FUEL-CYCLE COSTS

2.3 Procedure for Calculating Fuel-Cycle Costs

To calculate fuel-cycle costs, it is necessary to focus attention on individual fuel sublots and determine:

1. The amount and composition of each sublot when charged to the reactor

2. The amount of electricity generated by each sublot in each period in which electricity is paid for

3. The amount and composition of each sublot when discharged from the reactor

4. The cost incurred in each step for preparing fuel before it is charged to the reactor

5. The cost or credit incurred in each step for recovering fuel after it is discharged from the reactor

6. The time at which each cost is paid or each credit is received, and the time at which revenue is received for each increment of electricity generated by each lot of fuel

A somewhat simplified, approximate procedure for calculating fuel-cycle costs will be illustrated by the example of sublot 2A of the PWR whose fuel management was described in

Center­

line

|AB C d E F G H

6FG

8AH

7GB

8FG

8FF

7AH

7BG

9AH

27815

10500

22820

8023

12011

20926

23442

0

35977

20927

31825

18967

22722

29455

32594

10506

0.72

0,94

0.81

1.03

1.03

0.82

0.93

1.12

8HA

8BG

8CH

7DH

8DH

7EG

9BG

9BH

10500

12820

9879

19252

8086

21115

0

0

20926

23452

20532

28625

19246

30121

12827

10847

0.94

0.97

0.98

0.86

1.08

0.88

1.36

1.16

7GB

8HC

8GB

7FG

8EG

7CH

7DG

9CH

22820

9879

12818

18969

10517

20537

23395

0

31821

20527

22820

27841

21118

29352

32494

9884

0.81

0.98

0.91

0,81

1.02

0.86

0.92

1,03

8FG

7HD

7GF

7FF

8BH

8DG

9DG

9DH

8023

19240

19382

22713

10843

12829

0

0

18957

28597

28183

31175

21656

23409

12829

8086

1.02

0.86

0.80

0.79

1.07

1.07

1.37*

0.83

8FF

8HD

8GE

8HB

8GF

7BH

9EG

12011

8085

10516

10843

8023

21663

0

22715

19236

21099

21651

19382

31076

10514

1.03

1.08

1.02

1.07

1.15

0.95

1.10

7HA

7GE

7HC

8GD

7HB

9FF

9FG

20925

21094

20532

12828

21659

0

0

29453

30101

29344

23406

31072

12007

8021

0.82

0.88

0.86

1.07

0.95

1.25

0.82

78G

9GB

7GD

9GD

9GE

9GF

23442

0

23393

0

0

0

32594

12827

32492

12829

10514

8021

0.93

1.36

0.92

1.37*

1.10

0.82

9HA

9HB

9ИС

9HD

0

0

0

o

10506

10847

9884

8086

• = Maximum Relative Power

1.12

1.16

1.03

0.83

Fuel Lots 6,7, 8, 9 Initially 3.20 w/o U-235

Key

Cycle Average Burnup * 10,081 MWd/MT Cycle Thermal Energy = 896.8 GWd

Assembly Number BOC Burnup, MWd/MT EOC Burnup, MWd/MT BOC Relative Power (Assent)!у /Average)

