Results 21 to 30 of about 3,747 (225)

Molecular Dynamics Simulations of Lead and Lithium in Liquid Phase [PDF]

, 2011
Pb17Li is today a reference breeder material in diverse fusion R&D programs worldwide. Extracting dynamic and structural properties of liquid LiPb mixtures via molecular dynamics simulations, represent a crucial step for multiscale modeling efforts ...
Cuesta Lopez, Santiago, Fraile García, Alberto, Perlado Martín, José Manuel   +2 more
core   +3 more sources

The impact of design parameters on tritium breeding in a water cooled blanket for CFETR [PDF]

AIP Advances
The CFETR (China Fusion Engineering Test Reactor) is a major Chinese scientific project to design, build, and operate a next-generation tokamak nuclear fusion reactor.
Jie Li, Haiyan Yang, Jie Zhang
doaj   +1 more source

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
Tritium self-sufficiency is a key requirement for future fusion power plants. Therefore, it will be necessary to minimize tritium losses to the surrounding systems, such as the tritium breeding modules, plasma-facing components, cooling system, etc ...
R. Arredondo, K. Schmid, I. Ricapito, A. Lukenskas, G.A. Spagnuolo   +4 more
doaj   +1 more source

Modeling and analysis of the tritium fuel cycle for ARC- and STEP-class D-T fusion power plants

Nuclear Fusion, 2023
The limited tritium resources available for the first fusion power plants (FPPs) make fuel self-sufficiency and tritium inventory minimization leading issues in FPP design. This work builds on the model proposed by Abdou et al (2020 Nucl.
Samuele Meschini, Sara E. Ferry, Rémi Delaporte-Mathurin, Dennis G. Whyte   +3 more
doaj   +1 more source

Conceptual design of the EU-DEMO dual coolant lithium lead equatorial module [PDF]

, 2016
© 20xx IEEE. Personal use of this material is permitted. Permission from IEEE must be obtained for all other uses, in any current or future media, including reprinting/republishing this material for advertising or promotional purposes, creating new ...
Fernández, I., González, M., Mas de les Valls Ortiz, Elisabet, Moreno Sierra, César, Moreno, C., Palermo, I., Rapisarda, David   +6 more
core   +3 more sources

Advancements in Designing the DEMO Driver Blanket System at the EU DEMO Pre-Conceptual Design Phase: Overview, Challenges and Opportunities

Journal of Nuclear Engineering, 2023
The EU conducted the pre-conceptual design (PCD) phase of the demonstration reactor (DEMO) during 2014–2020 under the framework of the EUROfusion consortium.
Francisco A. Hernández, Pietro Arena, Lorenzo V. Boccaccini, Ion Cristescu, Alessandro Del Nevo, Pierre Sardain, Gandolfo A. Spagnuolo, Marco Utili, Alessandro Venturini, Guangming Zhou   +9 more
doaj   +1 more source

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
This work presents the results of the implementation in the GEneral Tokamak THErmal-hydraulic Model of available models for the generation and transport of any dispersed material in flowing PbLi eutectic mixture.
Fabrizio Lisanti, Pietro Arena, Roberto Bonifetto, Antonio Froio, Francisco Alberto Hernandez Gonzalez, Gandolfo Alessandro Spagnuolo, Roberto Zanino   +6 more
doaj   +1 more source

Parametric thermal analysis for the optimization of Double Walled Tubes layout in the Water Cooled Lithium Lead inboard blanket of DEMO fusion reactor [PDF]

, 2019
Within the roadmap that will lead to the nuclear fusion exploitation for electric energy generation, the construction of a DEMOnstration (DEMO) reactor is, probably, the most important milestone to be reached since it will demonstrate the technological ...
Arena P., Del Nevo A., Di Maio P. A., Forte R., Nevone G.   +4 more
core   +1 more source

Preliminary estimates of tritium permeation and retention in the first wall of DEMO due to ion bombardment

Nuclear Materials and Energy, 2021
Tritium self-sufficiency presents a critical engineering challenge for DEMO, requiring efficient breeding and extraction systems, as well as minimizing tritium losses to the surrounding systems, such as plasma-facing components, vacuum vessel, cooling ...
R. Arredondo, K. Schmid, F. Subba, G.A. Spagnuolo   +3 more
doaj   +1 more source

An intelligent optimization method for the HCSB blanket based on an improved multi-objective NSGA-III algorithm and an adaptive BP neural network

Nuclear Engineering and Technology, 2023
To improve the performance of blanket: maximizing the tritium breeding rate (TBR) for tritium self-sufficiency, and minimizing the Dose of backplate for radiation protection, most previous studies are based on manual corrections to adjust the blanket ...
Wen Zhou, Guomin Sun, Shuichiro Miwa, Zihui Yang, Zhuang Li, Di Zhang, Jianye Wang   +6 more
doaj   +1 more source