[ RadSafe ] Re: Spent Fuel and Decay
JGinniver at aol.com
JGinniver at aol.com
Tue Jul 31 16:47:38 CDT 2007
In a message dated 30/07/2007 18:38:58 GMT Standard Time,
Mike.Brennan at DOH.WA.GOV writes:
I took a quick look through the report, and I wasn't able to find the
passages you quote, but I accept without reservation that they are there
and you presented them in context.
Hi Mike, I had another look at the report and the section I quoted from is
Appendix 3 - nature of the hazard starting on p. 341
I have a suspicion, however, that
someone who had a hand in the report was sliding something by. Two of
the three passages specifically state "Natural Uranium ore" or "the
equivalent uranium ore", and the other is ambiguous as to what is being
compared (used fuel to "Natural Uranium"). A couple numbers are given,
from 130,000 to a million years, with the latter mentioned in each
quote. I note, however, two points that cause me some concern.
Having re-read the section I had quoted from I must admit that my impression
is that the report is simply using the terminology used in the source
material. Unfortunately without reading the source material I can't confirm this.
Perhaps someone else on the list is familiar with the source material (all
listed at the end of my last e-mail and might be able to clarify this)
The first is the use of the word "ore". "Ore" generally means the
material in question (in this case uranium) mixed with the rock it is
found in. While ore is interesting, I don't think it is in this case
particularly germane. While I am not familiar with CANDU fuel, I am
reasonably certain that the ore is processed to remove the uranium, and
the uranium is then mixed with other materials and fabricated into fuel
elements. I suspect that the fuel elements have a higher percentage of
uranium than ore does (though quite possibly a lower total activity, as
the non-uranium isotopes in the decay chain would not be present in the
fuel). Thus, even if the fuel was never used it would have higher
activity than ore, particularly if one was only considering the uranium
in the ore, and all radioactive isotopes in the fuel.
The same appendix in the report gives a brief description of CANDU fuel.
What I found interesting is that although it is natural uranium (i.e. approx.
99.3% U-238, and 0.7% U-235) it is in a ceramic UO2 matrix. Whereas I had
previously assumed that is natural uranium metal rods like UK Magnox fuel.
The "one million years" figure I find interesting. When one gets past
the time where the total activity of spent fuel is dominated by fission
fragments and activation products, say three or four hundred years, you
settle into for the long haul, with the total activity driven by U-235,
U-238, and Pu-239. The fresh fuel stated with the natural ratio of
U-235 to U-238, in which the overwhelming majority of the number of
atoms are U-238, but with U-235 providing a fair amount of the activity,
due to its higher specific activity. While the burn history of fuel may
vary, the goal is to consume as much of the uranium as can profitably be
converted into energy. In fuel I am familiar with, the limiting factor
usually is the build up of neutron poisons, but most of the U-235 is
consumed, with some of the U238 fissioned directly, and some converted
into Pu-239 (mostly). Of the Pu-239, some fissions and some remains.
The report states that 'used' CANDU fuel contains approx 0.23% U-235 and
0.25% Pu-239, this compares with approx 0.84% U-235 and 0.94% Pu (estimated,
based on 4.32Kg of Pu per PWR fuel assembly with an initial mass of 461.4 Kg
Uranium) at Discharge, unfortunately the Nuclear Fact Book doesn't quote the %
of Pu present and doesn't give individual isotopes/
The question of how radioactive the spent fuel is after the short
half-life (let's say 100 years) stuff decays seems to be mostly driven
by how much of the original U-238 is left, and how much Pu-239 was
created. The Pu-239 has a much higher specific activity than U-238, as
its half life is only 24,000 years, as opposed to 4.5 billion years for
U-238. As the Pu-239 decays into U-235 the total activity of the spent
fuel decrease, eventually reaching the same total activity of the
original fuel (the activity from the additional U-235 remains small).
This is where the one million years seems problematic to me. By the
time we get out to a million years, we have about 4.5 E-11 of the
original Pu-239. Even if you started with a lot, that's not much left.
Given the loss of some of the original uranium from the fuel, I find it
difficult to believe that this many half lives of Pu-239 have to occur
for total activity to get down to that of the fresh fuel. If someone
sees a problem with my math, I would be indebted if you would point it
out.
Unfortunately the only way to work out how the values of 500,000 or
1,000,000 years have been derived would be too look at the original reports from the
IAA and EN and the NEMO report doesn't provide any detail.
If the total activity is not being compared to the fresh fuel, but
rather to the ore that provided the uranium that went into the fuel, I
see several problems, the biggest of which is that of concentration. If
concentration is the sin, then dilution is the solution. In other
words, if those managing the spent fuel are being held responsible for
the increase in activity per kilo that occurred when the ore was turned
into fuel, it only seems fair that they be allowed to dilute the spent
fuel to get back to the original total mass. This lets you compare on a
same-weight basis. Of course, once you've started diluting, there is no
real reason to stop at the original ore weight. You can continue adding
filler until the concentrations are negligible.
Unfortunately the modern regulators mantra is 'concentrate and contain.'
Dilute and disperse in no longer considered acceptable.
If I made a mistake in interpreting the words out of the report, I
apologize. I have no desire to misrepresent anyone's work. It is just
that I have on far too many occasions seen individual with a particular
agenda choose inappropriate comparisons in order to make the "other
side" look worse than they really are.
I don't see that you made any mistakes at all. It would have been better if
I had been able to include more of the original report, but I could cut and
paste from the pdf file and the time I had available meant that I was only
able to cribs what I thought would be the relevant sections.
Regards,
Julian (not Julia lol)
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