Results 71 to 80 of about 14,440 (202)

Survey of tungsten gross erosion from main plasma facing components in WEST during a L-mode high fluence campaign

Nuclear Materials and Energy
An initial high fluence campaign was performed in WEST, in 2023, on the newly installed actively cooled tungsten divertor composed of ITER-grade monoblocks.
N. Fedorczak, C. Arnas, L. Cappelli, L. Colas, Y. Corre, M. Diez, A. Gallo, J. Gaspar, A. Grosjean, C. Guillemaut, J.P. Gunn, C. Johnson, C. Martin, E. Tsitrone, E.A. Unterberg, J. Bucalossi   +15 more
doaj   +1 more source

Divertor asymmetry and scrape-off layer flow in various divertor configurations in Experimental Advanced Superconducting Tokamak [PDF]

, 2012
Divertor asymmetry and its dependence on the ion del B direction has been investigated in the Experimental Advanced Superconducting Tokamak by changing the divertor configuration from lower single null (LSN), via double null (DN), to upper single null ...
Liu, P., Zhu, S. Z., T. F. Ming, H. Y. Guo, Jiang, M., M. Jiang, EAST Team, Wang, H. Q., W. Zhang, Yan, Ning, Chang, J. F., L. M. Shao, Zhang, W., Wang, L., Ding, S. Y., G. S. Xu, Luo, G. N., Xu, Guandong, L. Wang, Ming, T. F., X. Gao, S. Y. Ding, H. Xiong, P. Liu, Gao, X., H. Q. Wang, D. S. Wang, J. F. Chang, S. C. Liu, Wang, D. S., N. Yan, G. N. Luo, Shao, L. M., Liu, S. C., S. Z. Zhu, Z. W. Wu, Guo, H. Y., Xiong, H., Wu, Zhuang   +38 more
core   +1 more source

Effects of N/Ne impurity seeding on the divertor asymmetry in HL-2A tokamak

Nuclear Fusion
Divertor asymmetry is a major challenge in achieving high-power, long-pulse discharges in future fusion reactors. Impurity seeding is the most common method for achieving divertor detachment in fusion devices.
Qingyi Tan, Haoran Ye, Xueyu Gong, Yijun Zhong, Qianhong Huang, Zhe Wang, Chengzhi Cao, Zhanhui Wang, Cailong Fu, Min Xu, Tao Yang   +10 more
doaj   +1 more source

Tungsten as a Structural Divertor Material

Advances in Science and Technology, 2010
Refractory materials, in particular tungsten base materials are considered as primary candidates for structural high heat load applications in future nuclear fusion power plants. Promising helium-cooled divertor design outlines make use of their high heat conductivity and strength. The upper operating temperature limit is mainly defined by the onset of
Rieth, M., Armstrong, D., Dafferner, B., Heger, S., Hoffmann, A., Hoffmann, M. D., Jäntsch, U., Kübel, C., Materna-Morris, E., Reiser, J., Rohde, M., Scherer, T., Widak, V., Zimmermann, H.   +13 more
openaire   +4 more sources

Mechanical and electrical integration of the DTT divertor in the vacuum vessel [PDF]

openLa tesi consiste nell'utilizzo di un videoterminale messo a disposizione dal consorzio RFX al fine di condurre simulazioni con server di calcolo e di modellazione sul divertore.
BOVO, SAMUELE
core  

Spectroscopy of divertor plasmas [PDF]

, 1995
The requirements for divertor spectroscopy are treated with respect to instrumentation and observations on present machines. Emphasis is placed on quantitative measurements.of impurity concentrations from the interpretation of spectral line intensities ...
Isler, R. C., R. C. Isler
core   +1 more source

Audizione su realizzazione della infrastruttura di ricerca per l'avvio e l'implementazione del progetto Divertor Tokamak Test - X Commissione Attività Produttive della Camera dei Deputati

, 2017
Convocazione della X Commissione (ATTIVITA' PRODUTTIVE, COMMERCIO E TURISMO) Lunedì 3 aprile 2017 Audizioni nell'ambito della discussione congiunta delle risoluzioni 7-01195 Bargero e 7-01227 Crippa, relative alla realizzazione della infrastruttura di
Raffaele Albanese
core  

Snowflake divertor configuration studies for NSTX-Upgrade [PDF]

, 2011
Snowflake divertor experiments in NSTX provide basis for PMI development toward NSTX-Upgrade. Snowflake configuration formation was followed by radiative detachment. Significant reduction of steady-state divertor heat flux observed in snowflake divertor.
Soukhanovskii, V A
core  

Radiative divertor studies in JET high confinement mode plasmas [PDF]

, 2015
Controlled power exhaust is one of the key challenges in reactor scale fusion devices. These devices must maintain heat loads less than 10 MW/m2 at the plasma-facing materials (PFM), while producing gigawatts of fusion power.
Järvinen, Aaro
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