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Conceptual design and analysis of the HCCR breeder blanket for the K-DEMO

Fusion Engineering and Design, 2020
A helium-cooled ceramic reflector (HCCR) blanket was studied as a candidate breeder blanket for the Korean DEMO reactor. A detailed three-dimensional neutronics model based on a K-DEMO model and a simplified thermal-hydraulic model were established for ...
S. Yun   +10 more
semanticscholar   +3 more sources

Updated design of water-cooled breeder blanket for CFETR

Fusion Engineering and Design, 2019
The water-cooled ceramic breeder (WCCB) blanket is one candidate for the Chinese Fusion Engineering Testing Reactor (CFETR), and it is being developed at the Institute of Plasma Physics of the Chinese Academy of Sciences.
Songlin Liu   +8 more
semanticscholar   +3 more sources

Design of the Water-Cooled Ceramic Breeder blanket for CFETR

Fusion Engineering and Design, 2022
Songlin Liu   +13 more
semanticscholar   +3 more sources

Initial Neutronics Investigation of a Chlorine Salt–Based Breeder Blanket

Fusion science and technology, 2023
Tritium breeding blankets within D-T-fueled fusion reactors contain lithium compounds and typically require neutron multiplier materials to achieve a tritium breeding ratio (TBR) consistent with self-sustaining operation.
T. Bohm, Ben Lindley
semanticscholar   +1 more source

A Water cooled Lead Ceramic Breeder blanket for European DEMO

Fusion engineering and design, 2021
The development of a demonstration fusion power plant (DEMO) is widely considered a crucial step beyond ITER leading toward fusion electricity. In a viable DEMO plant two major functions have to be achieved, namely to breed tritium for fuel self ...
Guangming Zhou, Yudong Lu, F. Hernández
semanticscholar   +1 more source

Overview of progress on water cooled ceramic breeder blanket in Japan

Fusion Engineering and Design
Yoshinori Kawamura   +15 more
semanticscholar   +3 more sources

Experimental study on tritium breeding in water-cooled ceramic breeder blanket mock-up under D–T neutron irradiation conditions

Nuclear Fusion, 2021
The accurate assessment of tritium breeding parameters within fusion blankets is crucial for future magnet-confined fusion machines to realize fuel self-sufficiency.
Qingjun Zhu   +5 more
semanticscholar   +1 more source

Conceptual design of the water cooled ceramic breeder blanket for CFETR based on pressurized water cooled reactor technology

Fusion Engineering and Design, 2017
Songlin Liu   +7 more
semanticscholar   +3 more sources

Evaluation and optimization of tritium breeding, shielding and nuclear heating performances of the helium cooled solid breeder blanket for CFETR

International Journal of Hydrogen Energy, 2017
Shijie Cui   +6 more
semanticscholar   +3 more sources

Modelling WCLL breeder blankets

2021
The key purpose of DEMO is to provide electricity from fusion power. An integral part to this design will be the tritium breeding blanket. Accurate modelling of hydrogen transport and inventories within the breeder blanket component will be of predominant importance regarding safety issues and economic sustainability. The modelling of hydrogen isotopes
Dark, James   +5 more
openaire   +2 more sources

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