التفاصيل البيبلوغرافية
| العنوان: |
High Heat Flux Testing of Castellated Graphite Plasma- Facing Components |
| المؤلفون: |
Gray, T. K., Youchison, D. L., Ellis, R. E., Jaworski, M. A., Khodak, A., Looby, T., Reinke, M. L., Smalley, G., Wolfe, D. E. |
| المصدر: |
Fusion Science and Technology; January 2021, Vol. 77 Issue: 1 p9-18, 10p |
| مستخلص: |
AbstractAs part of the recovery project of the National Spherical Tokamak Experiment–Upgrade (NSTX-U), the divertor plasma-facing components (PFCs) were redesigned to handle significantly higher heat fluxes and longer pulse lengths than NSTX. The design process resulted in a castellated, graphite PFC tile. To verify the thermal performance of this design, dedicated electron beam, high heat flux (HHF) testing was carried out on a de-optimized mock-up PFC target. These tests demonstrated that the tile design is itself robust to large, localized thermal gradients. No mechanical damage to the mock-up was observed during HHF testing, though the actual PFC tile mechanical tie-down was not tested. Rather, when the surface temperature exceeded the sublimation temperature of graphite, carbon blooms from the mock-up tile surface were observed. This resulted in 1 to 2 mm of surface material ablating from the mock-up after repeated, highly localized electron beam exposures. |
| قاعدة البيانات: |
Supplemental Index |