The Mechanical Behavior of the Cable-in-Conduit Conductor in the ITER Project [PDF]
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]
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]
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
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
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]
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
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]
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
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
Feasibility Study to Byproduce Medical Radioisotopes in a Fusion Reactor. [PDF]
Li J, Zheng S.
europepmc +1 more source

