Fusion Engineering and Design
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* Dữ liệu chỉ mang tính chất tham khảo
Sắp xếp:
High heat flux engineering for the upgraded neutral beam injection systems of MAST-U
Fusion Engineering and Design - Tập 96 - Trang 458-462 - 2015
Lithium cooled blanket of RF DEMO reactor
Fusion Engineering and Design - Tập 49 - Trang 457-465 - 2000
Engineering challenges and development of the ITER Blanket System and Divertor
Fusion Engineering and Design - Tập 96 - Trang 34-41 - 2015
Nuclear analysis of the ITER radial neutron camera architectural options
Fusion Engineering and Design - Tập 123 - Trang 1033-1038 - 2017
Systems engineering approach for the iterative concept design and virtual simulation of the DTT hyper redundant manipulator
Fusion Engineering and Design - Tập 190 - Trang 113534 - 2023
Prospects of High Temperature Superconductors for fusion magnets and power applications
Fusion Engineering and Design - Tập 88 - Trang 440 - 2013
During the last few years, progress in the field of second-generation High Temperature Superconductors (HTS) was breathtaking. Industry has taken up production of long length coated REBCO conductors with reduced angular dependency on external magnetic field and excellent critical current density jc. Consequently these REBCO tapes are used more and more in power application. For fusion magnets, high current conductors in the kA range are needed to limit the voltage during fast discharge. Several designs for high current cables using High Temperature Superconductors have been proposed. With the REBCO tape performance at hand, the prospects of fusion magnets based on such high current cables are promising. An operation at 4.5K offers a comfortable temperature margin, more mechanical stability and the possibility to reach even higher fields compared to existing solutions with Nb3Sn which could be interesting with respect to DEMO. After a brief overview of HTS use in power application the paper will give an overview of possible use of HTS material for fusion application. Present high current HTS cable designs are reviewed and the potential using such concepts for future fusion magnets is discussed.
#High Temperature Superconductor #HTS #High current cable #Fusion #Magnet
Membrane gas-liquid contactor for tritium extraction from Pb-Li alloys
Fusion Engineering and Design - Tập 158 - Trang 111737 - 2020
3D tritium transport analysis for WCCB blanket based on COMSOL
Fusion Engineering and Design - Tập 151 - Trang 111405 - 2020
Cavitation inception upstream of liquid lithium target for intense fusion neutron source
Fusion Engineering and Design - Tập 124 - Trang 990-994 - 2017
Effect of doped niobium on the microstructure and properties of W–Nb/TiC composites prepared by spark plasma sintering
Fusion Engineering and Design - Tập 90 - Trang 62-66 - 2015
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