Center­

line

7FG

9AH

8GB

9FG

9FF

8AH

8BG

10AH

27841

10506

22820

8021

12007

20927

23452

0

35997

20929

31824

18967

22721

29456

32601

10505

0.72

0.94

0.81

1.03

1.03

0.82

0.93

1.12

9HA

9BG

9CH

8DH

9DH

8EG

10BG

10BH

10506

12827

9884

19247

8086

21118

0

0

20928

23454

20535

28621

19249

30125

12826

10847

0.94

0.97

0.98

0.86

1.08

0.88

1.36

1.16

8GB

9HC

9GB

8FG

9 EG

8CH

8DG

10CH

22820

9884

12827

18968

10514

20532

23409

0

31820

20530

22827

27840

21117

29348

32506

9883

0.81

0.98

0.91

0.81

1.02

0.86

0.92

1.03

9FG

8HD

8GF

8FF

98H

90G

10DG

100H

8021

19236

19382

22722

10847

12829

0

0

18956

28594

28183

31183

21660

23410

12830

8086

1.02

0.86

0.80

0.79

1.07

1.07

1.37*

0.83

9FF

9HD

9GE

9HB

9GF

8BH

10EG

12007

8086

10514

10847

8021

21656

0

22714

19238

21098

21656

19382

31071

10516

1.03

1.08

1.02

1.07

1.15

0.95

1.10

8HA

8GE

8HC

9GD

8HB

10FF

10FG

20926

21099

20527

12829

21651

0

0

29454

30105

29340

23408

31067

12010

8022

0.82

0.88

0.86

1.07

0.95

1.25

0.82

8BG

10GB

8GD

10GD

10GE

10GF

23452

0

23407

0

0

0

32601

12825

32504

12829

10516

8022

0.93

1.36

0.92

1.37*

1.10

0.82

ЮНА

10HB

10HC

10HD

0

0

0

0

10505

10847

9883

8086

= Maximum Relative Power

1.12

1.16

1.03

0.83

ABCOHFQH

Key

Fuel Lots 7, 8. 9. 10 Initially 3.20 w/o U-235

Assembly Number BOC Burnup, MWd/MT EOC Burnup, MWd/MT BOC Relative Power (Assembly/Average)

Figure 3.24 PWR, assembly power and burnup distribution, cycle 8.

Sec. 4. Information on material quantities and energy production from sublots 1A through 4B in cycles 1, 2, and 3, applicable to this example calculation, is given in Table 3.5.

The 63 assemblies of sublot 2A contain 28,171.8 kg of uranium enriched to 2.8 w/o aU. The average bumup experienced by this sublet is 16,448 MWd/MT in cycle 1 and 8700 MWd/MT in cycle 2, for a total bumup B2a of 25,148 MWd/MT. The total thermal energy produced by this sublot is

(25,148 MWd/MTX28.1718MTX24,000 kWh/MWd)= 17,003 X 106 kWh Calculations by computer code LEOPARD made by Rieck [Rl] predict that this fuel wnen

Table 3.3 Fuel-cycle performance of PWR in successive cycles

Cycle

number

Fuel lot number

w/o 233 U charged

Burnup, MWd/MT

Peak radial power ratio

Cycle

average

Fuel

discharged

Charged

Discharged

Max. value Position

1

1

1

2.25

15,535

16,943

1.24

EE

2*

2.8

3+

3.3

2

4

2*

3.2

9,652

25,115

1.34

DG

3

5

3*

3.2

9,894

32,076

1.36

DG

4

6

4*

3.2

10,284

30,306

1.34

DG

5

7

5*

3.2

10,038

30,401

1.38

DG

6

8

6*

3.2

10,084

30,419

1.37

DG

7

9

7*

3.2

10,081

30,399

1.37

DG

8

10

8*

3.2

10,081

30,400

1.37

DG

^Contains burnable poison.

* Sixty-three assemblies from this lot and one from previous lot.

exposed to burnup of 25,148 MWd/MT will contain 27,991 kg of uranium enriched to 0.920 w/o 235 U and 161.330 kg of the fissile isotopes of plutonium 239Pu and 241 Pu.

To obtain the durations of cycles 1 and 2, and from them the times at which payments are made, credits received, and revenue obtained from the sale of electricity, the total thermal energy per cycle Ht is required and is calculated from burnup increments in the next to the last row of the table. The duration of irradiation during the ith cycle, r,-‘ — /’■, in years is obtained from Hi in the last row of the table, using a rated thermal output of 3.250 GW.

Figure 3.25 is a schematic flow sheet for lot 2A fuel cycle. This shows the fuel-cycle steps to be considered and defines notation for the material and service quantities involved in each step, the total cost or credit associated with each step, and the timing of all transactions (dashed arrows).

Table 3.6 gives numerical values for material quantities, unit costs or credits, and total direct costs or credits involved in each fuel-cycle step and calculates the overall net direct cost for lot 2A as $26.4 million. A total of $27.8 million is paid out for UF6 and fabrication in transactions 1 and 2 before any revenue is received from the sale of electricity. Because of this delay in receiving revenue, the total fuel-cycle cost includes also charges for carrying the $27.8 million advanced several years before it is recovered through revenue from the sale of electricity. Similarly, there is a financing charge on the net credit of $1.4 million in steps 3 through 6, delayed until after revenue is received from the sale of electricity.

The assumptions going into the calculation of direct costs in Table 3.6 will be described first. Then the procedure for calculating financing charges will be described, and finally a value will be given for the complete fuel-cycle cost.

