TerraPower's Natrium: A Fast Neutron Reactor with Built-In Grid Level Storage
hackaday.com
hackaday.com
Referenced in TFA, India’s PFBR “began fuel loading” in March of 2024: https://www.powermag.com/long-awaited-milestone-fuel-loading...
Looks like they've gotten a permit to start construction in Kemmerer, Lincoln County, Wyoming last May: https://www.nrc.gov/reactors/new-reactors/advanced/who-were-...
Edit: this would be for 840 MW thermal (I assume that means 840 MW worth of heat, which is then to be turned into electricity and perhaps district heating): https://www.nrc.gov/reactors/new-reactors/advanced/who-were-...
Looking into India's plant, that is apparently entirely independent of Terrapower. Sounded a bit like they got a permit to build there sooner but no:
> designed by India’s Indira Gandhi Centre for Atomic Research (IGCAR) based on the success of IGCAR’s 13.6-MWe/40-MWth fast breeder test reactor (FBTR), an experimental sodium-cooled fast reactor that has operated since 1985 [...]. The 500-MW PFBR got its start in October 2003, when the Indian government set up a wholly owned enterprise [...]. Construction of the reactor began in 2004. [...] delays stemmed from funding deficits, procurement delays, operational challenges, technical difficulties, and the geopolitical impact of the Fukushima accident.
Much further down the article, also interesting:
> At the end of 2016, Russia put online the 800-MWe (2,100-MWth) BN-800 at its Beloyarsk nuclear plant, a sodium-cooled fast reactor project that [this magazine] recognized as a pioneering Top Plant in 2016. The BN-800 reactor was, for the first time, fully loaded with uranium-plutonium MOX fuel in 2022. In December 2023, it was preparing to begin pilot operation
China also has an experimental reactor, Japan is working on one, Canada started planning one in 2022, three European counties in 2023... nuclear isn't dead?! We're actually getting safer reactors that can eat spent fuel, even if they're a bit later than one might hope for? Cool!
https://news.ycombinator.com/item?id=40658852
They applied for their NRC permit on March 28, 2024.
https://www.nrc.gov/reactors/new-reactors/advanced/who-were-...
Absolutely not my field, but can't CANDU reactors use spent fuel too? They seem pretty cool, it's not clear to me why they use them only in Canada!
There are lots of CANDUs outside of Canada though! [2]
[1] https://dspace.mit.edu/bitstream/handle/1721.1/45495/4225543... (thesis)
[2] https://en.wikipedia.org/wiki/CANDU_reactor#Active_CANDU_rea...
However it’s all the other bits like maintenance keeping nuclear expensive right now, reactor grade enriched uranium is still cheap and plentiful (~0.9c/kWh in fuel rods) which is why CANDU reactors don’t take off in the first place.
Breeder reactors operating on spent fuel can only utilize the U238 that wasn’t discarded in the initial enrichment process.
That’s what happened to the vast majority of U238 in natural uranium used to make fuel. Roughly speaking to make 100kg of 5% enriched uranium fuel you need to throw away 1,000kg of U238 + ~3kg of U235 as 1,003 kg of depleted uranium.
Understanding why really comes down to following each step of the progression from natural uranium ore > natural uranium > etc. But basically U238 is really cheap, and nothing else in the process is.
The main one is that a certain reactivity feedback loop is positive. Meaning as things go bad, they tend to get worse. There are numerous feedback loops in a reactor, and the others are negative, so overall the reactors are safe. But inherently they are less safe than pressurized water reactors. Details here [1].
Another problem is the amount of waste. Because CANDU reactors use unenriched uranium, they extract less energy from the same amount of fuel. Put it differently, they need more fuel to get a certain amount of energy. About 10 times as much. After the fuel is used, it becomes waste, and you need to handle it somehow.
Yet another problem is that deuterium is not as good a moderator as hydrogen. It does not absorb neutrons, and because of that it results in much better neutron economy, but it takes a larger volume of heavy water to achieve the same amount of moderation. So a Candu reactor tends to be bigger. It is also much more complex, because the heavy water and the regular water move in different circuits. All in all, a Candu reactor is a bit more difficult to maintain. For example, it needs to be overhauled after 30 years in order to get a life extension of another 30 years. A PWR can go for 40 years before an overhaul. That's not a huge difference, but it's something.
Of course, the other thing is that you need the initial investment in the heavy water. Last time I read about it, that heavy water added about $1 BN to the construction cost. The idea was that over the life of the reactor, one would recoup that in the cheaper cost of the fuel, which does not need enrichment. Still, $1 BN is a big number.
As for the spent fuel. You are right, Candu reactors can use the spent fuel from PWRs. But that's just in theory. I don't think in practice they do that. Reactors are complex enough. Dealing with the uncertainty of using a different fuel that the one they've been tested with is not something operators like to do without a very good reason. So in practice Candu reactors don't use spent fuel or thorium, or even MOX fuel (a mix of uranium and plutonium).
The increase in PV and wind power means storage plays a much larger role today than could have been conceived of in 1977.
IMHO, a more self-explanatory term, like "medium enriched uranium (MEU)", would be much more useful for everyone.
i.e. why can’t you feed the Natrium reactor the usual 5% enriched fuel you’d use in an LWR ?