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Stability of advanced breeder pebbles in water containing purge gas atmosphere

Kolb, M. H. H.; Knitter, R. ORCID iD icon; Hoshino, T.


Solid breeder blankets are widely considered as attractive blanket concepts for a future DEMO reactor and will be tested in ITER by a number of parties. Ceramic breeder pebble beds are the major functional component of such breeder blankets. The principal task of the individual breeder pebbles is the generation of tritium by transmutation of lithium through neutron capture. Yet, the pebbles must not significantly degrade during use to allow for safe operation ofthe blanket. Currently the design of the outer tritium fuel cycle uses helium with 0.1% of hydrogen as purge gas for the generated tritium, which is also released as tritiated water besides hydrogen isotopologues. As there is a difference of orders of magnitude between the expected concentration of tritium and the hydrogen content, the separation of both is challenging and costly. A change to water replacing hydrogen might simplify the separation process, since the separation of water from helium is much easier. For fuelling of the reactor, however, pure tritium is required. At this time it is difficult to judge whether the processing of tritiated water to pure tritium predominates the initial cost savings. ... mehr

Volltext §
DOI: 10.5445/IR/220102714
Cover der Publikation
Zugehörige Institution(en) am KIT Institut für Angewandte Materialien – Keramische Werkstoffe und Technologien (IAM-KWT1)
Publikationstyp Poster
Publikationsjahr 2015
Sprache Englisch
Identifikator urn:nbn:de:swb:90-AAA2201027143
KITopen-ID: 220102714
HGF-Programm 31.03.06 (POF III, LK 01) Brutblanket-Entwicklung
Veranstaltung 12th International Symposium on Fusion Nuclear Technology (ISFNT 2015), Jeju, Korea, September 14-18, 2015
Schlagwörter Long-term annealing, breeder pebbles, purge gas, lithium orthosilicate, lithium metatitanate
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