Behavior of w-based materials in hot helium gas

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F15%3A%230001091" target="_blank" >RIV/26722445:_____/15:#0001091 - isvavai.cz</a>

Výsledek na webu

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DOI - Digital Object Identifier

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Jazyk výsledku

angličtina

Název v původním jazyce

Behavior of w-based materials in hot helium gas

Popis výsledku v původním jazyce

Poster at 17th International Conference on Fusion Reactor Materials Oct 11-16, 2015. Materials for the plasma facing components of future fusion reactors will be subjected to complex loading and various form of interaction with low Z species (hydrogen isotopes and helium). The divertor components will be among the most intensely loaded, as they will have to transfer heat loads up to 10-20 MW/m2. Besides the plasma facing surface being irradiated by highly energetic deuterium, tritium and helium particles from the burning plasma, the opposite surface will be exposed to a cooling medium at elevated temperature. Helium- and water-based cooling systems are currently being considered. While tungsten is the prime candidate material for the plasma facing components, in the helium-cooled divertor designs, it is also foreseen as a structural material, together with ODS steels. The behavior of these materials in He atmosphere at elevated temperatures has been little studied so far, and thus is t

Název v anglickém jazyce

Behavior of w-based materials in hot helium gas

Popis výsledku anglicky

Poster at 17th International Conference on Fusion Reactor Materials Oct 11-16, 2015. Materials for the plasma facing components of future fusion reactors will be subjected to complex loading and various form of interaction with low Z species (hydrogen isotopes and helium). The divertor components will be among the most intensely loaded, as they will have to transfer heat loads up to 10-20 MW/m2. Besides the plasma facing surface being irradiated by highly energetic deuterium, tritium and helium particles from the burning plasma, the opposite surface will be exposed to a cooling medium at elevated temperature. Helium- and water-based cooling systems are currently being considered. While tungsten is the prime candidate material for the plasma facing components, in the helium-cooled divertor designs, it is also foreseen as a structural material, together with ODS steels. The behavior of these materials in He atmosphere at elevated temperatures has been little studied so far, and thus is t

Druh

O - Ostatní výsledky

CEP obor

JF - Jaderná energetika

OECD FORD obor

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Projekt

<a href="/cs/project/ED2.1.00%2F03.0108" target="_blank" >ED2.1.00/03.0108: Udržitelná energetika</a><br>

Návaznosti

P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)

Rok uplatnění

2015

Kód důvěrnosti údajů

S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů