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Behavior of W-based materials in hot helium gas

  1. 1.
    SYSNO ASEP0468207
    Druh ASEPJ - Článek v odborném periodiku
    Zařazení RIVJ - Článek v odborném periodiku
    Poddruh JČlánek ve WOS
    NázevBehavior of W-based materials in hot helium gas
    Tvůrce(i) Matějíček, Jiří (UFP-V) RID, ORCID
    Vilémová, Monika (UFP-V) RID, ORCID
    Hadraba, Hynek (UFM-A) RID, ORCID
    Di Gabriele, F. (CZ)
    Kuběna, Ivo (UFM-A) RID, ORCID
    Kolíbalová, E. (CZ)
    Michalička, J. (CZ)
    Čech, J. (CZ)
    Jäger, Aleš (FZU-D) RID, ORCID
    Zdroj.dok.Nuclear Materials and Energy
    Roč. 9, December (2016), s. 405-410
    Poč.str.6 s.
    Forma vydáníTištěná - P
    AkceInternational Conference of Fusion Reactor Material (ICFRM-17) /17./
    Datum konání11.10.2015 - 16.10.2015
    Místo konáníAachen
    ZeměDE - Německo
    Typ akceWRD
    Jazyk dok.eng - angličtina
    Země vyd.NL - Nizozemsko
    Klíč. slovatungsten ; helium ; fusion materials
    Vědní obor RIVJG - Hutnictví, kovové materiály
    Vědní obor RIV – spolupráceÚstav fyziky materiálu - Hutnictví, kovové materiály
    Fyzikální ústav - Hutnictví, kovové materiály
    CEPGA14-12837S GA ČR - Grantová agentura ČR
    Institucionální podporaUFP-V - RVO:61389021 ; UFM-A - RVO:68081723 ; FZU-D - RVO:68378271
    UT WOS000391191500069
    EID SCOPUS84963984062
    DOI10.1016/j.nme.2016.03.009
    AnotaceMaterials for the plasma facing components of future fusion reactors will be subjected to complex loading and various forms 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 ferritic–martensitic steels. The behavior of these materials in He atmosphere at elevated temperatures has been little studied thus far, and therefore is the subject of the current work.
    A number of W-based materials (pure tungsten and some of its alloys) prepared by powder metallurgy techniques was exposed to He atmosphere at 720 ºC and 500 kPa for 500 h. Morphological surface changes were observed by SEM, chemical and phase composition was analyzed by EDS and XRD, respectively. The internal microstructure was observed by a combination of SEM, FIB and TEM techniques. Mechanical properties were determined by instrumented indentation. Some alloys developed a thin oxide layer, in some cases new morphological features were observed, while some samples remained mostly intact. The observed changes are correlated with specific compositions and microstructures.
    PracovištěÚstav fyziky plazmatu
    KontaktVladimíra Kebza, kebza@ipp.cas.cz, Tel.: 266 052 975
    Rok sběru2017
Počet záznamů: 1