analysis's compares with mine (if you can find it) and how we handle the data, and the type of simplifying assumptions we make. (Since I have never taken such a class - it will be especially interesting for me.)
The file below has some relevant and interesting data, specifically the energy value, sulfur content and ash content of coals and wood. For some reason, the metric values (ignoring the even more unworkable English units) give the energy in kilocalories/kg for these sources. As I'm sure you know, a kilocalorie is converted to a kilojoule by multiplying by 4.184. One simplifying assumption I will need to make is a sort of "universal energy value" of coal.
http://www.epa.gov/ttn/chief/ap42/appendix/appa.pdfFor accumulations of nuclear materials, years ago I derived the (simplified) relationship A = P(1-exp(-kt)) for how fission products accumulate. Here A is the accumulated mass (in most of my spreadsheets, given in metric tons), P is the maximal amount of a fission product that can accumulate before the fission product is decaying at exactly the rate it is created at a particular output for nuclear generated power, k is the decay constant for the nuclide decay constant, which is simply the natural logarithm of 2 divided by the half life, and t is the time at which a given power output has been generated by nuclear means. For convenience, I always use time units of seconds in values involving time.
As I usually do, I will not treat any Uranium, Plutonium, or minor actinides as "waste" since I find such a conception most unfortunate. (I regard these materials as resources.) I am aware however that public policy in the United States - though not elsewhere - my objection notwithstanding has managed to define these materials as "wastes."
Some simplifying assumptions went into this derivation. The differential equations that nuclear engineers call the "fuel depletion" equations can be quite complex and are often solved numerically using sophisticated fuel depletion programs like ORIGEN (to which I have no access). These programs account for issues like neutron fluxes and capture cross sections, sometimes - as I understand it - using "multigroup" analyses - in which neutron energy distributions, of which the cross sections are functions, are considered.
I have fudged all this by simply using the "accumulated fission yield" available for each nuclide in the Table of Nuclides.
http://atom.kaeri.re.kr/ Fission yields actually vary with the particular nuclide being fissioned. The "big four nuclides" under modern conditions can be considered to be Uranium-235 (by far now the biggest), Plutonium-239 (the next most important), Uranium-233 (which one hopes, for non-proliferation reasons, will become more important) and Plutonium-241, which becomes important when fuel is recycled. Because as a practical matter, most nuclear energy is still generated using U-235 enriched natural Uranium, and the vast majority of reactors in the world are thermal, I have used the values given for fission in U-235 under thermal conditions (0.253 MeV neutrons) in the tables. Note that the (internet) tables do not even give the values for Uranium-233 or Plutonium-241. This is trivial though: Most heavy nuclides have fission product distributions that look like camel humps and fissioning heavier nuclides move the hump reflecting the higher mass nuclides slightly to the right, towards heavier fission products. (The effect on the most important element in the heavy part of the fission product hump, Cesium, is slight.)
In general values are better when we consider so called "nuclear wastes" that have been removed from the reactor as spent fuel, although I don't think this makes all that much difference in most of the important cases. In any case, these are the most important values for people who are considering what to do with fission products, whether or not one regards them as "wastes" or as useful materials. The "constant" P I have used above, is obtained from from the fission yields, the power output and conversion factors (the electron charge, Avogadro's number, the energy yield per fission - generally taken to be 190 MeV per fission.)
Now I'll go back, consolidate some of the hundreds of spreadsheets I've generated jerking around with this data over the years, and get back when I have a chance.