Posted on 01/31/2015 1:05:27 AM PST by ckilmer
Today, it was announced that the Department of Energyâs Oak Ridge National Laboratory  (ORNL) in Tennessee is partnering with Canadian nuclear company Terrestrial Energy Inc. (TEI) to assist with TEIâs new Integral Molten Salt Reactor (IMSR). The engineering blueprint stage for this GenIV reactor should be reached in two years. The reactor should come online in less than ten.
(Excerpt) Read more at forbes.com ...
Thanks for getting the reference
It makes a huge difference in how reactors for each must be designed, as the neutron economies (reaction cross-sections, number of neutrons generated per fission, and more) are significantly different for the two isotopes.
Because the PBR's are not nearly as safe nor economical as their propagandists claim. Long-term research studies in prototype reactors shows that the fuel "pebbles" leak far more radioactivity than claimed, and wear out faster.
There was a long thread about this a couple of years ago.
Yes, I'm well aware of that (minored in nuclear science while getting my PhD in chemistry). But the reaction characteristics of the two isotopes are different, and 233 is NOT the isotope used in U-Pu "burner" and/or "breeder" reactors reactors. That is 235. And for an article that claims to be authoritative, that mistake is NOT one that should have been made.
the huge hope is that portable assembly line built thorium reactors will produce electricity for 1/2-1/4 the cost of the cheapest coal.
that would be the first time I heard that the russians successfully produced molten salt reactors. the way I heard it was that in the 60’s & 70’s the russians and indians both tried to do molten salt reactors but when the USA gave up both the russians and the indians gave up on molten salt reactors.
Hey! Canadians are Americans (so are Mexicans)
Nah, we can just steal it and improve it. Then we can tell them we are now even for all the intellectual property they have stolen from us.
I think the ground under this will shift here in the next couple of years, because there’s too many players getting into the game. The most recent is martingale thorcon. This company has an impressive bunch of founders and may well wind up with google funding.
http://nextbigfuture.com/2015/01/low-cost-walk-away-safe-molten-salt.html
Yes, many mistakes in the article - some pretty funny.
A LFTR needs U-233 to start the reaction, as I understand it. Then Thorium decay cycle maintains the reaction with a minimum of resulting actinides. Not really a burner fast neutron reactor.
The TE IMSR looks like it will use Uranium decay cycle, so more actinides. Good for burning “spent” fuel is the thinking I suppose.
Any thorium-cycle reactor can use any fissile material that is available for startup....U-235, U-233, or Pu-238. The excess neutrons from that "starter fuel" then "breed" Th-232 into U-233, which continues the cycle until all Th has been converted and "burned".
I am isophobic
Hahahaha, respect chinese intellectual property like they respect ours.
Bill gates will have iy reversed engineered i two weeks.
And patented.
And in every third world household.
As an add on to windows xp plus
The TE IMSR is a single fluid burner that will need infusions of Uranium. Disposal of spent fuel I suppose is the selling point.
Look, any startup will have to factor in costs of royalties or the legal costs in fending off litigation from employment of reverse engineered ip. Our system, which holders of ip will use, plays by the rules. It is not a problem that can be laughed off.
But a system that nationalizes industry to protect the proletariat, be upset overthe prolitariot using their system to further the cause... Ends justifying means
Sodium cooled-mix with water “Boom”! Lead/ Bismuth also used as coolant.
On average 96% of the initial fuel energy content remains in spent fuel assemblies, pulled due to accumulation of neutron absorbing contaminant reaction products. Decades worth of accumulated spent fuel once destined for “Yucca” can be re-purposed as a fuel source.
When Thorium breeding of fuel becomes necessary/ desired, the 3400# of pure U233 stockpiled will fulfill its most favored role.
Throwing away the bulk of the fuel energy content remaining within the fuel kernel heart of the pebble.
U233- more neutrons available for fuel breeding.
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