neutrons required to maintain fission uranium 233

#Neutrons required to maintain fission uranium 233 how to

In initial investigation of this idea this author received assistance from Mr. Then if the liquid sodium cooled reactor operates at 450 degrees C the ThF4 will be immersed in liquid FLiBe and the PaF5 will accumulate at either the top or bottom of the FLiBe column. At this time we are uncertain as to whether the relative densities of FLiBe and ThF4 will permit that to be the case.

It is essential that the ThF4 remain in the high neutron flx region. Note that it is essential that PaF5 be mobile in the aforemetioned mixture and that the PaF5 concentrate at either the top or bottom of the FLiBe column. The concept is to finely grind the ThF4 so that it exists as a powder immersed in molten FLiBe. Some of the UF6 will fission and some will remain for later recovery via fuel tube reprocessing. At that point it will form UF6 which as a gas will concentrate in the tube plenum. When Th-232 absorbs a neutron it quicky becomes Pa-233.Īt an appropriate temperature the PaF5 will concentrate either at the top or bottom of the FLiBe column where it should remain out of the neutron flux for at least a month until it naturally decays to form U-233. The concept is to partially fill the fuel tube with FLiBe (LiF-BeF2) to which ThF4 is added. The desired process is thought to be possible. If the Pa-233 remains in the neutron flux it will become Pa-234 and the desired U-233 breeding will not occur. One of the important functions of these novel fuel tubes is to breed Pa-233 and then immediately shift the Pa-233 out of the fast neutron flux until it decays to form U-233, at which time it can re-enter the fast neutron flx for subsequent fissioning. Essentially the idea involves adding novel fuel tubes to a fuel breeding fast neutron reactor that operates using the U-238 to Pu-239 fuel cycle. In March 2021 this author conceived what might be a workable idea.

#Neutrons required to maintain fission uranium 233 how to

The issue is how to utilize this knowledge in a practical nuclear reactor. It is believed that the number of neutrons per fission yielded by U-233 substantially improves in a fast neutron flux. This web page examines a novel process for making U-233.Ī major impediment to use of thorim as a source of prime energy is the relatively low number of neutrons per fission yielded by U-233 in a slow neutron flux. Hence in terms of providing long term energy supply for human civilization, a fast neutron reactor technology that can operate using Th-232 as its primary energy source has sustainability advantages over U-238. It is believed that thorium is about 4X more abundant than uranium.

The ability to sustainably produce the fissile isotope U-233 from Th-232 has huge implications for the sustainable energy supply and hence for the sustainability of human society on planet Earth. FNR U-233 PRODUCTION By Charles Rhodes, P.Eng., Ph.D.