Journal
NUCLEAR FUSION
Volume 61, Issue 9, Pages -Publisher
IOP PUBLISHING LTD
DOI: 10.1088/1741-4326/ac0f97
Keywords
helium plasmas; pedestal structure; EPED; DIII-D; ITER
Categories
Funding
- National Key R&D Program of China [2019YFE03040004]
- Comprehensive Research Facility for Fusion Technology Program of China [2018-000052-73-01-001228]
- National Natural Science Foundation of China [11675221]
- US DOE [DE-FC02-04ER54698, DE-FG02-95ER54309]
- China Scholarship Council
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Helium (He) plasmas are used to test systems and plasma diagnostics during the ITER non-nuclear phase, with good agreement found between pedestal width and height in recent experiments. The EPED/REPED pedestal model is applicable for predicting helium plasma pedestal structure and indicates similarities in pedestal height between helium and deuterium (D) plasmas, with helium having a slightly wider pedestal.
Helium (Ile) plasmas will be used to test the operationally relevant systems and plasma diagnostics during the ITER non-nuclear phase. Analyses of pedestal width and height in recent DIII-D H-mode experiments in He plasmas find good agreement with Delta(psi) = 0.095 beta(1/2)(p.ped) between the pedestal width Delta(psi) and the square root of the poloidal pedestal beta beta(1/2)(p.ped) from experimental observations. The EPED/REPED pedestal model is found to be applicable to predict the pedestal structure of the He plasma from comparison of predictions with experiments. Furthermore, it indicates that the pedestal height of lie and deuterium (D) plasmas are similar from the REPED predictions with the same global parameters, and the pedestal width of He is approximately 6% larger than that of D.
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