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Neutronic Comparison of Tritium-Breeding Performance of Candidate Tritium-Breeding Materials

Plasma Science and Technology, 2003
Tritium self-sustainment, which will meet the fuel requirement of fusion reactor, is one of the key issues of fusion power development. The tritium breeding performances of various tritium-breeding materials are compared based on a series of neutronics calculations using three-dimensional Monte Carlo neutron-photon transport code MCNP/4C with the IAEA ...
Zheng Shanliang, Wu Yican
openaire   +1 more source

Deuterium-tritium fusion reactors without external tritium breeding

Physics Letters A, 1998
Abstract An inherent property of deuterium fusion burn-up equations is presented, due to which deuterium-tritium reactions can be exploited without needing tritium breeding in external blankets. A small amount of tritium is added to the deuterium plasma in order to trigger ignition at less than 10 keV, and the same amount of tritium is found in the ...
S Eliezer   +3 more
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Tritium Breeding in Hybrid Reactors

Fusion Technology, 1986
The difficulty of achieving tritium self-sufficiency in a deuterium-tritium (D-T) hybrid has been reported in relation to different hybrid designs and concepts using lithium as the breeding material. Lithium-6 enrichment has been suggested to overcome this problem, provided the contribution of /sup 7/Li to tritium production is usually negligible, as ...
Mireia Piera, José M. Martinez-Val
openaire   +1 more source

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

Tritium fuel cycle modeling and tritium breeding analysis for CFETR

Fusion Engineering and Design, 2016
Abstract Attaining tritium self-sufficiency is a critical goal for fusion reactor operated on the D–T fuel cycle. The tritium fuel cycle models were developed to describe the characteristic parameters of the various elements of the tritium cycle as a tool for evaluating the tritium breeding requirements.
Hongli Chen   +4 more
openaire   +1 more source

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
openaire   +4 more sources

Properties and performance of tritium breeding ceramics

Journal of Nuclear Materials, 1992
Lithium-containing ceramics are being strongly considered as tritium breeding materials for fusion reactor blankets owing to their good thermal stability, favorable chemical behavior and tritium breeding potential, and excellent tritium release characteristics. The research effort has focused on four compounds: Li 2 O, γ-LiAIO 2 , Li 4 SiO 4 , and Li 2
N. Roux, C. Johnson, K. Noda
openaire   +2 more sources

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   +3 more
openaire   +1 more source

Behaviour of tritium in breeding materials

Fusion Engineering and Design, 2005
Abstract The tritium release from ceramic materials of the HCPB under real DEMO operating conditions will depend not only on temperature and neutron flux but also on an intense magnetic field (MF) of 7–9 T. The delay in the tritium release induced by the MF is proportional to the grain size of the ceramics, the squared MF intensity and the abundance ...
G. Kizāne   +4 more
openaire   +1 more source

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