Thorium Molten Salt Reactors – A Really Short Intro
Thorium is about thrice as abundant compared to Uranium. And countless times more abundant than the U-235 Uranium isotope that is used mostly by modern nuclear reactors.
You can use Thorium, Th-232, as the sole fuel in a special nuclear reactor, which first turns the Thorium into Uranium, namely, U-233, and then splits it in fission. The good thing is that very little Thorium is needed (under 1000 kg per gigawatt year), and no isotopic enrichment (that Uranium needs to separate U-235 from U-238 ) has to be done, and there are practically no transuranic products from the reactor (that’s the long-lived radioactive stuff). The reactor is called the Molten Salt Reactor – MSR, or the Liquid Fluoride Thorium Reactor – LFTR. The trick is to not use any fuel rods, but have the nuclear fuel in a molten salt. More on why this is done below.
A U-233 atom receiving a neutron splits into fission products, giving energy, and also gives off two neutrons (statistically, a bit more). One neutron is used to hit another U-233 so the reaction continues, while the other is used to turn Th-232 into U-233. This is called breeding, where enough neutrons are produced so they can, in addition to keeping the chain reaction going on (like in all current nuclear reactors), also “breed” new nuclear fuel.
Now, there are some breeder research reactors working with U-238, the more common Uranium isotope, being bred to Plutonium Pu-239, but with Plutonium the problem is that you have to use fast spectrum (otherwise there won’t be enough neutrons), which again often brings some controllability issues. Also, nuclear bomb material can be produced because Pu-239 is easy to separate chemically compared to the different isotopes of Uranium which are chemically similar. U-233 from a Thorium reactor on the other hand is not very suitable for bomb material, and there are options to denature it while in the reactor so it’s unusable.
The Th-232 / U-233 MSR is unique in that it can be a breeder reactor in a thermal spectrum. This is achieved with keeping both the fertile and fissile material in a molten salt, Thorium and Uranium Tetrafluoride. (ThF4 / UF4.) The reactor core is filled with Uranium while there is a blanket of Thorium around. When a Thorium atom changes into Uranium, it is taken out of the blanket by bubbling the blanket it with Fluorine gas which turns the UF4 into UF6, a gas. It is again reduced to UF4 with hydrogen and then put into the core. This is the critical idea of the molten salt reactor, continuous reprocessing. Also, the fission product waste can be removed during continuous reprocessing (vacuum distillation). The molten salt also enables harmful fission products like Xenon to bubble out of the molten salt immediately so they don’t worsen the neutron economy by capturing neutrons themselves (a significant problem in current reactors, limiting their fuel use percentage.)
The MSR has been demonstrated in the US Oak Ridge National Laboratory in the sixties and seventies with multiple prototypes, but the development stopped since the fast uranium breeder was the way chosen instead (for a variety of reasons, many of which are not valid today).
Many think that it could be a good solution to the energy crisis. It is relatively known technology yet changes the nuclear equation hugely, by reducing fuel needs AND waste immensely, multiple ten fold. 1000 kg per year for a gigawatt sized plant would mean you could run 30 years with one container of Thorium. The waste, of similar mass, could be relatively safe after 300 years, since it would not have much transuranic elements.
Sadly, most nuclear engineers have not even heard about MSR / LFTR. There is a lot more material on Kirk Sorensen’s site, energyfromthorium.com, most highly recommended.
As Alvin Weinberg said, we are still living in the First Nuclear Age. The Molten Salt Reactors could bring the next one.
I’ve been planning a few posts about molten salt reactors so this is an introductory post to the matter. Please, ask anything in the comments!
I’ve been a fan of the concept ever since I stumbled on Kirk’s blog. With the potential availability of Thorium from KREEP deposits on the Moon, it could become an important part of an off-world nuclear economy.
Not to mention the whole much cheaper and less waste bit for terrestrial economies.
I look forward to seeing some more of your thoughts.
I’ve been looking around the web, are there any companies currently pursuing research and development on this design in the US? I know that a Japanese group is working with the Fuji II, but since this is a designated Gen. IV design, you would think there would be DOE contracts out or something!?!?
This has also fascinated me since finding Kirk’s blog. It makes a great deal of sense, there was some significant testing (back in the days when engineers could just try things) but there is almost no possibility of the necessary development happening.
There may be a downside. I have heard that some of the waste products are things like Americium, which are readily absorbed by the body. One critic said that he preferred Plutonium as at least it didn’t collect in people. I guess that Thorium byproducts are more of a danger now and Uranium byproducts are more of a problem for the next few millenia. That might actually be a fair trade.
None as far as I know. Some work at universities and labs. There are companies proposing solid fuel rods with Thorium to conventional light water reactors but that’s an extremely bad way of using Thorium because you get losses since there’s no Uranium or fission product separation.
I’ve never heard about specific Americium production from Thorium MSR:s.
Since Americium’s atomic mass is 243, U-233 would have to absorb ten neutrons (and beta decay so some would become protons) before it could become Americium. From Pu-239 there’s only four neutrons to Am-243.
Hence the claim seems a bit unlikely to me.
Also couple this with the online reprocessing where many materials can be removed, hence you can remove something when it hasn’t yet become so nasty, although this one I’m not so familiar with and also it adds complications and cost.
Also, there appear to be some “related” links below my blogpost that wordpress inserts and I can’t get rid of. The nukeginrich blog one erroneously states that you need an accelerator to enable Thorium energy. That is NOT true. It is a very common mistake, I guess it somehow is misinterpred from some press releases from a Norwegian particle physicist who has promoted the idea for years.
This topic was a great and nice surprise! Tremendous!
Looking forward to more and I hope this subject might “catch fire” because it really ought to be widely known that humanity already has all the solutions needed (and more).
Americum is a transuranic far up the chain. It is produced only by absorbing lots of neutrons. You have to absorb neutrons rather than fission at U233, U235, Pu239, and Pu241, before you can get Americum. Very little is produced (roughly 0.1%). Then in an MSR you put the transuranics back into the fuel salt and it will also fission. In the end what is left is only the portion that escapes the chemical separation process to put it back into the fuel. Estimates for this are that between 0.1% and 1% will be missed in the chemical separate and go out with the fission products. So in total we are talking about 10^-5 or so. Translating this to grams per GWe-year depends on the rate at which the fuel salt is reprocessed but it is a very small amount in any event.