Results 31 to 40 of about 4,264 (289)

Overview of the ITER TBM program

He jishu, 2022
The tritium breeding blanket (TBB) technology is one of the key technologies to be solved and also one of three major issues in the development of fusion reactor in the future. The international thermonuclear experimental reactor (ITER) will be the first
SHENG Qian, WU Shuqin, WANG Xiaoyu, ZHAO Fengchao, LUO Xiaofang, QIAN Xiaoyong, LUO Delong   +6 more
doaj   +1 more source

Exploratory tritium breeding performance study on a water cooled lead ceramic breeder blanket for EU DEMO using Serpent-2

Nuclear Materials and Energy, 2021
Innovative Water cooled Lead Ceramic Breeder (WLCB) blanket concepts are being developed at Karlsruhe Institute of Technology (KIT) to explore alternative options for the European demonstration fusion power plant (DEMO).
Yudong Lu, Minyou Ye, Guangming Zhou, Francisco A. Hernández, Jaakko Leppänen, Yuan Hu   +5 more
doaj   +1 more source

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

Physical Background, Computations and Practical Issues of the Magnetohydrodynamic Pressure Drop in a Fusion Liquid Metal Blanket

Fluids, 2021
In blankets of a fusion power reactor, liquid metal (LM) breeders, such as pure lithium or lead-lithium alloy, circulate in complex shape blanket conduits for power conversion and tritium breeding in the presence of a strong plasma-confining magnetic ...
Sergey Smolentsev
doaj   +1 more source

Thermo-hydraulic analysis of EU DEMO WCLL breeding blanket [PDF]

, 2018
In the frame of EUROfusion Work Package Breeding Blanket, thermal-hydraulic engineering analyses were carried out at ENEA Brasimone, in close cooperation with Sapienza University of Rome, to investigate thermal and fluid-dynamic behavior of the Water ...
Gianfranco Caruso, Alessandro Del Nevo, Giannetti, Fabio, Fabio Giannetti, Del Nevo, Alessandro, Emanuela Martelli, Caruso, Gianfranco, Martelli, Emanuela   +7 more
core   +2 more sources

Design and simulation of a blanket module with high efficiency cooling system of tokamak focused on DEMO reactor

Nuclear Engineering and Technology, 2020
In this study, the neutronic calculation to obtain tritium breeding ratio (TBR) in a deuterium-tritium (D-T) fusion power reactor using Monte Carlo MCNPX is done. In addition, by using COMSOL software, an efficient cooling system is designed.
H. Sadeghi, R. Amrollahi, M. Zare, S. Fazelpour   +3 more
doaj   +1 more source

Multiphysics Optimization for Water-Cooled Breeding Blanket Design Enhancement [PDF]

, 2021
The commercial feasibility of the first fusion power plant generation adopting D-T plasma is strongly dependent upon the self-sustainability in terms of tritium fueling.
FORTE, Ruggero
core  

Model Development and Transient Analysis of the HCPB BB BOP DEMO Configuration Using the Apros System Code

Energies, 2021
Extensive modeling and analytical work has been carried out considering the Helium-Cooled Pebble Bed Breeding Blanket (HCPB BB) Balance Of Plant (BOP) configuration of the Demonstration Power Plant (DEMO) using the Apros system code, developed by VTT ...
Marton Szogradi, Sixten Norrman
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

Activation analysis and waste management for dual functional lithium-lead blanket of the China Fusion Engineering Test Reactor

Fushe yanjiu yu fushe gongyi xuebao, 2021
Based on the design requirements of the first stage of the China Fusion Engineering Test Reactor (CFETR), the activation performance calculation and analysis of the components in the dual function lead-lithium blanket were performed using a neutron ...
ZENG Zhengkui, CHEN Size, YU Huiying, XIONG Houhua, DU Jifu, WANG Zhiwei   +5 more
doaj   +1 more source