Jeremy Thomson said:
I believe spent fuel from fission is about half transuranics and half fission products. Am I right in that fusion 'spent fuel' will be isotopes of helium? Which if radioactive have very short half lives. So the 'products' of fusion aren't a problem but the activated reactor walls will be just as much a problem as a fission reactor when it comes to decommissioning. But will it be worse, the same or better. I suspect worse because with fusion you actually want the neutrons to hit the walls and make heat.
Spent LWR/Candu/AGR fuel consists of unused UO
2 (or MOX), which is the majority and the fission products (FP) and transuranics (TU). The amount of FP and TU depends on burnup (energy/mass) of the fuel and time. It now common to have fuel with burnups of 45 to 60 GWd/tU, which is approximately 4.5 to 6% of the initial fuel consumed (4.5 to 6% fima), and I believe a lesser fraction of TU. I'll have to check on the TU fraction as a function of burnup.
The structure will become activated, so that would become radwaste, when the structure is removed. It has to be stored somewhere such that the radioactive material does not enter the environment/biosphere.
Adding to what the _wolfman has mentioned, He-4 and He-3 are not radioactive, so they are not a problem. Any T bred has to be collected and its release mitigated.
One could do useful comparison of a fission and fusion system on the basis of 1 GWe. However, that requires some details of each system, e.g., fuel cycle and operating cycle, as well as detailed designs.
For fusion systems, one goal is to identify low-activation, radiation-resistant structural materials.
This reference provides some information on fission products, transuranics and activation products in LWRs - Radiochemistry in Nuclear Power Reactors
http://www.nap.edu/download.php?record_id=9263
One example for UO
2 shows (Figure 2-4) that at a burnup of 35 GWd/tU, or ~3.5% fima, the Pu content is about 1% of the fuel metal with about half being Pu-239, one-third Pu-240, and 10% Pu-241. Less than 0.1% consists of Am-241, Cm-242 and Cm-244.
Figure 2-5 shows that for 2.5% at 40 GWd/tU, U-235 account for less than 20% of fissions, while Pu-239 represents slightly more than 50% and Pu-241 about 20% of fissions. U-238 undergoes fast fission, and it starts at about 7% of fissions and increases to about 8-9% of fissions. For higher enrichments, the U-235 fraction of fissions would not decrease as quickly, and Pu-239, Pu-241 would show a slower increase, which is due to self-shielding.