Results 81 to 90 of about 628,084 (215)

Analysis of a segmentation approach to breeder blanket design and the utilisation of FLiBe as a novel neutron reflector

Nuclear Fusion
Tritium production in a fusion reactor is essential for a deuterium-tritium burning plasma source, and designing a lithium-containing breeder blanket is crucial for a closed fuel cycle in an electricity-to-grid power plant.
Adam J. Barker, Mark R. Gilbert, Philip D. Edmondson   +2 more
doaj   +1 more source

Garnet-type lithium sensors for the monitoring and control of Pb-Li alloys in tritium breeding modules

Nuclear Materials and Energy
During the EU-DEMO conceptualization, eutectic Pb-Li was considered as the prime candidate liquid breeding material. Nonetheless, the conversion of lithium into tritium through the breeding reaction will result in a decrease in the lithium concentration ...
Marc Nel-lo, Enric Lujan, Antonio Hinojo, Sergi Colominas, Jordi Abella   +4 more
doaj   +1 more source

ITER Water Cooled Lithium Lead Test Blanket System transient thermal-hydraulic analysis

Nuclear Fusion
The planned experimental activities of the ITER Test Blanket Module (TBM) program will be a key step in understanding the physics and technologies required for tritium breeding blankets, which are essential for achieving tritium self-sufficiency in a ...
Tommaso Glingler, Gianfranco Caruso, Danilo Nicola Dongiovanni, Salvatore D’Amico, Italo Ricapito, Paul Wouters, Francesca Fantini, Joelle Elbez-Uzan, Sandrine Rosanvallon, Matteo D’Onorio   +9 more
doaj   +1 more source

Assessment of Startup Inventory and Required Tritium Breeding Ratio for Fusion Reactor Based on Integrated Analytical Scheme

He huaxue yu fangshe huaxue
The development of Tokamak fusion reactors encompasses hybrid and pure fusion reactor designs. In the study of tritium self-sustainability, the average retention time method is predominantly employed for Tokamak fusion reactors, with less emphasis on ...
WANG Jun, ZHANG Long, LI Ru-yan
doaj   +1 more source

Water-cooled lead and ceramic breeder (WLCB) breeding blanket (BB) for the EU DEMO: Neutronic campaigns for T breeding optimization

Nuclear Materials and Energy
A novel Breeding Blanket (BB) concept, the Water-cooled Lead and Ceramic Breeder (WLCB) BB, has been developed under the EUROfusion Programme to address key challenges identified during the Pre-Conceptwual Design (PCD) phase for the driver BB concepts ...
Iole Palermo, Francisco A. Hernandez, Salvatore D’Amico, Jin Hun Park, Pavel Pereslavtsev, Guangming Zhou, Iñaki Zumalde   +6 more
doaj   +1 more source

Tritium production and processing systems for ST-E1

Nuclear Fusion
An integrated tritium fuel-cycle architecture has been developed for ST-E1, a low-aspect-ratio, high-power fusion power plant. The approach couples a helium-cooled liquid-lithium breeder blanket with a dedicated circulation loop providing tritium ...
E. Yildirim, J. Naish, J. Trueba, S. Levine, A. Kumar, V.B. Gohani, M.K.E. Mohamed, A. Vorobev, L. Yang, P.C. Simon, A. Somers, C. Malone, H. Flynn, P. Rowell, T. Stahl, G.K. Larson, R. Barnett, L.R. Baylor, T.E. Gebhart, N. Adhikari   +19 more
doaj   +1 more source

Densification behavior of ceramic tritium breeder pebble beds under vertical vibration: Effect of vibration parameters

Nuclear Materials and Energy
Packing density of the tritium breeder pebble beds are closely related to the effective density of the lithium atom in the breeding cavities. And the higher the density of lithium atoms the higher the tritium breeding ratio.
Baoping Gong, Hao Cheng, Juemin Yan, Long Wang, Qixiang Cao, Long Zhang, Jiming Chen, Yongjin Feng   +7 more
doaj   +1 more source

Neutronics analysis of spin-polarized fuel in spherical tokamaks

Nuclear Fusion
The effect of spin-polarized deuterium–tritium fuel on the blanket, magnets, and surrounding structures is analyzed for a spherical tokamak fusion power plant.
Jin Whan Bae, Katarzyna Borowiec, Vittorio Badalassi, Jason Parisi, Ahmed Diallo, Jon Menard, Andrei Khodak, Thomas Brown   +7 more
doaj   +1 more source

Optimized Water Distillation Layout for Detritiation Purpose

Applied Sciences
Tritium permeation constitutes a key issue for the future EU-DEMO, especially in the Breeding Blanket (BB) where fusion energy must be delivered to the Primary Heat Transport System (PHTS) and where tritium must be bred.
Vincenzo Narcisi, Alessia Santucci
doaj   +1 more source

ParaStell: parametric modeling and neutronics support for stellarator fusion power plants

Frontiers in Nuclear Engineering
The three-dimensional variation inherent to stellarator geometries and fusion sources motivates three-dimensional modeling to obtain accurate results from computational modeling in support of design and analysis of first wall, blanket, and shield (FWBS ...
Connor Moreno, Aaron Bader, Aaron Bader, Paul Wilson   +3 more
doaj   +1 more source