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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

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