Comment Re:Burn the Uranium in safe Thorium reactors... (Score 1) 146
The continuous-process system envisaged by LFTR enthusiasts needed to purify the molten-salt stream and prevent the reactor from shutting down due to poisoning can be tapped to extract any particular element with a bit of surreptitious work, and that includes extracting pure kickstarter U-235 (which is easy to make a bomb from) or pure kickstarter Pu-239 (trickier to weaponise but still possible) or U-233 bred from thorium (which also works as bomb material but not as well as U-235).
Removing fuel from a running reactor, and thinking no one will notice, is insane. Thinking you're going to be able to remove weapon grade material from a running reactor is beyond insane. Once that reactor reaches critical there's going to be all kinds of interesting isotopes created. The plutonium will quickly be contaminated with Pu-240 and the uranium contaminated with U-232.
Current conventional reactors produce a mixture of Pu-239 and Pu-240, useless as bomb material, in spent fuel since the operating cycles last for a year or more between refuelling and some of the Pu-239 undergoes another neutron capture to make Pu-240. Pu-239 can't be separated from Pu-240 without great effort; the centrifuges or other enrichment equipment needed could purify U-235 from raw uranium much more easily.
Same goes for MSR. The operators of the reactor are not going to remove any fuel until they can sustain a critical state with bred U-233. That will take about a year. Taking out any fuel before then is going to make a noticeable drop in power output. That fuel is hot enough to melt aluminum and most common steels. It will also be contaminated with isotopes that are gamma emitters, easily detectable from vast distances.
If the Pu-239 is going to be stolen it's going to be before it gets to the reactor, that holds true for MSR and MOX.
MOX fuel formulations are only a small percentage of Pu, typically something like 6% or so hence the term Mixed-OXide comprising both uranium oxide and plutonium oxide. A MOX fuel element will still have Pu in it after it has spent a cycle in the reactor but much of the original Pu-239 and Pu-240 will have been fissioned. More Pu will have been bred from the U-238 comprising most of the rest of the fuel element but the total inventory of Pu in the spent fuel will have been decreased while producing a significant amount of process heat for electricity generation and other uses such as desalination. The spent fuel rod can of course be reprocessed and the Pu reconstituted as fresh MOX fuel.
That's nice, Pu-239 and Pu-240 is reduced in MOX fueled reactors. In MSRs the Pu-239 and Pu-240 is destroyed, it never leaves the reactor.
I don't know of any proposed LFTR operational cycle that would produce Pu-238 in any significant quantity; breeding up from Th-232 all the way to Pu-238 is a lot of steps requiring several neutron captures and decays with several intermediates which would interrupt the chain if fissioned. Adding Np-238 to the molten-salt fuel might work to make Pu-238 but the only source of Np-238 in quantity is a conventional nuclear reactor...
LFTR does not produce Pu-238 in significant quantity. It produces enough to be financially advantageous to extract. My point is that any plutonium that is produced will peak at Pu-238, it will rarely get heavier since Pu-239 and Pu-241 are so readily fissile.
Your claims of stealing Pu-239 from MSRs makes as much sense as stealing it from MOX fueled plants. The difference is that getting Pu-239 from MSRs is near impossible. All the Pu-239 we have right now came from solid fuel reactors like those fueled with MOX. This feature is why the MSR technology was not pursued, the reactors were worthless for producing weapon grade material.