Results 91 to 100 of about 100,982 (265)
Cryopump and fuelling location impacts on upstream density and detachment on MAST-Upgrade
A cryopump was installed in the MAST Upgrade (MAST-U) lower divertor at the start of its fourth scientific campaign (MU04) to enhance density control, detachment front management, and impurity removal, while expanding the operational space to lower ...
Q. Xia +8 more
doaj +1 more source
Assessment of X-point target divertor configuration for power handling and detachment front control
A study of long-legged tokamak divertor configurations is performed with the edge transport code UEDGE (Rognlien et al., J. Nucl. Mater. 196, 347, 1992). The model parameters are based on the ADX tokamak concept design (LaBombard et al., Nucl. Fusion 55,
M.V. Umansky +6 more
doaj +1 more source
Heat Load Mitigation Studies in the W7‐X Stellarator Experiment
ABSTRACT During the experiments at the stellarator Wendelstein 7‐X (W7‐X) with fully water‐cooled plasma‐facing components (PFC), including carbon‐fiber composite (CFC) divertor targets with a thermal load capability of 10 MW/m2, high performance was achieved.
Dirk Naujoks +11 more
wiley +1 more source
Experimental research on the deeply detached X-point radiator regime on EAST
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 +26 more
doaj +1 more source
Current convective instability in detached divertor plasma
The asymmetry of inner and outer divertors, which cause the inner divertor to detach first, while the outer one is still attached, results in the large temperature difference between the vicinities of inner and outer targets and the onset of large electric potential drop through detached plasma of the inner divertor.
S. I. Krasheninnikov, A. I. Smolyakov
openaire +2 more sources
Effect of divertor geometry on plasma detachment in DIII-D [PDF]
This paper explores the physics of the recently installed Radiative Divertor Plasma divertor (RDP) in DIII-D through the use of UEDGE simulation with experimentally derived plasma parameters.
Wolf, N. S., Dickinson College, LLNL
core
First SOLPS‐ITER Simulation Study of Japanese DEMO on Leakage of Seeded Ar Impurity
ABSTRACT For JA DEMO, one of the grand challenges is efficiently handling the extreme power loads onto plasma‐facing components, particularly the divertor targets. Impurity seeding is an essential strategy for increasing the radiation losses and thereby reducing the heat load on the targets.
Hang Si +6 more
wiley +1 more source
Study of lithium vapor flow in a detached divertor using DSMC code
A detached divertor is predicted to be necessary to handle the heat fluxes of a demonstration fusion power plant. The lithium vapor box divertor localizes dense lithium vapor to cause stable detachment.
E.D. Emdee +4 more
doaj +1 more source
This study presents large‐scale similarity model testing (geometric ratio 3.6) of an innovative multiple‐layered lining system—comprising exterior precast segments, middle self‐compacting concrete, and an interior steel pipe—for high‐pressure (0.75 MPa) water conveyance tunnels.
Ramin Asadi +4 more
wiley +1 more source
Modeling and experimental investigation of the distribution of seeded impurities and their influence on divertor detachment in all-metal tokamaks is critical for developing reactor-scale exhaust scenarios. In this work, the degree and operating space for
B. Lomanowski +11 more
doaj +1 more source

