Overview of the EUROfusion Tokamak Exploitation programme in support of ITER and DEMO
The result's identifiers
Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F61389021%3A_____%2F24%3A00617264" target="_blank" >RIV/61389021:_____/24:00617264 - isvavai.cz</a>
Result on the web
<a href="https://iopscience.iop.org/article/10.1088/1741-4326/ad2be4" target="_blank" >https://iopscience.iop.org/article/10.1088/1741-4326/ad2be4</a>
DOI - Digital Object Identifier
<a href="http://dx.doi.org/10.1088/1741-4326/ad2be4" target="_blank" >10.1088/1741-4326/ad2be4</a>
Alternative languages
Result language
angličtina
Original language name
Overview of the EUROfusion Tokamak Exploitation programme in support of ITER and DEMO
Original language description
Within the 9th European Framework programme, since 2021 EUROfusion is operating five tokamaks under the auspices of a single Task Force called 'Tokamak Exploitation'. The goal is to benefit from the complementary capabilities of each machine in a coordinated way and help in developing a scientific output scalable to future largre machines. The programme of this Task Force ensures that ASDEX Upgrade, MAST-U, TCV, WEST and JET (since 2022) work together to achieve the objectives of Missions 1 and 2 of the EUROfusion Roadmap: i) demonstrate plasma scenarios that increase the success margin of ITER and satisfy the requirements of DEMO and, ii) demonstrate an integrated approach that can handle the large power leaving ITER and DEMO plasmas. The Tokamak Exploitation task force has therefore organized experiments on these two missions with the goal to strengthen the physics and operational basis for the ITER baseline scenario and for exploiting the recent plasma exhaust enhancements in all four devices (PEX: Plasma EXhaust) for exploring the solution for handling heat and particle exhaust in ITER and develop the conceptual solutions for DEMO. The ITER Baseline scenario has been developed in a similar way in ASDEX Upgrade, TCV and JET. Key risks for ITER such as disruptions and run-aways have been also investigated in TCV, ASDEX Upgrade and JET. Experiments have explored successfully different divertor configurations (standard, super-X, snowflakes) in MAST-U and TCV and studied tungsten melting in WEST and ASDEX Upgrade. The input from the smaller devices to JET has also been proven successful to set-up novel control schemes on disruption avoidance and detachment.
Czech name
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Czech description
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Classification
Type
J<sub>imp</sub> - Article in a specialist periodical, which is included in the Web of Science database
CEP classification
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OECD FORD branch
10305 - Fluids and plasma physics (including surface physics)
Result continuities
Project
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Continuities
I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace
Others
Publication year
2024
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů
Data specific for result type
Name of the periodical
Nuclear Fusion
ISSN
0029-5515
e-ISSN
1741-4326
Volume of the periodical
64
Issue of the periodical within the volume
11
Country of publishing house
US - UNITED STATES
Number of pages
19
Pages from-to
112019
UT code for WoS article
001325235900001
EID of the result in the Scopus database
2-s2.0-85202295883