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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

  • Czech description

Classification

  • Type

    J<sub>imp</sub> - Article in a specialist periodical, which is included in the Web of Science database

  • CEP classification

  • OECD FORD branch

    20305 - Nuclear related engineering; (nuclear physics to be 1.3);

Result continuities

  • Project

  • 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