Progresses in the development of the tritium extraction and removal system for the water-cooled lithium-lead breeding blanket in EUROfusion 

Kód výsledku v 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>

Výsledek na webu

<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>

Jazyk výsledku

angličtina

Název v původním jazyce

Progresses in the development of the tritium extraction and removal system for the water-cooled lithium-lead breeding blanket in EUROfusion 

Popis výsledku v původním jazyce

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.

Název v anglickém jazyce

Progresses in the development of the tritium extraction and removal system for the water-cooled lithium-lead breeding blanket in EUROfusion 

Popis výsledku anglicky

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.

Druh

J_imp - Článek v periodiku v databázi Web of Science

CEP obor

—

OECD FORD obor

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

Projekt

—

Návaznosti

R - Projekt Ramcoveho programu EK

Rok uplatnění

2025

Kód důvěrnosti údajů

S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

Název periodika

Fusion Engineering and Design

ISSN

0920-3796

e-ISSN

1873-7196

Svazek periodika

216

Číslo periodika v rámci svazku

July

Stát vydavatele periodika

CH - Švýcarská konfederace

Počet stran výsledku

9

Strana od-do

1-9

Kód UT WoS článku

001484997200002

EID výsledku v databázi Scopus

2-s2.0-105003962739