Moltex gets a lot less interest than I think it deserves. There is a grassroots movement to develop MSRs that started out with an interest in fluoride salt reactors breeding U233 from Th232. I saw people look at many configurations but the one that Moltex has developed using chloride salts and breeding Pu239 from U238 seems to solve most of the practical problems.
Ordinary fast reactors can, in principle, consume all the transuranics they produce and leave waste that is less radioactive than the original fuel in 1000 years. In principle the neutron economy of a fast MSR can be so good that you can put back all the most problematic elements like Cesium and Iodine and end up with waste that is mostly decayed in 100 years.
Ordinary fast reactors can, in principle, consume all the transuranics they produce and leave waste that is less radioactive than the original fuel in 1000 years. In principle the neutron economy of a fast MSR can be so good that you can put back all the most problematic elements like Cesium and Iodine and end up with waste that is mostly decayed in 100 years.