That's not actually accurate, but OP's comment was inaccurate anyway.
LFTR is one idea: You fission U-233 such that one neutron continues the chain reaction and another is absorbed by a thorium blanket; the resultant U-233 is extracted and placed in the fissile stream. You do this in a thermal spectrum, using a fluoride salt as carrier solvent for everything as well as being part of the moderator system.
Unfortunately, this won't work for spent LWR fuel; they've already given up all the goodies they can handle in the thermal spectrum. This is why you hear all the talk about fast reactors; much of the fissile load in spent LWR fuel is flavor of Pu, which only perform well in a fast neutron spectrum. Further, other trans-actinides only fissile at all with fast neutrons. Fluoride is too moderating, so that can't be used as a carrier salt.
What's used instead is a LCTR (Liquid Chloride Reactor). Works pretty much the same way, except (a) you have a much bigger core (fast neutrons go further), (b) the fissile stream is fueled ONLY by spent LWR fuel, (c) you shunt off the U-233 for seed material for LFTRs. This also puts you in the fortunate position that your fuel salt is already easily processed as a liquid, in a form that is commonly used for what's called "Pyroprocessing" anyway.
While you could, in theory, harvest the plutonium that occurs in this cycle, there are serious engineering challenges to that task. The expense alone to do it frequently enough to avoid significant amounts of Pu-240 and Pu-241 would be astronomical.