Advance in the conceptual design of the European DEMO magnet system
The result's identifiers
Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F61389021%3A_____%2F20%3A00536804" target="_blank" >RIV/61389021:_____/20:00536804 - isvavai.cz</a>
Alternative codes found
RIV/68378271:_____/20:00536804 RIV/26722445:_____/20:N0000026
Result on the web
<a href="https://iopscience.iop.org/article/10.1088/1361-6668/ab75a9#artAbst" target="_blank" >https://iopscience.iop.org/article/10.1088/1361-6668/ab75a9#artAbst</a>
DOI - Digital Object Identifier
<a href="http://dx.doi.org/10.1088/1361-6668/ab75a9" target="_blank" >10.1088/1361-6668/ab75a9</a>
Alternative languages
Result language
angličtina
Original language name
Advance in the conceptual design of the European DEMO magnet system
Original language description
The European DEMO, i.e. the demonstration fusion power plant designed in the framework of the Roadmap to Fusion Electricity by the EUROfusion Consortium, is approaching the end of the pre-conceptual design phase, to be accomplished with a Gate Review in 2020, in which all DEMO subsystems will be reviewed by panels of independent experts. The latest 2018 DEMO baseline has major and minor radius of 9.1 m and 2.9 m, plasma current 17.9 MA, toroidal field on the plasma axis 5.2 T, and the peak field in the toroidal-field (TF) conductor 12.0 T. The 900 ton heavy TF coil is prepared in four lowerature-superconductor (LTS) variants, some of them differing slightly, other significantly, from the ITER TF coil design. Two variants of the CS coils are investigated a purely LTS one resembling the ITER CS, and a hybrid coil, in which the innermost layers made of HTS allow the designers either to increase the magnetic flux, and thus the duration of the fusion pulse, or to reduce the outer radius of the CS coil. An issue presently investigated by mechanical analyzes is the fatigue load. Two variants of the poloidal field coils are being investigated. The magnet and conductor design studies are accompanied by the experimental tests on both LTS and HTS prototype samples, covering a broad range of DC and AC tests. Testing of quench behavior of the 15 kA HTS cables, with size and layout relevant for the fusion magnets and cooled by forced flow helium, is in preparation.
Czech name
—
Czech description
—
Classification
Type
J<sub>imp</sub> - Article in a specialist periodical, which is included in the Web of Science database
CEP classification
—
OECD FORD branch
10305 - Fluids and plasma physics (including surface physics)
Result continuities
Project
<a href="/en/project/8D15001" target="_blank" >8D15001: Project ID 633053 - EUROfusion</a><br>
Continuities
I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace
Others
Publication year
2020
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů
Data specific for result type
Name of the periodical
Superconductor Science and Technology
ISSN
0953-2048
e-ISSN
—
Volume of the periodical
33
Issue of the periodical within the volume
4
Country of publishing house
GB - UNITED KINGDOM
Number of pages
9
Pages from-to
044013
UT code for WoS article
000518697500001
EID of the result in the Scopus database
2-s2.0-85082398376