Results 21 to 30 of about 38,108 (302)

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

A neutron diode for subcritical multistage multipliers with special reference in tritium breeding [PDF]

, 2016
This is a copy of the author 's final draft version of an article published in the Journal of fusion energy. The final publication is available at Springer via http://dx.doi.org/10.1007/s10894-015-0049-7In this paper the interaction between a magnetic ...
Arias Montenegro, Francisco Javier, Parks, Geoffrey T   +1 more
core   +2 more sources

Conceptual design of solid-type Pb x Li y eutectic alloy breeding blanket for CFETR

Nuclear Fusion, 2023
As a key component of the Chinese Fusion Engineering and Test Reactor (CFETR), the blanket is responsible for tritium breeding, neutron shielding and energy conversion.
K. Jiang, Q. Wu, L. Chen, S. Liu
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

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

On the thermal dynamic behaviour of the helium-cooled DEMO fusion reactor [PDF]

, 2019
The EU-DEMO conceptual design is being conducted among research institutions and universities from 26 countries of European Union, Switzerland and Ukraine. Its mission is to realise electricity from nuclear fusion reaction by 2050.
Barucca L., Ciattaglia S., Di Maio P. A., Moscato I.   +3 more
core   +1 more source

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

The Thorium Molten Salt Reactor : Moving on from the MSBR [PDF]

, 2005
A re-evaluation of the Molten Salt Breeder Reactor concept has revealed problems related to its safety and to the complexity of the reprocessing considered.
A. Nuttin, C. Garzenne, C. Le Brun, D. Heuer, D. Lecarpentier, E. Liatard, E. Merle-Lucotte, E. Walle, J. Wilson, J.-M. Loiseaux, L. Mathieu, Nuttin, O. Méplan, R. Brissot, Rosenthal   +14 more
core   +3 more sources

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