Optimization of tungsten castellated structures for the ITER divertor

Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F61389021%3A_____%2F15%3A00446753" target="_blank" >RIV/61389021:_____/15:00446753 - isvavai.cz</a>
Result on the web
<a href="http://dx.doi.org/10.1016/j.jnucmat.2014.11.009" target="_blank" >http://dx.doi.org/10.1016/j.jnucmat.2014.11.009</a>
DOI - Digital Object Identifier
<a href="http://dx.doi.org/10.1016/j.jnucmat.2014.11.009" target="_blank" >10.1016/j.jnucmat.2014.11.009</a>

Result language
angličtina
Original language name
Optimization of tungsten castellated structures for the ITER divertor
Original language description
In ITER, the plasma-facing components (PFCs) of the first wall and the divertor armor will be castellated to improve their thermo-mechanical stability and to limit forces due to induced currents. The fuel accumulation in the gaps may significantly contribute to the in-vessel fuel inventory. Castellation shaping may be the most straightforward way to minimize the fuel inventory and to alleviate the thermal loads onto castellations. A new castellation shape was proposed and comparative modeling of conventional (rectangular) and shaped castellation was performed for ITER conditions. Shaped castellation was predicted to be capable to operate under stationary heat load of 20 MW/m(2). An 11-fold decrease of beryllium (Be) content in the gaps of the shaped cells alone with a 7-fold decrease of carbon content was predicted
Czech name
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Czech description
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Type
J<sub>x</sub> - Unclassified - Peer-reviewed scientific article (Jimp, Jsc and Jost)
CEP classification
BL - Plasma physics and discharge through gases
OECD FORD branch
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Project
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Continuities
I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace

Publication year
2015
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

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