Results 281 to 290 of about 1,102,878 (329)
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Fusion Engineering and Design, 2018
The Helium-Cooled Lithium-Lead (HCLL) and Water-Cooled Lithium-Lead (WCLL) Breeding Blankets are two of the four European blanket designs proposed for the DEMO reactor. A tritium transport model inside the blanket is fundamental to assess its preliminary
Luigi Candido +2 more
exaly +2 more sources
The Helium-Cooled Lithium-Lead (HCLL) and Water-Cooled Lithium-Lead (WCLL) Breeding Blankets are two of the four European blanket designs proposed for the DEMO reactor. A tritium transport model inside the blanket is fundamental to assess its preliminary
Luigi Candido +2 more
exaly +2 more sources
Fusion Engineering and Design, 2020
The strategy for the development of the European DEMO Breeding Blanket (BB) and the TBM (Test Blanket Module) Programme have been recently realigned with the objective to mitigate the risks associated with the development of tritium breeding and power ...
F Cismondi, M Zmitko, I Ricapito
exaly +2 more sources
The strategy for the development of the European DEMO Breeding Blanket (BB) and the TBM (Test Blanket Module) Programme have been recently realigned with the objective to mitigate the risks associated with the development of tritium breeding and power ...
F Cismondi, M Zmitko, I Ricapito
exaly +2 more sources
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
openaire +2 more sources
Tritium permeation issues for helium-cooled breeding blankets
2013 IEEE 25th Symposium on Fusion Engineering (SOFE), 2013Tritium 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 +3 more sources
High Performance Breeding Blankets for ICF Facilities
Nuclear Technology/Fusion, 1983Discussed are the advantages of using fusion neutrons for breeding special nuclear materials and tritium. Monte Carlo calculations were used to identify both fissionable and nonfissionable materials that multiply neutrons and increase breeding ratios. Fissionable multipliers also greatly multiply the neutron energy.
A. R. Larson, I. O. Bohachevsky
exaly +2 more sources
International Journal of Heat and Mass Transfer, 2021
In PbLi based breeding blanket concepts, tritium is produced inside the liquid metal and drag out of the reactor by the liquid metal flow. However, undesired permeation through the channels and pipes walls occurs spontaneously since tritium naturally ...
F. R. Urgorri +3 more
semanticscholar +1 more source
In PbLi based breeding blanket concepts, tritium is produced inside the liquid metal and drag out of the reactor by the liquid metal flow. However, undesired permeation through the channels and pipes walls occurs spontaneously since tritium naturally ...
F. R. Urgorri +3 more
semanticscholar +1 more source
Breeding blanket development for NET
Fusion Engineering and Design, 1989Abstract The design of blankets for NET is reviewed. Three categories of blankets are discussed: non breeding shield blankets for the physics phase, tritium producing driver blankets to operate the NET machine for extended periods of time in the technology test phase, and DEMO relevant blankets, which shall demonstrate their performance as test ...
J.E. VETTER, P. Komarek
openaire +2 more sources
Tritium breeding control within liquid metal blankets
Fusion Engineering and Design, 2013L. Morgan, J. Pasley
exaly +2 more sources
Fusion Engineering and Design, 1993
This paper presents the main design features, their rationale, and the main critical issues for the development, of the four DEMO-relevant blanket concepts presently being investigated within the framework of the European Test-Blanket Development Programme.
Proust, E. +5 more
openaire +1 more source
This paper presents the main design features, their rationale, and the main critical issues for the development, of the four DEMO-relevant blanket concepts presently being investigated within the framework of the European Test-Blanket Development Programme.
Proust, E. +5 more
openaire +1 more source
, 2020
Understanding and predicting tritium transport is considered a key issue for the design of safe and self-sufficient fusion power plants. Indeed, tritium generated in the breeder materials is susceptible to permeate to the blanket coolant circuits where ...
Fernando Roca Urgorri +2 more
semanticscholar +1 more source
Understanding and predicting tritium transport is considered a key issue for the design of safe and self-sufficient fusion power plants. Indeed, tritium generated in the breeder materials is susceptible to permeate to the blanket coolant circuits where ...
Fernando Roca Urgorri +2 more
semanticscholar +1 more source