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A Fission-Fusion Hybrid Reactor in Steady-State L-Mode Tokamak Configuration with Natural Uranium [PDF]

Forget, B., Parker, R., Reed, M.
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Chemical Aspects in Molten-salt FLIBE System Design for FFH R [PDF]

A. Sagara, O. Motojima, S. Tanaka, T. Terai   +3 more
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Molten-salt FLIBE System Design for FFHR [PDF]

A. Sagara, A. Suzuki, O. Motojima, S. Tanaka, T. Terai   +4 more
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Overview of the Tritium Technologies for the EU DEMO Breeding Blanket

Fusion Science and Technology, 2020
The development of commercial fusion power production using deuterium and tritium has been ongoing worldwide for decades and the European version of DEMO will undergo conceptual design between 2021...
Ion Cristescu, F. Priester, D. Rapisarda, A. Santucci, M. Utili   +4 more
openaire   +4 more sources

Tritium permeation issues for helium-cooled breeding blankets

2013 IEEE 25th Symposium on Fusion Engineering (SOFE), 2013
Tritium permeation through Breeding Blanket and Steam Generator heat transfer areas is a crucial aspect for the design of the next generation DEMO fusion power plants. Tritium is generated inside the breeder, dissolves in and permeates through materials, thus leading to a potential hazard for the environment.
Franza F., Boccaccini L. V., Demange D., CIAMPICHETTI, ANDREA, ZUCCHETTI, MASSIMO   +4 more
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TRITIUM BREEDING CALCULATION IN A STELLARATOR BLANKET

Problems of Atomic Science and Technology, 2019
In current blanket projects, tritium breeding ratio (TBR), the ratio of tritium production rate to the neutron production rate, is low (1.1…1.2). The MCNPX Monte-Carlo code has been used to model the neutron kinetics and to look for a principal possibility of increase TBR within a stellarator blanket limited space.
Chernitskiy, S.V., Moiseenko, V.E.
openaire   +2 more sources

Multilayered Blanket Concept for Tritium Breeding Assemblies Blanket Engineering

Nuclear Technology - Fusion, 1983
The multilayered concept of the fusion blanket is introduced, and it is shown that with this concept the lithium inventory can be reduced by an order of magnitude compared to that in the block conc...
Vijay R. Nargundkar, Om Prakash Joneja
openaire   +1 more source

Solid breeder blanket design and tritium breeding

Fusion Engineering and Design, 1991
Abstract Thermonuclear D–T power plants will have to be tritium self-sufficient. In addition to recovering the energy carried by the fusion neutrons (about 80% of the fusion energy), the blanket of the reactor will thus have to breed tritium to replace that burnt in the fusion process.
Proust, E., Anzidei, L., Dalle Donne, M., Fischer, U., Kuroda, T.   +4 more
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Aqueous tritium breeding blanket with natural lithium

Fusion Engineering and Design, 1989
An aqueous tritium breeding blanket concept with natural lithium has been proposed. Lithium oxide dissolved in pressurized heavy water forms a saturated solution of LiOD in the liquid phase and the remainder is suspended in the solution or forms a breeder solid skeleton.
Masabumi Nishikawa, Toshihiko Kawano, Kenzo Munakata, Yukinori Kanda, Hideki Nakashima   +4 more
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Compatibility problems in tritium breeding blankets

Journal of Nuclear Materials, 1991
Abstract The compatibility between tritium breeding materials (liquid or solid), neutron multiplier and structural steels is a concern for the choice of a tritium breeding blanket for NET. For solid tritium breeding blanket, it seems that the more severe compatibility problem is due to the interaction of beryllium with steel.
M. Broc, T. Flament, A. Terlain, J. Sannier   +3 more
openaire   +1 more source