Progresses in the development of the tritium extraction and removal system for the water-cooled lithium-lead breeding blanket in EUROfusion
The result's identifiers
Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F25%3AN0000088" target="_blank" >RIV/26722445:_____/25:N0000088 - isvavai.cz</a>
Result on the web
<a href="https://www.sciencedirect.com/science/article/pii/S0920379625003230" target="_blank" >https://www.sciencedirect.com/science/article/pii/S0920379625003230</a>
DOI - Digital Object Identifier
<a href="http://dx.doi.org/10.1016/j.fusengdes.2025.115126" target="_blank" >10.1016/j.fusengdes.2025.115126</a>
Alternative languages
Result language
angličtina
Original language name
Progresses in the development of the tritium extraction and removal system for the water-cooled lithium-lead breeding blanket in EUROfusion
Original language description
In the EU DEMO reactor, the Water-Cooled Lithium-Lead Tritium Extraction and Removal system (WCLL TER) is dedicated to transporting tritium-rich PbLi from the Breeding Blanket to the Tritium Extraction Unit and then back to it, after tritium is extracted and routed to the fuel cycle. In addition to circulating PbLi and extracting tritium, the TER system maintains constant PbLi temperature of 330 degrees C, provides safe storage of PbLi during reactor shutdowns as well as PbLi purification from by-products and contaminants linked both to structural materials corrosion processes and neutronic reactions of Pb, Li and other dissolved species. This contribution presents the latest developments in the design of the WCLL TER and in some of the related key areas of research. Among the most significant outcomes, the Permeator Against Vacuum was selected as a reference tritium extraction technology, preferred over the Gas-Liquid Contactor and the Liquid Vacuum Contactor, and its design was updated based on recent experimental evidence. All components of the TER such as tanks, pipelines, valves and other equipment were integrated into the tokamak building, ensuring compliance with fundamental operating principles.
Czech name
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Czech description
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Classification
Type
J<sub>imp</sub> - Article in a specialist periodical, which is included in the Web of Science database
CEP classification
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OECD FORD branch
20305 - Nuclear related engineering; (nuclear physics to be 1.3);
Result continuities
Project
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Continuities
R - Projekt Ramcoveho programu EK
Others
Publication year
2025
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů
Data specific for result type
Name of the periodical
Fusion Engineering and Design
ISSN
0920-3796
e-ISSN
1873-7196
Volume of the periodical
216
Issue of the periodical within the volume
July
Country of publishing house
CH - SWITZERLAND
Number of pages
9
Pages from-to
1-9
UT code for WoS article
001484997200002
EID of the result in the Scopus database
2-s2.0-105003962739