Nuclear fusion: Difference between revisions

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


The nuclear reaction that is easier to obtain is based on the deuterium-tritium (DT) reaction.  
The nuclear reaction that is easiest to obtain is the deuterium-tritium (DT) reaction.  
A nuclear power reactor delivering 1GW of electric power to the network would aproximately consume 200 kg of Tritium a year. The current world reserves are of about 29 kg of tritium. Then, a nuclear fusion reactor must provide its own fuel. This is obtained using the so called breeders. Tritium breeders capture the neutrons comming from the nuclear fusion reactions and generate tritium that can be used as fuel for the reactor. For more information:  
A nuclear power reactor delivering 1GW of electric power to the network would aproximately consume 200 kg of Tritium a year. The current world reserves are of 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]].
 
http://www-fusion.ciemat.es/fusionwiki/index.php/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 1.3e21 neutrons per second. This flux will make any conventional iron to become brittle in less than a year. For this reason, a programm for material testing under heavy neutron flux has been launched. The programm, called IFMIF, aims to the development of fast neutron generation facility.
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.
 
http://www.frascati.enea.it/ifmif/
 
Also, a program for material testing in Spain has recently been lauched:


http://www-fusion.ciemat.es/fusionwiki/index.php/TechnoFusi%C3%B3n
Also in Spain, a program for material testing has been launched recently:  
[[TechnoFusión]].


==See also==
==See also==