Forced flow cryogenic cooling in fusion devices: A review
H Vaghela, VJ Lakhera, B Sarkar - Heliyon, 2021 - cell.com
The constantly increasing energy consumption along with the depleting fossil fuel resources
as well as owing to the fact that the nuclear fission not being an intrinsically safe method of …
as well as owing to the fact that the nuclear fission not being an intrinsically safe method of …
Progress in the design of the superconducting magnets for the EU DEMO
In the framework of the DEMOnstration fusion power plant (DEMO) design coordinated by
the EUROfusion consortium, a pre-conceptual design of the superconducting magnet …
the EUROfusion consortium, a pre-conceptual design of the superconducting magnet …
Effect of local defects on HTS fusion magnets performance
Local defects in the manufacturing of high temperature superconducting cable-in-conduit
conductors are known to be present at different stages of the conductor production. The …
conductors are known to be present at different stages of the conductor production. The …
Development and validation of the 4C thermal–hydraulic model of the ITER Central Solenoid modules
A Zappatore, R Bonifetto, N Martovetsky, R Zanino - Cryogenics, 2022 - Elsevier
Abstract The ITER Central Solenoid (CS) consists of a stack of six modules, each made of 40
pancakes wound with Nb3Sn Cable-In-Conduit Conductors (CICCs) cooled with …
pancakes wound with Nb3Sn Cable-In-Conduit Conductors (CICCs) cooled with …
Multi-scale 3D modelling of a DEMO prototype cable from strand to full-size conductor based on X-ray tomography and image analysis
The design of a superconducting magnet system of a fusion reactor candidate is usually
based on the Cable in Conduit Conductor (CICC) concept. CICC consist of complex …
based on the Cable in Conduit Conductor (CICC) concept. CICC consist of complex …
Friction factor of a forced-flow cooled HTS subsize-conductor for fusion magnets
Thermal–hydraulic analyses of forced-flow cooled superconducting conductors designed for
fusion magnets are typically based on 1-D mathematical models, which demand reliable …
fusion magnets are typically based on 1-D mathematical models, which demand reliable …
Hydraulic characterization of conductor prototypes for fusion magnets
M Lewandowska, A Dembkowska, R Heller… - Cryogenics, 2020 - Elsevier
Forced flow HTS conductors designed for the Winding Demonstrator (WD) or EU DEMO
Toroidal Field (TF) and Central Solenoid coils consist of several CroCo or twisted stack …
Toroidal Field (TF) and Central Solenoid coils consist of several CroCo or twisted stack …
Thermal-hydraulic analysis of the DTT CS and PF pulsed coil performance during AC operation
R Bonifetto, A Di Zenobio, L Muzzi, S Turtù… - Fusion Engineering and …, 2021 - Elsevier
The EU DEMO fusion reactor, now entering in its conceptual design phase, will have to
tackle several challenges, such as the long plasma pulse duration and the exhaust of very …
tackle several challenges, such as the long plasma pulse duration and the exhaust of very …
Parametric study and optimization of the cryo-magnetic system for EU DEMO at the pre-conceptual design phase
C Hoa, T Latella, F Bonne, B Lacroix, Q Le Coz, L Zani… - Cryogenics, 2022 - Elsevier
The pre-conceptual design phase of the EU DEMO magnet system relies on mechanical,
electromagnetic and thermal-hydraulic analyses of different conductor designs for the …
electromagnetic and thermal-hydraulic analyses of different conductor designs for the …
Analysis of the effects of thermal anchors on the reduction of the parasitic load to the EU-DEMO TF coils
The design of the superconducting magnet system of the EU-DEMO tokamak reached the
end of the pre-conceptual design phase, and a careful investigation of the parasitic heat …
end of the pre-conceptual design phase, and a careful investigation of the parasitic heat …