U.S. Department of EnergyOffice of Scientific and Technical Information
Rapidly Moving Divertor Plates In A Tokamak
Abstract
It may be possible to replace conventional actively cooled tokamak divertor plates with a set of rapidly moving, passively cooled divertor plates on rails. These plates would absorb the plasma heat flux with their thermal inertia for ~10-30 sec, and would then be removed from the vessel for processing. When outside the tokamak, these plates could be cooled, cleaned, recoated, inspected, and then returned to the vessel in an automated loop. This scheme could provide nearoptimal divertor surfaces at all times, and avoid the need to stop machine operation for repair of damaged or eroded plates. We describe various possible divertor plate designs and access geometries, and discuss an initial design for a movable and removable divertor module for NSTX-U.
- Authors:
- Publication Date:
- Research Org.:
- Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
- Sponsoring Org.:
- USDOE Office of Science (SC)
- OSTI Identifier:
- 1014566
- Report Number(s):
- PPPL-4622
TRN: US1102615
- DOE Contract Number:
- DE-ACO2-09CH11466
- Resource Type:
- Conference
- Resource Relation:
- Conference: TOFE-19 Conference, Las Vegas, NV (November 7-11, 2010)
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 70 PLASMA PHYSICS AND FUSION TECHNOLOGY; DESIGN; DIVERTORS; HEAT FLUX; PLASMA; PLATES; PROCESSING; REPAIR; Divertors, Tokamaks, Plasma Wall Interaction
Citation Formats
Zweben, S. Rapidly Moving Divertor Plates In A Tokamak. United States: N. p., 2011.
Web.
Zweben, S. Rapidly Moving Divertor Plates In A Tokamak. United States.
Zweben, S. 2011.
"Rapidly Moving Divertor Plates In A Tokamak". United States. https://www.osti.gov/servlets/purl/1014566.
@article{osti_1014566,
title = {Rapidly Moving Divertor Plates In A Tokamak},
author = {Zweben, S},
abstractNote = {It may be possible to replace conventional actively cooled tokamak divertor plates with a set of rapidly moving, passively cooled divertor plates on rails. These plates would absorb the plasma heat flux with their thermal inertia for ~10-30 sec, and would then be removed from the vessel for processing. When outside the tokamak, these plates could be cooled, cleaned, recoated, inspected, and then returned to the vessel in an automated loop. This scheme could provide nearoptimal divertor surfaces at all times, and avoid the need to stop machine operation for repair of damaged or eroded plates. We describe various possible divertor plate designs and access geometries, and discuss an initial design for a movable and removable divertor module for NSTX-U.},
doi = {},
url = {https://www.osti.gov/biblio/1014566},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Mon May 16 00:00:00 EDT 2011},
month = {Mon May 16 00:00:00 EDT 2011}
}