Results 21 to 30 of about 2,502 (210)
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 +3 more
doaj +1 more source
HCCR breeding blankets optimization by changing neutronic constrictions
Nuclear Engineering and Technology, 2021 The neutronic analysis of Helium Cooled Ceramic Reflector (HCCR) breeding blankets has been performed using the 3D Monte Carlo code MCNPX and ENDF nuclear data library.
R. Zadfathollah Seighalani +2 more
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Impact of blanket material and configuration on the size of a tokamak fusion reactor
Nuclear Materials and Energy, 2021 On the basis of the Korean fusion roadmap, conceptual design of the DEMO and R&D on the breeding blanket are ongoing. This article addresses the impact of blanket material and configuration on the tritium breeding, shielding characteristics, and ...
Bong Guen Hong
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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 +3 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 +6 more
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Energies, 2022 The optimal shape of a fusion-based transmutation reactor with a molten salt coolant was determined by plasma physics, technology, and neutronic requirements.
Bong-Guen Hong
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Analysis of Coolant Purification Strategies for Tritium Control in DEMO Water Primary Coolant
Energies, 2023 A major objective of the European fusion program is the design of the DEMOnstration power plant named DEMO. Up to now, most fusion experiments have been dedicated to a plasma physics investigation while, in DEMO-oriented activities, large attention is ...
Vincenzo Narcisi +3 more
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Energies, 2023 Significant design efforts were undertaken during the Pre-Concept Design (PCD) phase of the European DEMO program to optimize the helium cooled pebble bed (HCPB) breeding blanket.
Guangming Zhou +6 more
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Neutronic analysis of effects of inboard materials on the size of a tokamak fusion reactor
Nuclear Materials and Energy, 2021 The effects of inboard materials on the size of a tokamak fusion reactor were studied based on reactor system parameters determined through a coupled analysis of tokamak systems and neutron transport. With an inboard blanket, the shielding capability was
B.G. Hong, W. Cho
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Tritium Breeding in a Fusion--Fission Hybrid Breeder Reactor [PDF]
, 1978 In order to construct a D-T fusion-fission hybrid breeder reactor there must be some guarantee that tritium will be available to fuel the fusion reaction. This can be achieved by breeding tritium in the blanket of the reactor.
McCowan, John R.
core +1 more source