Results 21 to 30 of about 16,994 (249)

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

Investigation of the Helical Divertor Function and the Future Plan of a Closed Divertor for Efficient Particle Control in the LHD Plasma Periphery [PDF]

, 2009
The function of the divertor plasmas on the particle control in the plasma periphery is investigated from viewpoints of magnetic field line structures and neutral particle transport in the Large Helical Device (LHD).
SAKAUE, A, KOMORI, Akio, IWAMAE, Atsushi, LHD Experiment Group, KOBAYASHI, Masahiro, MORISAKI, Tomohiko, SHOJI, Mamoru, GOTO, Motoshi, MASUZAKI, Suguru, YAMADA, H.   +9 more
core   +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

Design of the divertor and power exhaust scenarios development for the Divertor Tokamak Test facility

, 2022
The new high field superconducting divertor tokamak test facility (DTT) [1] presently under construction is devoted to specifically study power exhaust solutions in regimes as close as possible to those foreseen in DEMO fusion reactor in terms of power ...
Innocente P, Castaldo A, Roccella S, Brezinsek S, Uccello A, Crisanti F, Ambrosino R, Calabrò G, Neu R, Rubino G, Dose G   +10 more
core  

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

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

Design of a Closed Helical Divertor in LHD and the Prospect for Helical Fusion Reactors [PDF]

, 2017
A new closed helical divertor configuration for efficient particle control and reduction of the heat load on the divertor plates is proposed. The closed divertor configuration practically utilizes an ergodic layer and magnetic field line configuration on
YAMADA, Hiroshi, the LHD Experimental Groups,, LHD Experimental Groups,, LHD Experimental Group,, SAGARA, Akio, KOMORI, Akio, KOBAYASHI, Masahiro, SHOJI, Mamoru, MASUZAKI, Suguru, the LHD Experimental Group,   +9 more
core   +1 more source

Analysis of indefinite divertor footprint with proper orthogonal decomposition in hydrogen/deuterium plasmas in LHD

Nuclear Materials and Energy, 2019
Divertor particle flux signals on divertor plates were analyzed with the multivariable analysis technique, namely, proper orthogonal decomposition (POD), to characterize the indefinite divertor footprint in the Large Helical Device.
H. Tanaka, S. Masuzaki, G. Kawamura, M. Kobayashi, Y. Suzuki, T. Morisaki, N. Ohno   +6 more
doaj   +1 more source

Membrane composition and thermodynamic identity as boundaries of life for synthetic cell research

FEBS Letters, EarlyView.
What makes a cell a cell? The boundary of a living cell is not just a wall. Read as a Markov blanket, the membrane separates internal from external states, generating identity and non‐equilibrium order. Can this identity be rebuilt from scratch in a synthetic cell?
Caterina Presutti, Bert Poolman
wiley   +1 more source