Results 11 to 20 of about 38,324 (298)

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.
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Study on the effect of neutron shielding design on tritium breeding based on water-cooled ceramic blanket for CFETR

AIP Advances, 2023
The Chinese Fusion Engineering Test Reactor (CFETR) is a magnetic confinement fusion reactor independently designed and developed by China, which is based on the ITER design experience.
Jie Li, Hang Li, Muquan Wu, Xiang Zhu, Peiguang Yan, Xiaodong Lin, Jie Zhang, Xiang Gao   +7 more
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Multiphysics Optimization for First Wall Design Enhancement in Water-Cooled Breeding Blankets

Nuclear Materials and Energy, 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 fuelling. Within such a kind of reactor, the component selected to house the tritium breeding
Ruggero Forte, Pierluigi Chiovaro, Pietro Alessandro Di Maio, Nasr Ghoniem   +3 more
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Tritium Breeding Blanket [PDF]

Fusion Technology, 1991
The terms of reference for ITER provide for incorporation of a tritium breeding blanket with a breeding ratio as close to unity as practical. A breeding blanket is required to assure an adequate supply of tritium to meet the program objectives. Based on specified design criteria, a ceramic breeder concept with water coolant and an austenitic steel ...
D. Smith, M. Billone, Y. Gohar, A. Raffray, W. Daenner, D. Lorenzetto, C. Baker, I. Sviatoslavsky, A. Anitipenkov, A. Siderov, S. Mori, T. Kuroda, K. Maki, H. Takatsu, H. Yoshida, G. Simbolotti, G. Shatalov   +16 more
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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
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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
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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
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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
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ITER breeding blanket design [PDF]

Proceedings of 16th International Symposium on Fusion Engineering, 2002
A breeding blanket design has been developed for ITER to provide the necessary tritium fuel to achieve the technical objectives of the Enhanced Performance Phase. It uses a ceramic breeder and water coolant for compatibility with the ITER machine design of the Basic Performance Phase.
Y. Gohar, M. Billone, A. Cardella, W. Danner, K. Ioki, T. Kuroda, D. Lousteau, P. Lorenzetto, S. Majumdar, R. Mattas, K. Mohri, R. Raffray, Y. Strebkov, H. Takatsu, E. Zolti   +14 more
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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
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