Results 151 to 160 of about 513 (179)

Power plant conceptual study—WCLL concept

Fusion Engineering and Design, 2003
Abstract A power plant conceptual study (PPCS) has been launched in the framework of the EU fusion program the objective of which is to demonstrate the credibility of fusion power plant design and the claims for safety and environmental advantages and for economic viability of fusion power.
Sardain, P., Michel, B., Giancarli, L., Li Puma, A., Poitevin, Y., Szczepanski, J., Maisonnier, D., Ward, D., Fischer, U., Pereslavtsev, P., Natalizio, A., Collen, J., Orden Martinez, A.   +12 more
openaire   +4 more sources

Modelling WCLL breeder blankets

2021
The key purpose of DEMO is to provide electricity from fusion power. An integral part to this design will be the tritium breeding blanket. Accurate modelling of hydrogen transport and inventories within the breeder blanket component will be of predominant importance regarding safety issues and economic sustainability. The modelling of hydrogen isotopes
Dark, James, Delaporte-Mathurin, Rémi, Charles, Y., Hodille, Etienne, Grisolia, Christian, Mougenot, Jonathan   +5 more
openaire   +2 more sources

Influence of hydrogen trapping on WCLL breeding blanket performances

Nuclear Fusion, 2021
Tritium transport simulations in Water-Cooled Lithium Lead (WCLL) breeding blankets have been performed with FESTIM. Fluid dynamics and heat transfer were coupled to evaluate how temperature and LiPb velocity fields affect Tritium transport. The 2D WCLL model consisted of tungsten, EUROFER and liquid LiPb. Tritium inventories and permeation fluxes have
Dark, James, Delaporte-Mathurin, Rémi, Charles, Yann, Hodille, Etienne, Grisolia, Christian, Mougenot, Jonathan   +5 more
openaire   +3 more sources

Tritium permeation modelling in DEMO WCLL cooling system

Fusion Engineering and Design, 2020
Abstract Tritium management is one of the most critical aspects in DEMO design. Knowledge of tritium permeation is a priority both in terms of safety and plant performance, as it may represent a radiological risk for the employed personnel and a significance loss of plasma fuel.
Noschese, Leonardo, Santucci, Alessia, Tosti, Silvano, Romanelli, Francesco   +3 more
openaire   +2 more sources

DEMO WCLL primary heat transfer system loops activated corrosion products assessment

Fusion Engineering and Design, 2021
Abstract The estimation of Activated Corrosion Products (ACPs) in fusion technology is an important input to safety assessments (e.g. occupational radiation exposure, accidental analyses). The present work aims to calculate ACPs for the First Wall (FW) and Breeder Zone (BZ) water cooling loops of the DEMO Water Cooled Lithium Lead (WCLL) fusion ...
Terranova, Nicholas, Di Pace, Luigi
openaire   +1 more source

Tritium transport in HCLL and WCLL DEMO blankets

Fusion Engineering and Design, 2016
Abstract The Helium-Cooled Lithium Lead (HCLL) and Water-Cooled Lithium Lead (WCLL) Breeding Blankets are two of the four blanket designs proposed for DEMO reactor. The study of tritium transport inside the blankets is fundamental to assess their preliminary design and safety features. A mathematical model has been derived, in a new form making makes
CANDIDO, LUIGI, Utili, Marco, NICOLOTTI, IURI, ZUCCHETTI, MASSIMO   +3 more
openaire   +1 more source