics debris shields. To meet the planned maintenance and refinishing rate, the contamination of the debris shields cannot exceed about 1 nm equivalent thickness per shot of total material. This implies that he target mass must be limited to no more than 1 gram and the ablated mass released to the chamber from all other components must not exceed 3 grams. In addition, the targets themselves must either completely vaporize or send any minor amounts of shrapnel towards the chamber waist to prevent excessive catering of the debris shields. The constraints on the first-wall debris will remobilize at a rate fast enough to require cleaning every 3 weeks, about three times more frequent than possible with planned robotics. Furthermore, a comparison of ablatants from B4C and stainless-steel louvers suggest that remobilization of target debris by x-rays will be greater than that of the base material in both cases, thereby reducing the performance advantage of clean B4C over much cheaper stainless steel. Neutronics calculations indicate that activation of thin Ni-free stainless steel is not a significant source of maintenance personnel radiation dose. Consequently, the most attractive first wall design consists of stainless-steel louvers. Evaluation of various unconverted-light beam dump designs indicates that stainless steel louvers generate no more debris than other matrices, so one single design can serve as both first wall and beam dumps, eliminating beam steering restrictions caused by size and location of the beam dumps. One reservation is that the allowable contamination rate of the debris shield is not yet completely understood. Consequently, it is likely that either a protruding beam tube, a rapid post-shot gas purge of the final optics assembly, or thin polymeric pre-shield will be required to prevent low-velocity contamination from reaching the debris shield.
Conference Committee Involvement (1)
High Power Lasers for Fusion Research
26 January 2011 | San Francisco, California, United States
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