IFE Chamber Wall Materials Response to Pulsed X-rays on Z and Ions on RHEPP* **
Abstract
We are investigating the response of candidate Inertial Fusion Energy (IFE) reactor materials to pulsed x-rays (on Z) and energetic ions (on RHEPP) at fluences similar to those predicted for future reactors. Both the Z and RHEPP facilities are located at Sandia National Laboratories. Primary dry wall armor materials under consideration are carbon and tungsten in various forms, in either flat or 'engineered' geometry such as carbon 'velvet'. Experiments are underway to 1) determine single-shot threshold for ablation, 2) characterize surface roughening occurring below this ablation threshold, and 3) measure net ablation for doses exceeding the ablation threshold, as a function of dose. Graphite is observed to ablate readily above a threshold dose level of 3-4 J/cm^2. Sintered graphite and tungsten sheet are observed to exhibit thermomechanical responses that result in material loss beyond that expected from sublimation predicted by BUCKY and other modeling codes. Experiments are planned to measure erosion of the carbon velvet tips and shafts due to RHEPP ion exposure, to measure directly the time-dependent surface temperature during ion beam exposure, and to compare both with code predictions.
- Publication:
-
APS Division of Plasma Physics Meeting Abstracts
- Pub Date:
- November 2002
- Bibcode:
- 2002APS..DPPFP1162R