I am given a table that describes an ancient spillage of spent nuclear fuel:
Pu-232 0.1150% Pu-239 0.3730% Pu-241 2.2900% *Sr-90 44.3000% U-234 0.1290% U-235 0.0112% U-235 0.0079% U-238 0.0496% Am-241 0.1920% Cs-137 52.5000%
Time since the spill happened until measurement: 36 years
The slightly high proportion Sr/Cs could be because an extra spillage of 90Sr that happened time after in the same installation. But note the proportion of 241Pu, is it very high, isn't it?
So I think that this table shows a measurement of relative activity. How should one proceed to transform it to a table of isotope proportions?
According to notes, the spent fuel come from the SAPHIR reactor, but given that this reactor was sharing installations with the DIORIT, I wonder if it could be a mix from both. Also, the spillage did not happened in the origin lab, so some extra time, perhaps six months or one year, should be added to compare it with original "cask strength" fuel.
My first approach has been simply to use half-life to factor out the activity, then normalizing again... Then obviously I get a result where U-238 is the main component. Does it fit with the spillage of burned fuel? Or perhaps the proportions are not Becquerels but Sieverts or Grays? I wonder because, as Jacobson points out, even after correcting for activity the ratio Am/Pu seems to be out by a factor two (or perhaps it is just that it has been washed away during periodic cleaning of the room after the years)