Abstract
The Wendelstein 7-X (W7-X) fusion experiment is aimed at proving that the stellarator concept is suitable for a future fusion reactor. Therefore, it is designed for steady-state plasmas of up to 30 min, which means that the thermal control of the plasma-facing components (PFCs) is of vital importance to prevent damage to the device.In this paper an overview of the design of the Near Real-Time Image Diagnostic System (hereinafter called “the System”) for PFCs protection in W7-X is presented. The goal of the System is to monitor the PFCs with high risk of permanent damage due to local overheating during plasma operations and to send alarms to the interlock system. The monitoring of the PFCs is based on thermographic and video cameras, and their video streams are analyzed by means of graphics processing unit–based computer vision techniques to detect the strike line, hot spots, and other thermal events. The video streams and the detected thermal events are displayed online in the control room in the form of a thermal map and permanently stored in the database. In order to determine the emissivity and maximum temperature allowed, a pixel-based correspondence between the image and the observed device part is required. The three-dimensional geometry of W7-X makes the System particularly sensitive to the spatial calibration of the cameras since hot spots can be expected anywhere, and a full segmentation of the field of view is necessary, in contrast to other regions of interest–based systems. A precise registration of the field of view and a correction of the strong lens distortion caused by the wide-angle optical system are then required.During the next operation phase the uncooled graphite divertor units will allow the System to be tested without risk of damaging the divertors in preparation for when water-cooled high-heat-flux divertors will be used.
Highlights
Wendelstein 7-X (W7-X) is a drift optimized nuclear fusion device of stellarator type build in Greifswald by the Max-Planck-Institut fur Plasmaphysik (IPP).[1]
It is designed for steady-state plasmas of up to 30 minutes, which means that the thermal control of the Plasma Facing Components (PFCs) is of vital importance to prevent damages to the device
The goal of the System is to monitor the PFCs with high risk of permanent damage due to local overheating during plasma operations and send alarms to the Interlock System
Summary
Wendelstein 7-X (W7-X) is a drift optimized nuclear fusion device of stellarator type build in Greifswald by the Max-Planck-Institut fur Plasmaphysik (IPP).[1]. The so-called OP1.2 test phase, planned for the second half of 2017 and the first half of 2018, will be used to test the Near Real-time Image Diagnostic System aimed to protect the PFCs during the steady-state operation. During this phase, an inertially cooled graphite divertor will be used, and the system will be tested without risk of damaging the divertor.
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