Claude Degueldre1,Joshua Findlay1,David Cheneler1
Lancaster University1
Claude Degueldre1,Joshua Findlay1,David Cheneler1
Lancaster University1
The Molten Salt Fast Reactor<b> (</b>MSFR) liquid fuel is made of uranium chloride dissolved in sodium or rubidium chloride. <sup>235</sup>U enrichment goes from 0.3% (depleted) for power plant to 20% enriched for research reactor. At End of Live (EoL) the fuel cycle strategies go from the once through then out i.e. full geological disposal (spent fuel, core vessel and structurals’ of primary) to spent fuel and primary loop material reprocessing and recycling. The late case is emphasized when the chloride of the fuel and from the reflector are made of <sup>37</sup>Cl enriched chloride and has to be reprocessed and recycled for economical reason in new fuel and reflector.<br/>The first option would require addition of neutron absorber prior to final geological disposal in a water free environment e.g. in salt dome. The option of Molten Salt drainage in specific tank designed for radwaste disposal would be associated with intelligent barrier to minimise first nuclide release such as <sup>36</sup>Cl and <sup>126</sup>I. Among them Ag or Cu barriers could be envisaged.<br/>The second option deals with the Na/Rb<sup>37</sup>Cl - <sup>dep</sup>U<sup>37</sup>Cl<sub>4</sub> spent fuel in which case <sup>37</sup>Cl has to be, for economic reason, reprocessed for recycling.<br/>In memory of Lou Vance, Ansto