The FuTure oF nuclear Fuel cycle - MIT Energy Initiative
The FuTure oF nuclear Fuel cycle - MIT Energy Initiative
The FuTure oF nuclear Fuel cycle - MIT Energy Initiative
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Twice-Through Cycle<br />
Table 7A.3 shows the key engineering and other<br />
economic assumptions used to calculate the<br />
LCOE for the Twice-Through Cycle. <strong>The</strong> calculations<br />
of the levelized costs for the various components<br />
are conducted in exactly the fashion as<br />
described immediately above. However, since the<br />
Twice-Through Cycle involves the expression of<br />
the cost and credit for the separated plutonium,<br />
we detail that calculation in particular, and we<br />
show how the value for the separated plutonium<br />
is derived. Also, because the cost of disposing of<br />
the spent MOX is critical to the final LCOE, we<br />
explain that calculation in some detail.<br />
Reprocessing and <strong>Fuel</strong> Fabrication Costs as a<br />
Function of the Value of Separated Plutonium<br />
Each 1kg of spent UOX leads to the separation<br />
of 0.011kg of plutonium. We denote the attributed<br />
price of plutonium as p, denominated in<br />
$/kgHM, and then calculate the total attributed<br />
value to the separated plutonium, measured per<br />
unit of electricity originally produced by the fuel<br />
being reprocessed as:<br />
table 7a.3 twice-through <strong>Fuel</strong> Cycle Specifications<br />
FirSt reaCtor, burninG uox<br />
Front-end fuel parameters<br />
same as oTc<br />
reactor capital costs<br />
same as oTc<br />
reactor operating costs<br />
same as oTc<br />
Spent fuel pool storage period<br />
same as oTc<br />
loss during reprocessing (u & Pu) 0.2%<br />
reprocessed uranium recovered 0.930 kghM/kgihM<br />
Plutonium recovered 0.011 kghM/kgihM<br />
enrichment target for reprocessed u 5.16%<br />
optimum Tails assay for reprocessed u 0.39%<br />
Feed for reprocessed u 7.63 (initial kgu/enriched kgu)<br />
Separative Work units for reprocessed u 4.80<br />
Price of reprocessed u from uoX 108.30 $/kghM<br />
SeCond reaCtor, burninG uox and mox<br />
loss during MoX fabrication 0.2%<br />
u-235 content of depleted uranium 0.25%<br />
depleted uranium required as % weight 91.3%<br />
Plutonium required as % weight 8.6%<br />
lead time for plutonium separation 2 years<br />
americium as % weight 0.1%<br />
reactor capital costs<br />
same as oTc<br />
reactor operating costs<br />
same as oTc<br />
We leave this value expressed as a function of the as yet unspecified attributed price of plutonium,<br />
p. This is solved for below.<br />
By a similar calculation for the second reactor which is fed with MOX fuel fabricated from<br />
the separated plutonium, and assuming that 8.73% of the fuel by weight is composed of<br />
plutonium and Americium coming from spent UOX, we have:<br />
<strong>The</strong> Second Reactor Back-end <strong>Fuel</strong> Cycle Cost<br />
We assume that after a period of temporary storage the spent MOX will be sent to a geological<br />
repository just as we had assumed for the spent UOX in the Once-Through Cycle.<br />
We base our calculation of the cost of disposal of the spent MOX off of the cost of disposal<br />
of spent UOX. This had included two parts: a cost of above-ground storage equal to<br />
$200/kgiHM, and a cost of disposal in a geological repository equal to $470/kgiHM. <strong>The</strong><br />
$470/kgiHM cost for disposal is derived from the current 1 mill/kWh statutory charge to be<br />
paid 5 years after unloading of the fuel. For spent MOX we assume the identical cost for the<br />
appendix to chapter 7: economics 177