Results 21 to 30 of about 14,440 (202)

The impact of ELMs on the ITER divertor [PDF]

, 1998
Edge-Localized-Modes (ELMs) are expected to present a significant transient flux of energy and particles to the ITER divertor. The threshold for ablation of the graphite target will be reached if the ELM transient exceeds Q/t{sup 1/2} {approximately} 45 ...
Herrmann, A., Osborne, T.H., Hermann, A., Osborne, T., Lingertat, J., Leonard, A., Suttrop, W., Itami, K., Leonard, A.W., Loarte, A.   +9 more
core   +1 more source

Density dependence of SOL power width in ASDEX upgrade L-Mode

Nuclear Materials and Energy, 2017
Understanding the heat transport in the scrape-off layer (SOL) and the divertor region is essential for the design of large fusion devices such as ITER and DEMO.
B. Sieglin, T. Eich, M. Faitsch, A. Herrmann, D. Nille, A. Scarabosio, ASDEX Upgrade Team   +6 more
doaj   +1 more source

On the lifetime of the first mirrors in the diagnostic systems of the international thermonuclear experimental reactor [PDF]

, 2006
Plasma diagnostic systems will be necessary tools for the future success of the International Thermonuclear Experimental Reactor (ITER) both to better understand the physics involved in magnetically confined burning plasma and for the protection of the
Temmerman, Gregory de
core   +1 more source

Evaluation of ITER divertor shunts as a synthetic diagnostic for detachment control

Nuclear Fusion, 2023
Reliable diagnostics that measure the detached state of the ITER divertor plasma will be necessary to control heat flux to the divertor targets during steady state, burning plasma operation. This paper conducts an initial exploration into the feasibility
C.A. Orrico, T. Ravensbergen, R.A. Pitts, X. Bonnin, E. Kaveeva, J.S. Park, V. Rozhansky, I. Senichenkov, C. Watts, M. de Baar   +9 more
doaj   +1 more source

The correlation of edge plasma current, electric field and divertor condition in tokamak

Nuclear Materials and Energy, 2022
The particle transport in divertor region of current size tokamak can be affected by electric field (E) significantly through the E × B drift. The plasma current, which is associated with drifts closely, affects E.
Xuele Zhao, Chaofeng Sang, Yilin Wang, Daoyuan Liu, Chen Zhang, Dezhen Wang   +5 more
doaj   +1 more source

Divertor geometry modeling with the SOLPS-ITER code for reactor concepts with liquid metal divertors

Nuclear Materials and Energy, 2022
The SOLPS-ITER code has been applied to the analysis of the scrape-off layer (SOL) plasma associated with the fast flow Lithium (Li) divertor design for Fusion Nuclear Science Facility (FNSF).
M.S. Islam, J.D. Lore, S. Smolentsev, C.E. Kessel   +3 more
doaj   +1 more source

Investigation of the particle accumulation effects on the power exhaust of snowflake minus divertor on HL-2M tokamak by SOLPS-ITER

Nuclear Materials and Energy, 2020
To solve the power exhaust handling challenge, meanwhile maintaining acceptable divertor target erosion, the snowflake divertor (SFD) is proposed on HL-2M tokamak. In this work, simulations are carried out by using scrape-off layer plasma simulation code
Yanjie Zhang, Chaofeng Sang, Jiaxian Li, Guoyao Zheng, Chen Zhang, Daoyuan Liu, Dezhen Wang   +6 more
doaj   +1 more source

Island divertor configuration design for a quasi-axisymmetric stellarator CFQS

, 2020
0000-0002-8156-8233A magnetic field configuration of an island divertor for a quasi-axisymmetric stellarator (CFQS) is proposed. The configuration incorporates large islands surrounding the core confinement region.
LIU, Haifeng, Xiong, G., XU, Yuhong, SHIMIZU, Akihiro, KINOSHITA, Shigeyoshi, ISOBE, Mitsutaka, OKAMURA, Shoichi   +6 more
core   +1 more source

Advanced divertor configurations with large flux expansion [PDF]

, 2013
Experimental studies of the novel snowflake divertor concept (D. Ryutov, Phys. Plasmas 14 (2007) 064502) performed in the NSTX and TCV tokamaks are reviewed in this paper.
De Temmerman, G., Bell, R. E., Menard, J. E., Tal, B., Vijvers, W., Reimerdes, H., Gerhardt, S., Leblanc, B. P., Labit, B., Mueller, D. M., Diallo, A., Raman, R., Mclean, A., Podesta, M., Kaita, R., Morgan, T., Kaye, S., Canal, G. P., Maingi, R., Kolemen, E., Coda, S., Ryutov, D. D., Scotti, F., Duval, B. P., Roquemore, A. L., Paul, S. F., Zielinski, J., Soukhanovskii, V. A.   +27 more
core   +2 more sources

Conduction-based model of the Scrape-Off Layer power sharing between inner and outer divertor in diverted low-density tokamak plasmas

Nuclear Materials and Energy, 2019
A simple analytic model for the repartition of the Scrape-Off Layer (SOL) exhaust power between the inner and outer divertors in a diverted low-density tokamak plasma is introduced. Electron heat conduction is assumed to dominate the heat transport, from
R. Maurizio, B.P. Duval, B. Labit, H. Reimerdes, C. Theiler, C.K. Tsui, J. Boedo, H. De Oliveira, O. Février, U. Sheikh, M. Spolaore, K. Verhaegh, N. Vianello, M. Wensing   +13 more
doaj   +1 more source