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Strategy, Politics & International Relations Forum • Re: India Nuclear News and Discussion 4 July 2011

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Will the spent fuel even be worth reprocessing? Article indicates that it will not have viable weapons level of elements of interest (Pu?)
Will it have significant level of U-233? In that case wouldn't it be used in the current reactor itself?

Thanks
FWIW: In addition to what I said above, adding/clarifying to explicit question(s):
1. Will the spent fuel even be worth reprocessing? -
ANEEL design intentionally avoids producing significant quantities of weapons-grade isotopes like Pu-239. This is a safety and proliferation-resistant feature inherent in thorium fuel cycles. In thorium reactors, thorium-232 absorbs neutrons to eventually breed U-233, which is fissile but designed to be denatured by co-producing U-232, an isotope that complicates handling due to its strong gamma radiation.

Worth for reprocessing? - Even if not weaponizable, the spent fuel still contain valuable fissile materials, like U-233, which could make reprocessing worthwhile. (It all depends on many other factors -- viability of reprocessing depends on the recovery cost versus vs importing new fuel. -- In general If the reactor is designed to minimize waste and maximize burn-up, the incentives for reprocessing could decrease)

- Will it have significant levels of U-233?
Yes, ANEEL fuel is designed to breed U-233 from Th-232. Depending on the reactor's operating conditions (neutron flux, burn-up rates, etc.), the spent fuel could have significant amounts of U-233.. but as said , U-233 may be mixed with U-232, which emits high-energy gamma rays, complicating its handling etc.
( The production of U-233 is a cornerstone of thorium fuel cycles, and its quantity in spent fuel is expected to be enough for consideration in reprocessing .. in my thinking)

- Wouldn’t the U-233 be used in the current reactor itself?
Yes, in a closed fuel cycle or advanced reactor designs like the ANEEL, U-233 produced in the reactor can be recycled as fuel. This aligns with thorium's primary advantage—creating a self-sustaining fuel cycle.

If reprocessing is performed, the recovered U-233 could either be recycled back into the same reactor or used in another reactor designed for U-233 fuel, such as molten salt reactors (MSRs) etc...

Hope the info. is useful.

Statistics: Posted by Amber G. — 16 Jan 2025 02:59



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