Testing IFE materials on Z.
- Los Alamos National Laboratory, Los Alamos, NM
On a single-pulse basis, the tungsten armor for the chamber walls in a laser inertial fusion energy power plant must withstand X-ray fluences of 0.4-1.2 J/cm{sup 2} with almost no mass loss, and preferably no surface changes. We have exposed preheated tungsten samples to 0.27 and 0.9 J/cm{sup 2} X-ray fluence from the Z accelerator at Sandia National Laboratories to determine the single-shot X-ray damage threshold. Earlier focused ion beam analysis has shown that rolled powdered metal formed tungsten and tungsten alloys, will melt when exposed to 2.3 J/cm{sup 2} on Z, but not at 1.3 J/cm{sup 2}. Three forms of tungsten single-crystal (SING), chemical-vapor-deposited (CVD), and rolled powdered metal (PWM) were exposed to fluence levels of 0.9 J/cm{sup 2} without any apparent melting. However, the CVD and PWM sample surfaces were rougher after exposure than the SING sample, which was not roughened. BUCKY (1D) calculations show a threshold of 0.5 J/cm{sup 2} for melting on Z. The present experiments indicate no melting but limited surface changes occur with polycrystalline samples (PWM and CVD) at 0.9 J/cm{sup 2} and no surface changes other than debris for samples at 0.27 J/cm{sup 2}.
- Research Organization:
- Sandia National Laboratories
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- AC04-94AL85000
- OSTI ID:
- 952155
- Report Number(s):
- SAND2004-6711J
- Journal Information:
- Proposed for publication in the Journal of Nuclear Materials., Journal Name: Proposed for publication in the Journal of Nuclear Materials.
- Country of Publication:
- United States
- Language:
- English
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