Results 11 to 20 of about 2,339 (265)

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

Materials for breeding blankets [PDF]

Journal of Nuclear Materials, 1996
There are several candidate concepts for tritium breeding blankets that make use of a number of special materials. These materials can be classified as Primary Blanket Materials, which have the greatest influence in determining the overall design and performance, and Secondary Blanket Materials, which have key functions in the operation of the blanket ...
Mattas, R. F., Billone, M. C.
openaire   +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

Testing needs for the development and qualification of a breeding blanket for DEMO

Nuclear Fusion, 2023
The purpose of this paper is to critically review the testing and qualification strategy for the DEMO breeding blanket in Europe, identifying the potential risks and weaknesses and recommending, where necessary, the changes required to strengthen or ...
Gianfranco Federici
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

Engineering Design of the European DEMO HCPB Breeding Blanket Breeder Zone Mockup

Applied Sciences, 2023
The Helium Cooled Pebble Bed (HCPB) breeding blanket is one of the two driver-blanket candidates for the European fusion demonstration power plant (EU DEMO) within the framework of the EUROfusion Consortium.
Guangming Zhou, Joerg Rey, Francisco A. Hernández, Ali Abou-Sena, Martin Lux, Frederik Arbeiter, Georg Schlindwein, Florian Schwab   +7 more
doaj   +1 more source

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

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

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