the economics of the nuclear fuel cycle...3/29/04 nuclear energy economics and policy analysis 20...
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The Economics of the NuclearFuel Cycle
March 29, 2004
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Enrichment Plant Material Balance
Tails: W, xw
Feed: F, xF
Product: P, xP
Material balance on U: F = P + W
Material balance on U-235: FxF = PxP + WxW
F = Pxp - xW
xF - xW
È
ÎÍ
˘
˚̇
and for xP= 0.03, xF=0.00711, xW= 0.002, F/P = 5.5
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Source: US Energy Information Agency (http://eia.doe.gov/cneaf/nuclear/page/nuc_reactors/pwr.html)
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Source: US Energy Information Agency (http://eia.doe.gov/cneaf/nuclear/page/nuc_reactors/pwr.html)
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PWR Batch Refueling Scheme(Batch fraction = 1/3)
Cycle No. Batch #
I 1 2 3 Startup core
II 2 3 4 (new)
III 3 4 5 (new)
IV 4 5 6 (new)
VDischarged
after 1 cycle
Bd~Bc*
Discharged
after 2
cycles
Bd~2 Bc*
Discharged
after 3
cycles
Bd~3 Bc*
*Useful approximation. In practice, need
to track Bd with computer codes
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If the batch fraction is 1/n, under steady state conditions each batch remains in the core for n cycles.
Similarly, at steady state the energy produced by all n batches in the core during one cycle is equal to the
energy produced by one batch during its total residence time in the core (i.e., n cycles.).
Thus the total electrical energy produced by a given batch during its in-core lifetime at steady state is:
Eb (kwh(e)/batch) = 8766 (hrs/yr) x CF x K (kwe) x Tc (yr)
where:
CF = cycle average capacity factor (including refueling downtime)
K = plant rating (kwe)
Tc = cycle length (yrs) including downtime
We can also write that the energy produced per batch is:
Eb (kwhr(e)/batch) = Bd (MWD(th)/MTHM) x 24 (hr/day) x 1000 (kw/MW) x h x P (MT)
where:
Bd = discharge burnup of the fuel (MWD(th)/MT of heavy metal)
h = thermodynamic efficiency (Mwe/MW(th))
P = batch fuel inventory (MT of heavy metal)
Also,
Tb = n Tc
Bd = n Bc
And P, the fuel inventory per batch = Total core inventory/n
Energy from a fuel batch
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Material balance on the front end of the cycle
Assume:K = 1000 MWeTc= 1.5 yearsCF = 90%h = 33%n = 3In-core fuel inventory = 89.4 MTHM
Hence we can calculate:• Energy output per batch, Eb, (at steady state)• Mass of fuel (as heavy metal), P, per batch• Discharge burnup of spent fuel, Bd (MWDth/MTHM)
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xp = 0.41201 + 0.11508•n + 1
2n•Bd
Ê
ËÁ
ˆ
¯˜ + 0.00023937•
n + 1
2n•Bd
Ê
ËÁ
ˆ
¯˜
2
Source: Zhiwen Xu, NED DoctoralDissertation, 2003
where n = number of batches
(valid for xp< 20%)
Approximate Correlation: Initial enrichment (xP) vs.discharge burnup (Bd)
Image removed due to copyright considerations.
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Material balance on the front end of the PWR fuel cycle
(Basis: 1 steady state batch; 1000 MWe PWR; thermal efficiency = 33%; 90% capacity factor; 18-month
refueling cycle; batch fraction = 1/3; discharge burnup = 50,000 MWD(th)/MT))
FABRICATION
CONVERSION
CONVERSION
MINE & MILL
1000 MWePWR
Cap. fact.= 90%Therm. eff.=33% Discharge burnup =
50,000 MWD/MTHM
29.8 MTHM of LEU
4.51% U-235
1% losses
29.8/0.99 = 30.1MTHM of U
30.1 x (270/238)
= 34.15 MT UO2
0.5% losses
UF6
34.15
.995¥
352
270= 44.74 MT UF
6
Product, P
XP=4.51%
Tails, WXW = 0.3%
458.3 - 44.74 =413.6 MT UF6
Feed, FXF=0.711%
F =4.51- 0.3
.711-0.3¥ 44.74
= 458.3 MT nat. UF6
0.5% losses
Yellowcake(U308)
458.3
.995¥
842
3
352= 367.3MT U
3O
8≡ 367.3¥
238
842
3
= 311.4MT U
Nat.UF6
Molecular Weights
U3O8 842UF6 352
UO2 270
U 238
Mill tailings
Uranium ore
Spent fuel