Results 101 to 110 of about 96,750 (196)

Tungsten Material Behavior under H₂, D₂, and He Plasma Interaction Conditions in the Framework of Fusion-Relevant Studies. [PDF]

Materials (Basel), 2023
Stancu C, Marascu V, Bonciu A, Bercea A, Stoica SD, Constantin C.   +5 more
europepmc   +1 more source

Runaway electrons and their interaction with tungsten wall: a comprehensive study of effects. [PDF]

Sci Rep, 2023
Ataeiseresht L, Abdi MR, Pourshahab B, Rasouli C.   +3 more
europepmc   +1 more source

Erosion enhancement by impurity entrainment in the highly collisional plasmas of Magnum-PSI

Nuclear Fusion
Extrinsic impurity seeding is planned for ITER to avoid high heat fluxes to the tungsten divertor targets. Nevertheless, excessive sputtering by impurities would lead to a reduction in fusion power output and divertor lifetime.
Mark J.H. Cornelissen, Jordy W.M. Vernimmen, Jesse D.E. Verstappen, Erwin Zoethout, Ivo G.J. Classen, Job Beckers, Thomas W. Morgan   +6 more
doaj   +1 more source

Improved material mixing model in ERO2.0: Nonlinear effect of boron concentration on tungsten sputtering and influx from mixed tungsten-boron surfaces

Nuclear Materials and Energy
An upgraded homogeneous mixing model for plasma-facing surfaces in ERO2.0 has been developed using a database of SDTrimSP mixed-material simulations, replacing earlier linear interpolation between pure-material sputtering yields. The SDTrimSP simulations
H.A. Kumpulainen, S. Brezinsek, J. Romazanov, A. Kirschner, C. Baumann, K. Schmid   +5 more
doaj   +1 more source

Novel concept suppressing plasma heat pulses in a tokamak by fast divertor sweeping. [PDF]

Sci Rep, 2022
Horacek J, Lukes S, Adamek J, Havlicek J, Entler S, Seidl J, Cavalier J, Cikhardt J, Sedmidubsky V.   +8 more
europepmc   +1 more source

Validation of Integrated Modelling of KSTAR Plasmas with Carbon Divertor using JINTRAC and Prediction for Tungsten Divertor

The JINTRAC integrated modelling suite has been adapted for the KSTAR tokamak, with its primary goal being the establishment of a core-edge integrated modelling framework for predictive analysis of KSTAR plasmas.
Chan-Young Lee, Beomsu Kim, JAEGON LEE, Francis J Casson, SeulChan Hong, Yong-Su Na, Sun Hee Kim, Florian Koechl, Boseong Kim, Romain Futtersack   +9 more
core   +1 more source

Experimental research on the deeply detached X-point radiator regime on EAST

Nuclear Fusion
Radiative divertor detachment with impurity seeding is considered one of the most promising means for mitigating particle and heat fluxes on the divertor target.
Baoguo Wang, Rong Yan, Kedong Li, Dahuan Zhu, Rui Ding, Beihe Zhang, Kai Wu, Xin Lin, Binfu Gao, Lingyi Meng, Jianhua Yang, Lin Yu, Yanmin Duan, Jinju Yang, Kangning Geng, Qing Zhang, Tao Zhang, Fudi Wang, Yifei Jin, Hailin Zhao, Bin Zhang, Pengfei Zhou, Chunyu He, Yang Wang, Liang Wang, Junling Chen, the EAST Team   +26 more
doaj   +1 more source

New proposed ITER divertor design using carbon insert on tungsten to mitigate ELMs and secondary radiation effects on nearby components. [PDF]

Sci Rep, 2022
Sizyuk V, Hassanein A.
europepmc   +1 more source

Numerical Studies on Divertor Plasmas in Helical Systems

, 1990
"Scrape-off layer and divertor plasmas in helical systems are studied by using the two-dimensional (2D) numerical simulation code. Unified Edge Divertor Analysis code (UEDA code) is applied to the straight helical model of torsatron/helical heliotron ...
Itoh, S.-I.", Itoh, K., "Ueda, N.
core  

Microengineering Design for Advanced W-Based Bulk Materials with Improved Properties. [PDF]

Nanomaterials (Basel), 2023
Galatanu M, Enculescu M, Galatanu A, Ticos D, Dumitru M, Ticos C.   +5 more
europepmc   +1 more source