Can Zirconium from Nuclear Waste be Recycled for Other Uses?

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Discussion Overview

The discussion centers around the potential for recycling zirconium from nuclear waste for other applications. Participants explore the feasibility, economic implications, and safety concerns associated with extracting zirconium, particularly focusing on its isotopes and the challenges posed by radioactivity.

Discussion Character

  • Exploratory
  • Technical explanation
  • Debate/contested

Main Points Raised

  • Some participants argue that while zirconium from fission products contains radioactive isotopes like 93Zr, it is also used in a radioactive environment, which may mitigate concerns about its radioactivity.
  • Others suggest that extracting zirconium from nuclear waste is technically possible but likely not economically viable compared to traditional mining methods.
  • Concerns are raised about the handling of radioactive waste and the high costs associated with processing it, especially given the significant radioactivity levels of nuclear waste.
  • Participants note that the neutron cross-section of Zr-92 is low, which is beneficial, but question whether Zr-93 shares this characteristic.
  • Some contributions highlight that more than 5% of the waste is Zr-93, which may be in a largely unoxidized form, potentially simplifying the chemistry for extraction compared to ore.
  • There is a discussion about the implications of using contaminated zirconium in fuel cladding production, including contamination of equipment and increased regulatory burdens.
  • One participant mentions the low fission yield of Zr-93 and the long half-life of 93Zr, suggesting it may not be very radioactive, but emphasizes the complexities of reprocessing spent fuel.
  • Details are provided about the composition and use of zirconium alloys in fuel assemblies, noting that recycling these alloys would be problematic due to activated alloying elements.

Areas of Agreement / Disagreement

Participants express multiple competing views regarding the feasibility and practicality of recycling zirconium from nuclear waste. There is no consensus on whether it is economically viable or safe to do so.

Contextual Notes

Participants acknowledge limitations related to the handling of radioactive materials, the economic implications of extraction versus mining, and the complexities of reprocessing spent fuel, which remain unresolved.

dgjxqz
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Zirconium from fission product cannot be safely used as it contains 93Zr which is radioactive. However, zirconium is also used for fuel cladding and building some other parts of a reactor, which is already a radioactive environment thus its own radioactivity is no longer a concern.
So, is it possible to economically extract zirconium from nuclear waste for something useful rather than burying it?
 
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Is it possible to extract zirconium from nuclear waste - I'm sure it is possible.
Is it cheaper to produce zirconium this way than simply mining zirconium - almost certainly not.
 
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I think the major problem would be in the handling of the radioactive waste.
The other is that the neutron cross-section of Zr-92 is very low, which is why it is used. I don't know if Zr-93 shares that characteristic.

Aside from that, more that 5% of the waste is Zirconium-93 - and it is likely to be in a largely unoxidized form. So the chemistry for removing Zr from the waste should be easier than it is from ore. Also, if you wait a few months, the unstable isotopes remaining will be Zr-93 and Zr-95.
 
dgjxqz said:
However, zirconium is also used for fuel cladding and building some other parts of a reactor, which is already a radioactive environment thus its own radioactivity is no longer a concern.
It is a big enough problem already that the used fuel is radioactive: nobody needs unused fuel which is radioactive. So, it is a concern.
I don't know how radioactive 93Zr is. What I'm saying is just that the radioactivity of the input side does matters.
 
dgjxqz said:
However, zirconium is also used for fuel cladding and building some other parts of a reactor, which is already a radioactive environment thus its own radioactivity is no longer a concern.

Just imagine the complications and associated costs of using contaminated Zr in a production of fuel cladding. All the production equipment becomes contaminated. What joy.

And the resulting fuel bundles now are radioactive and the rules for their handling are much more restrictive.
 
.Scott said:
Aside from that, more that 5% of the waste is Zirconium-93 - and it is likely to be in a largely unoxidized form. So the chemistry for removing Zr from the waste should be easier than it is from ore.

Chemistry per se may be somewhat easy, but nuclear waste (after U and Pu removal) has radioactivity on the order of ~1 million R/h.

Doing anything with it is VERY expensive, that's why usually nothing is done with it. In US, nuclear industry even went with the route "we won't even bother with U/Pu removal step, let's just keep spent fuel securely stored in heavily shielded containers for now", and it makes economic sense.
 
dgjxqz said:
Zirconium from fission product cannot be safely used as it contains 93Zr which is radioactive. However, zirconium is also used for fuel cladding and building some other parts of a reactor, which is already a radioactive environment thus its own radioactivity is no longer a concern.
So, is it possible to economically extract zirconium from nuclear waste for something useful rather than burying it?
The fission yield of Zr-93 is very low, on the order of 1E-6. The yield of Zr-95, from thermal fission of U-235 is on the order of 0.06.

The half-life of Zr-93 is 1.6E6 years, so it would not be very radioactive. Recovery would require reprocessing of the spent fuel, which means dealing with all the other radionuclides. It would be more practical to use the irradiated Zr to combine with other radionuclides for final disposal.

Natural Zr is 0.5415 Zr-90, 0.1122 Zr-91, 0.1715 Zr-92, 0.1737 Zr-94 and 0.028 Zr-96.

Fuel assemblies use Zr-alloys for fuel rod cladding and endplugs, water rods (BWRs) or guide tubes (PWRs), spacer grids, and channels (BWRs). The Zr-alloys include Zircaloy-2 (BWRs), Zircaloy-4 (PWRs, and non-fuel components in BWRs), and more recently Zr-1Sn-0.6-1.0Nb-0.1-0.35 Fe or Zr-1Nb, where the coefficients represent wt%, with Zr being the balance. The compositions are tightly controlled, so beside the radioactivity, recycling irradiated Zr-alloys would be problematic, since some of the alloying elements become activated and would have to be separated and disposed in a manner similar to spent fuel.
 
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