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The FuTure oF nuclear Fuel cycle - MIT Energy Initiative

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Fast reactor technical Characteristics (continued)<br />

<strong>The</strong> spent Fr fuel reprocessing and<br />

the Fr fuel fabrication (including shipping<br />

and storage at reactor site) are<br />

assumed to take 1 year 2 each.<br />

notes<br />

1. We deem 5 years to be more realistic.<br />

[Bunn et al., 2003] implicitly assumes only<br />

1 year of cooling before reprocessing;<br />

[NEA, 2009] assumes 4 years of cooling<br />

before reprocessing; [NEA, 2002] assumes<br />

2 years of cooling, including reprocessing;<br />

[de Roo and Parsons, 2009] assumes<br />

5 years of cooling before reprocessing.<br />

2. [Bunn et al., 2003] also assumes 1 year of<br />

reprocessing and 0.5 year of fuel fabrication<br />

+ 0.5 year of storage of the fresh fuel;<br />

[NEA, 2009] assumes only 0.5 year of reprocessing<br />

and 0.5 year of fuel fabrication;<br />

[NEA, 2002] assumes 2 years of storage of<br />

the fresh fuel (including fabrication); [de<br />

Roo and Parsons, 2009] assumes 1 year of<br />

reprocessing, 0.5 year of fuel fabrication +<br />

0.5 year of shipping and storage.<br />

FR Metal <strong>Fuel</strong> Compositions for Various Conversion Ratios (equilibrium <strong>cycle</strong>)<br />

CompoSitionS in %W <strong>oF</strong> the initial heavy metal load<br />

FaSt reaCtor breeder<br />

FaSt burner reaCtor<br />

conversion ratio 1.23 0.0 0.5 0.75 1.0<br />

load<br />

aFter<br />

diSCharGe load<br />

aFter<br />

CoolinG load<br />

aFter<br />

CoolinG load<br />

aFter<br />

CoolinG load<br />

aFter<br />

CoolinG<br />

Tru 8.90 10.38 98.59 67.13 33.32 27.07 21.21 19.20 13.86 14.04<br />

u 91.10 84.03 1.41 1.44 66.68 58.88 78.79 70.12 86.14 78.30<br />

FP 0 5.60 0 31.43 0 14.05 0 10.68 0 7.66<br />

Pu 8.67 10.15<br />

Ma 0.23 0.23<br />

sion ratio to 1.115, the installed capacity is only increased by a small amount, less than 5%.<br />

Recalling that the total <strong>nuclear</strong> capacity in 2100 will be about 860 GWe, the share of fast<br />

reactors is about 56% with the improved fuel requirements.<br />

Startup of Fast Reactors with Enriched Uranium<br />

One option to avoid the coupling of fast reactor startup with reprocessing of LWR spent<br />

fuel is to start fast reactors with a core of enriched uranium rather than TRU. As can be<br />

seen in the preceding results of the <strong>nuclear</strong> fuel <strong>cycle</strong>, the availability of TRU from LWRs<br />

for the initial fast reactor core places an upper limit on the deployment rate of fast reactors.<br />

Alternatively, starting fast reactors with enriched uranium, and multi-recycling of the resulting<br />

TRU, may allow building a larger number of fast reactors, which in turn would save<br />

uranium resources. If only fast reactor TRU was re<strong>cycle</strong>d, this strategy would obviate the<br />

need for facilities to re<strong>cycle</strong> LWR TRU.<br />

Many experimental fast reactors were started using medium- and high-enriched uranium,<br />

higher than the current limit on commercial reactor enrichment of 20% U-235— the<br />

standard dividing enrichment level distinguishing LEU and HEU (weapons useable). Historically<br />

it has been assumed that medium-enriched uranium or plutonium was required<br />

to start a fast reactor. Core simulations at <strong>MIT</strong> show suitable performance for a sodium-<br />

chapter 6: analysis of <strong>Fuel</strong> <strong>cycle</strong> options 93

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