Tritium technologies and transport modelling: main outcomes from the European TBM Project-Reference-Cited by-同舟云学术

Tritium technologies and transport modelling: main outcomes from the European TBM Project

Published:2018-11 Issue: Volume:136 Page:128-134
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Ricapito I.,Aiello A.,Bükki-Deme A.,Galabert J.,Moreno C.,Poitevin Y.,Radloff D.,Rueda A.,Tincani A.,Utili M.

Publisher

Elsevier BV

Subject

Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Civil and Structural Engineering

Reference10 articles.

1. Investigation on efficiency of gas liquid contactor used as tritium extraction unit for HCLL-TBM Pb-16Li loop;Utili;Fusion Eng. Des.,2016

2. Tritium extraction from liquid Pb-16Li: a critical review of candidate technologies for ITER and DEMO applications;Ricapito;Fusion Sci. Technol.,2011

3. Design performance and manufacturing analysis for a compact permeators;Sacristán;Fusion Eng. Des.,2012

4. Design of a permeator against vacuum for tritium extraction from eutectic lithium-lead in a DCLL DEMO;Garcinuno;Fusion Eng. Des.,2017

5. Feasibility analysis of vacuum sieve tray for tritium extraction in the HCLL test blanket system;Okino;Fusion Eng. Des.,2016

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1. Numerical simulation of tritium extraction from liquid PbLi by gas–liquid contactor;Annals of Nuclear Energy;2024-03

2. Overview of tritium management in WCLL test blanket system of ITER;Fusion Engineering and Design;2024-03

3. Tritium Transport in WCLL Outboard Breeding Blanket of EU-DEMO Reactor Under Pulsed Plasma Operation;Fusion Science and Technology;2023-03-20

4. Modeling the Transport of Activated Corrosion Products in the WCLL PbLi Loop for ITER and the EU DEMO With the GETTHEM Code;IEEE Access;2023

5. Preliminary assessment of tritium permeation and retention in the European Water Cooled Lithium Lead Test Blanket Module with TESSIM-X;Nuclear Materials and Energy;2022-09