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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. +4 more
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Blanket Simulation and Tritium Breeding Ratio Calculation for ITER Reactor
Journal of Fusion Energy, 2015In this study, the neutronic calculation to obtain tritium breeding ratio (TBR) in a deuterium–tritium fusion power reactor using Monte Carlo MCNPX is done. To this end Li4SiO4 was considered as the blanket module. In order to improve the distribution of power density in the blanket module, an arrangement of the neutron multiplier Be in the breeding ...
Morteza Habibi
exaly +2 more sources
Magneto-convective effect on tritium transport at breeder unit level for the WCLL breeding blanket of DEMO [PDF]
Fusion Engineering and Design, 2020 The Water-Cooled Lithium-Lead (WCLL) is one of the four breeding blanket concepts proposed by Europe in view of its DEMO reactor. The velocity field of the electrically conducting lead-lithium eutectic alloy inside the blanket is strongly influenced by ...
Luigi Candido +2 more
exaly +3 more sources
Tritium breeding capability of water cooled ceramic breeder blanket with different container designs
Fusion Engineering and Design, 2019 Water cooled ceramic breeder (WCCB) blankets have been regarded as a primary concept in Japan. We in-vestigated the tritium breeding capability of a WCCB blanket with a cylindrical structure, an advantageous shapefor withstanding high coolant pressure ...
Takanori Hirose +2 more
exaly +2 more sources
Integration issues on tritium management of the European DEMO Breeding Blanket and ancillary systems
Fusion Engineering and Design, 2021 Within the EUROfusion framework, two reactor architectures are being developed as possible candidates for the EU DEMO. One is based on the Water Cooled Lithium Lead (WCLL) Breeding Blanket (BB) concept and the other on the Helium Cooled Pebble Bed (HCPB)
Gandolfo Alessandro Spagnuolo +2 more
exaly +2 more sources
TRITIUM BREEDING CALCULATION IN A STELLARATOR BLANKET
Problems of Atomic Science and Technology, 2019In 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.
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Compatibility problems in tritium breeding blankets
Journal of Nuclear Materials, 1991Abstract 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 +3 more
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Multilayered Blanket Concept for Tritium Breeding Assemblies Blanket Engineering
Nuclear Technology - Fusion, 1983The 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
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Tritium inventory and permeation in the ITER breeding blanket
Fusion Engineering and Design, 2000Abstract A model has allowed us to perform the analysis of the tritium inventory and permeation in the international thermonuclear experimental reactor (ITER) breeding blanket under the hypothesis of steady state conditions. Li 2 ZrO 3 (reference) and Li 2 TiO 3 (alternative) have been studied as breeding materials.
V. Violante +5 more
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Solid breeder blanket design and tritium breeding
Fusion Engineering and Design, 1991Abstract 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. +4 more
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