Feasibility study of fast swept divertor strike point suppressing transient heat fluxes in big tokamaks.
The result's identifiers
Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F61389021%3A_____%2F17%3A00481373" target="_blank" >RIV/61389021:_____/17:00481373 - isvavai.cz</a>
Result on the web
<a href="http://dx.doi.org/10.1016/j.fusengdes.2017.01.027" target="_blank" >http://dx.doi.org/10.1016/j.fusengdes.2017.01.027</a>
DOI - Digital Object Identifier
<a href="http://dx.doi.org/10.1016/j.fusengdes.2017.01.027" target="_blank" >10.1016/j.fusengdes.2017.01.027</a>
Alternative languages
Result language
angličtina
Original language name
Feasibility study of fast swept divertor strike point suppressing transient heat fluxes in big tokamaks.
Original language description
n order to avoid metal surface melting of divertor targets of big tokamak fusion reactors by localized ELM heat loads, sudden detachment loss or VDEs, we study a new technique of spreading the heat flux by harmonic divertor strike point sweeping using a dedicated divertor coil. We ran 2D dynamic heat conduction simulation using real infra-red data of large ELMs heat fluxes on JET divertor target, rescaled for EU DEMO reactor (B-0 = 6 T, I-p =21 MA, R-0 = 9 m). Aiming for the surface temperature suppression factor of 4, this requires sweeping with amplitude*frequency=7cm*2 kHz. Building the divertor coil out of 27 tons of copper, this requires 0.8 MW cooling. Triggered by analog divertor heat flux signal, dedicated dynamic Fiesta simulation scenario requires 54 capacitive energy storages at 1500 V (6mF) discharged into 54 divertor coils, each with AC current of 130kA for each ELM event for similar to 4 ms (with waiting time 40 ms). The Ix B-tor forces would yield less than 0.1 mm rotational vibrations of the coil at the ELM frequency (similar to 20 Hz). The DEMO divertor surface temperature suppression reaches factor of 9 with 18 kV, 20 cm, 7.5 kHz, 400 kA. We also calculate system requirements (0.6mF, 5 kV & 60kA -> suppression factor = 2) for ASDEX Upgrade using the upper divertor coil. Since we found no show-stoppers, this technique seems attractive for big tokamaks.
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
20305 - Nuclear related engineering; (nuclear physics to be 1.3);
Result continuities
Project
Result was created during the realization of more than one project. More information in the Projects tab.
Continuities
P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)
Others
Publication year
2017
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů
Data specific for result type
Name of the periodical
Fusion Engineering and Design
ISSN
0920-3796
e-ISSN
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Volume of the periodical
123
Issue of the periodical within the volume
November
Country of publishing house
CH - SWITZERLAND
Number of pages
4
Pages from-to
646-649
UT code for WoS article
000418992000134
EID of the result in the Scopus database
2-s2.0-85011103413