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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 +6 more
doaj +1 more source

Eurofusion-DEMO Divertor - Cassette Design and Integration

, 2020
The Eurofusion-DEMO design will complete the Pre Conceptual Design phase (PCD) with a PCD Gate, named G1, scheduled to take place in Q4 2020 that will focus on assessing the feasibility of the plant and its main components prior to entering into the ...
G. Mazzone +20 more
semanticscholar +1 more source

Divertor impurity seeding with a new feedback control scheme for maintaining good core confinement in grassy-ELM H-mode regime with tungsten monoblock divertor in EAST

Nuclear Fusion, 2020
Small perturbations and strong impurity exhaust capability associated with the small grassy ELMs render the grassy-ELM regime a suitable candidate for achieving steady-state H-mode operation with a radiative divertor, especially in a metal-wall device ...
G.S. Xu +35 more
semanticscholar +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 +9 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 +6 more
doaj +1 more source

Performance of Wendelstein 7-X stellarator plasmas during the first divertor operation phase

Physics of Plasmas, 2019
Wendelstein 7-X is the first comprehensively optimized stellarator aiming at good confinement with plasma parameters relevant to a future stellarator power plant. Plasma operation started in 2015 using a limiter configuration.
R. Wolf +74 more
semanticscholar +1 more source

MAST-upgrade divertor facility and assessing performance of long-legged divertors [PDF]

Journal of Nuclear Materials, 2013
16 pages, 5 ...
Fishpool, G. +9 more
openaire +2 more sources

Solitary magnetic perturbations at the ELM onset [PDF]

, 2012
Edge localised modes (ELMs) allow maintaining sufficient purity of tokamak H-mode plasmas and thus enable stationary H-mode. On the other hand in a future device ELMs may cause divertor power flux densities far in excess of tolerable material limits. The
A. Burckhart +45 more
core +2 more sources

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

Divertor Tokamak Test facility project: status of design and implementation

Nuclear Fusion
An overview is presented of the progress since 2021 in the construction and scientific programme preparation of the Divertor Tokamak Test (DTT) facility. Licensing for building construction has been granted at the end of 2021. Licensing for Cat.
D. Angeli +499 more
semanticscholar +1 more source

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