Abstract
Understanding the erosion of plasma facing components in fusion devices is vital, particularly for long-pulse operations. This study presents the application of synthetic optical diagnosis on the all-W WEST tokamak. The analysis reveals reflections as significant contributors to measured emission, varying across main chamber limiters and divertor targets. Reflections at divertor locations can be up to 50% of measured emission while 95% at limiter locations. Oxygen is investigated as a proxy for low-Z species and underscores the importance of reflections in interpreting optical diagnostics, especially for validating plasma-material interactions and scrape-off layer impurity transport codes. As more fusion devices adopt full metal walls, the accurate assessment of reflections will become increasingly crucial for erosion analysis and plasma control.
Original language | English |
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Article number | 123505 |
Journal | Review of Scientific Instruments |
Volume | 95 |
Issue number | 12 |
DOIs | |
State | Published - Dec 1 2024 |
Funding
The authors would like to thank Ekin Ozturk for developing the volume emission addition to Mitsuba 3 and for the helpful discussions. The authors would also like to thank Alexandra Fisher for proofreading the manuscript. This work was funded under U.S. DOE Contract No. DE-AC05-00OR22725.