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Tritium Migration in HCLL and WCLL Blankets: Impact of Tritium Solubility in Liquid Pb-17Li

contributor authorSantucci, Alessia
contributor authorCiampichetti, A.
contributor authorDemange, D.
contributor authorFranza, F.
contributor authorTosti, Silvano
date accessioned2020-03-12T23:49:30Z
date available2020-03-12T23:49:30Z
date issued2014
identifier issn0093-3813
identifier other6750113.pdf
identifier urihttps://libsearch.um.ac.ir:443/fum/handle/fum/1124659?locale-attribute=en&show=full
formatgeneral
languageEnglish
publisherIEEE
titleTritium Migration in HCLL and WCLL Blankets: Impact of Tritium Solubility in Liquid Pb-17Li
typeJournal Paper
contenttypeMetadata Only
identifier padid8304206
subject keywordsTokamak devices
subject keywordsfusion reactor blankets
subject keywordslead alloys
subject keywordslithium alloys
subject keywordsplasma toroidal confinement
subject keywordstritium handling
subject keywordsArrhenius plot magnitude
subject keywordsFUS-TPC code
subject keywordsHCLL blanket
subject keywordsWCLL blanket
subject keywordsaccurate experiments
subject keywordsbreeding blanket
subject keywordscomputational code
subject keywordsconsolidate liquid blanket material
subject keywordsdifferent K<
subject keywordssub>
subject keywordsS<
subject keywords/sub>
subject keywordsvalues
subject keywordsenvironmental release
subject keywordseutectic lithium-lead alloy
subject keywordshelium-cooled lead-lithium DEMO BB
subject keywordshydrogen Sieverts constant
subject keywordshydrogen isotope interactions
subject keywordshydrogen isotope solubilit
identifier doi10.1109/TPS.2014.2305759
journal titlePlasma Science, IEEE Transactions on
journal volume42
journal issue4
filesize839457
citations0


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