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Simulations of fusion edge plasmas by linear plasma devices: physics and plasma–material interactions
Authors
Jeong-Sun Ahn
Min-Keun Bae
+55 more
Doo-Hee Chang
Soon-Gook Cho
Geun-Sik Choi
Heung-Gyun Choi
Yong-Sup Choi
Bo-Hyun Chung
Kyu-Sun Chung
Tae Hun Chung
Jeong-Joon Do
Bon-Cheol Goo
Suk-Ho Hong
Sung Hoon Hong
Jong-Sik Jeon
Sung-Kiu Joo
Seo Jin Jung
Seok-Won Jung
Yong Ho Jung
Young-Dae Jung
In Je Kang
Beom-Sik Kim
Gon-Ho Kim
Heung-Su Kim
Hye-Ran Kim
Jae Yong Kim
Jin-Hee Kim
Jin-Woo Kim
Jong-Il Kim
Kyung-Cheol Kim
Myung Kyu Kim
Sang-You Kim
Yong-Kyun Kim
Kwang-Cheol Ko
Gyea Young Kwak
Byoung-Kyu Lee
Dong-Han Lee
Heon-Ju Lee
Min Ji Lee
Myoung-Jae Lee
Seung-Hwa Lee
Taihyeop Lho
Seung Jeong Noh
Byung-Hoon Oh
Cha-Hwan Oh
Hye Taek Oh
Young-Suk Oh
Eun-Kyung Park
In Sun Park
Sang Joon Park
Young-Jun Seo
Dong Chan Seok
Yun-Keun Shim
Jong Ho Sun
Hyun-Jong Woo
Hun Suk You
Hyun Jong You
Publication date
1 April 2022
Publisher
한국물리학회
Abstract
© 2022, The Korean Physical Society.Because a fusion edge plasma contains various atomic and molecular processes, along with various plasma–material interactions (PMIs) for post-mortem analyses, a linear plasma device can simulate divertor and scrape-off layer (SOL) plasmas with DC edge relevant parameters, although it cannot generate a high ion temperature and toroidicity with much less power density compared to toroidal devices. The Divertor Plasma Simulator-2 (DiPS-2), a linear device with an LaB6 DC cathode, has been used for a few fusion-relevant physics experiments, including edge localized mode (ELM) simulation and edge transport of diffusion and convection. An ELM simulation has been performed by modulating the magnetic field relevant to the pressure modulation of a toroidal device, and the diffusion coefficients of free and bound presheaths have been measured in simulations of divertor or limiter transport. Moreover, the convection of the filament or the bubble expansion to the first wall has also been analyzed. In addition to various atomic and molecular processes in SOL and divertor plasmas, PMIs must be analyzed both on and beneath the surface of the plasma-facing components (PFCs) because of surface modification. Using DiPS-2 and other linear devices along with Korea Superconducting Tokamak Advanced Research (KSTAR), PMIs have been analyzed in terms of the following elements or processes: (1) boronizations, both for dust interactions with the surface chamber (DiSC) and KSTAR device, are analyzed; (2) carbon damage by the dense heat flux of DiPS-2 is experimentally investigated; (3) the density profile of the lithium injection gettering of hydrogen and its transport experiments (LIGHT-1) device is analytically calculated; (4) the effect of nitrogen on the relaxation of the heat flux to the divertor tile is experimentally analyzed; and (5) tungsten as the divertor tile material is analyzed via laser ELM simulations in terms of dust generation and surface modification.N
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Last time updated on 06/07/2022