Nuclear fusion: Difference between revisions

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== A Nuclear Fusion reactor ==
== A Nuclear Fusion reactor ==


The nuclear reaction that is easiest to obtain is the deuterium-tritium (DT) reaction.  
The fusion reaction that is easiest to obtain is the deuterium-tritium (DT) reaction.  
A [[:Wikipedia:Fusion power|fusion power reactor]] delivering 1GW of electric power to the network would approximately consume 200 kg of Tritium a year. The current world reserves are about 29 kg of tritium. Thus, a nuclear fusion reactor must provide its own fuel. This is achieved using so-called [[Breeding blanket|breeders]]. Tritium breeders capture the neutrons originating from nuclear fusion reactions, generating tritium that can be used as fuel for the reactor. For more information: [[TECNO_FUS]].
A [[:Wikipedia:Fusion power|fusion power reactor]] delivering 1GW of electric power to the network would approximately consume 200 kg of Tritium a year. The current world reserves are about 29 kg of tritium. Thus, a nuclear fusion reactor must provide its own fuel. This is achieved using so-called [[Breeding blanket|breeders]]. Tritium breeders capture the neutrons originating from nuclear fusion reactions, generating tritium that can be used as fuel for the reactor. For more information: [[TECNO_FUS]].


== The need for new materials for Fusion ==
== The need for new materials for Fusion ==


A nuclear power reactor delivering 1GW of electric power to the network would generate 1.3 10<sup>21</sup> neutrons per second. This flux will make any conventional iron to become brittle in less than a year. For this reason, a program for testing materials under intense neutron fluxes has been launched. The aim of the [[IFMIF]] program is to develop a fast neutron generation facility.
A fusion power reactor delivering 1GW of electric power to the network would generate 1.3 &times; 10<sup>21</sup> neutrons per second. This flux will make any conventional iron to become brittle in less than a year. For this reason, a program for testing materials under intense neutron fluxes has been launched. The aim of the [[IFMIF]] program is to develop a fast neutron generation facility.


Also in Spain, a program for material testing has been launched recently:  
Also in Spain, a program for material testing has been launched recently: