Results 61 to 70 of about 2,258 (214)

The Mechanical Behavior of the Cable-in-Conduit Conductor in the ITER Project [PDF]

open access: yes, 2018
Cable-in-conduit conductor (CICC) has wide applications, and this structure is often served to undergo heat force-electromagnetic coupled field in practical utilization, especially in the magnetic confinement fusion (e.g., Tokamak).
Yue, Donghua, Zhang, Xingyi, Zhou, Youhe
core   +2 more sources

Magneto-convective effect on tritium transport at breeder unit level for the WCLL breeding blanket of DEMO [PDF]

open access: yes, 2020
The Water-Cooled Lithium-Lead (WCLL) is one of the four breeding blanket concepts proposed by Europe in view of its DEMO reactor. The velocity field of the electrically conducting lead-lithium eutectic alloy inside the blanket is strongly influenced by ...
Alberghi, Ciro   +4 more
core   +1 more source

Core plasma ion cyclotron emission driven by fusion-born ions [PDF]

open access: yes, 2019
Ion cyclotron emission (ICE) signals whose spectral peaks match the fundamental cyclotron frequencies of hydrogen and tritium in the plasma core, near the magnetic axis, are observed in ASDEX Upgrade deuterium plasmas.
Bilato, R.   +9 more
core   +1 more source

Conceptual design of solid-type Pb x Li y eutectic alloy breeding blanket for CFETR

open access: yesNuclear Fusion, 2023
As a key component of the Chinese Fusion Engineering and Test Reactor (CFETR), the blanket is responsible for tritium breeding, neutron shielding and energy conversion.
K. Jiang, Q. Wu, L. Chen, S. Liu
doaj   +1 more source

Elevating zero dimensional global scaling predictions to self-consistent theory-based simulations

open access: yes, 2023
We have developed an innovative workflow, STEP-0D, within the OMFIT integrated modelling framework. Through systematic validation against the International Tokamak Physics Activity (ITPA) global H-mode confinement database, we demonstrated that STEP-0D ...
Candy, Jeff   +7 more
core  

Metallographic investigation of first full-size high-Jc Nb3Sn cable-in-conduit conductor after cyclic loading tests [PDF]

open access: yes
In order to verify the feasibility of applying high-Jc Nb3Sn strand in fusion magnet, a full-size cable-in-conduit conductor (CICC) with short twist pitch (STP) cable pattern was manufactured and tested in SULTAN facility at SPC, Switzerland.
Dai, Chao   +7 more
core   +1 more source

Multi-functional Dual-arm actuator system design for Tokamak divertor maintenance

open access: yesNuclear Engineering and Technology
During the remote handling maintenance of the divertor in the China Fusion Engineering Test Reactor (CFETR), a significant gap was observed between the repeatability performance of the CFETR Multipurpose Overload Robot (CMOR)—a key component—and the ...
Ruochen Yin   +4 more
doaj   +1 more source

RELAP5-based thermal-hydraulic assessment of the STEAM facility for DEMO WCLL balance of plant analysis [PDF]

open access: yes
DEMO power station aims to demonstrate the generation of hundred MWs of electrical power from fusion reactions, then transmitted from the Tokamak reactor to the grid through the Balance of Plant (BoP).
Alessandra Vannoni   +6 more
core   +1 more source

Comparative studies of tungsten erosion and edge transport under partially detached divertor condition of CFETR with neon and argon seedings

open access: yesNuclear Materials and Energy
Neon (Ne) and argon (Ar) impurity seedings are recognized as effective techniques for reducing the divertor heat load in high-power operations of future reactors like CFETR.
Hui Wang   +7 more
doaj   +1 more source

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