Direct costs. The unit costs used in the examples of this chapter are those anticipated in 1975 for the year 1980. Because of changes since 1975, readers are cautioned to regard these costs more as examples than as firm numbers.

The unit cost of enriched uranium in the form of UF6 depends on the 235 U content of the uranium, the price paid for the natural uranium from which the uranium was enriched, the cost of the separative work expended in enriching the uranium, and the composition of the tails stream containing depleted uranium leaving the uranium enrichment plant. The procedure for calculating the cost of enriched uranium is described in Chap. 12. The unit costs

Сц[6] = $848.66/kg U for uranium enriched to 2.8 w/o 235 U fed to fabrication and cV" = $152.83/kg U for uranium containing 0.920 w/o 235 U recovered from reprocessing are based on the following assumptions:

Price of natural uranium ore concentrates, $31.55ДЬ U308

Price of natural UF6, $89.11/kg U

Cost of separative work, $100/separative work unit

235 U content of enrichment plant tails, 0.3 w/o

Table 3.4 Zion reactor, cycle 8: Relative power and bumup

Assembly location

DA

DB

DC

DD

DE

DF

DC

DH

Number of

previous cycles

1

2

2

2

1

1

0

0

Axial position

Relative power at beginning

12 (top)

0.72

0.64

0.60

0.57

0.68

0.62

0.61

0.35

11

1.03

0.87

0.81

0.78

1.00

0.94

1.07

0.64

10

1.13

0.95

0.89

0.86

1.13

1.10

1.32

0.81

9

1.17

0.98

0.92

0.89

1.20

1.18

1.48

0.91

8

1.18

0.99

0.92

0.90

1.23

1.23

1.58

0.97

7 Mid-

1.17

0.98

0.92

0.90

1.24

1.26

1.64

1.01

6 plane

1.15

0.96

0.90

0.89

1.23

1.26

1.68

1.04

5

1.11

0.93

0.87

0.86

1.21

1.25

1.70*

1.04

4

1.07

0.89

0.83

0.82

1.16

1.21

1.67

1.02

3

1.00

0.83

0.78

0.77

1.09

1.13

1.57

0.96

2

0.91

0.76

0.70

0.69

0.97

0.99

1.32

0.79

1 (bottom)

0.64

0.56

0.52

0.51

0.68

0.66

0.77

0.44

Average

1.02

0.86

0.80

0.79

1.07

1.07

1.37*

0.83

Assembly location

AA

AB

AC

AD

AE

AF

AG

AH

Number of

previous cycles

4

2

3

2

2

3

3

1

Axial position

Bumup, MWd/MT, at end

of cycle

12

27,179

14,426

23,474

13,087

15,589

21,108

22,962

6,100

11

35,525

19,961

31,028

18,154

21,530

28,394

31,095

9,347

10

37,482

21,536

32,909

19,575

23,259

30,387

33,421

10,543

9

37,850

21,992

33,348

19,972

23,794

30,932

34,124

11,018

8

37,893

22,174

33,478

20,120

24,028

31,129

34,421

11,267

7

37,897

22,303

33,564

20,221

24,199

31,256

34,631

11,454

6

37,913

22,430

33,653

20,320

24,364

31,378

34,833

11,629

5

37,952

22,568

33,762

20,431

24,537

31,513

35,042

11,803

4

38,028

22,710

33,894

20,546

24,710

31,653

35,247

11,956

3

38,052*

22,740

33,952

20,566

24,760

31,661

35,281

11,957

2

37,078

21,905

33,049

19,808

23,889

30,614

34,090

11,236

1

29,045

16,317

25,703

14,715

17,904

23,379

25,999

7,671

Average

35,991*

20,922

31,818

18,959

22,714

29,450

32,595

10,498

^Maximum local value.

* Maximum assembly average.

Table 3.5 Example of material quantities and energy production by lot and cycle

Cycle i

——————— Fuel discharged

Fuel

sublot

number

к

Number

of

assemblies

Fuel charged

1

2

3

Average burnup per lot, MWd/MT,

Bk = 2/ ABik

Thermal energy per lot, GWh, Hk = 24 X 10’6

w/o 235 у

kg U,

w*

kg

fissile

Pu,

Pk

Average burnup increment of sublot к in cycle i, MWd/MT, ДBlk

w/o 235 и

kg U,

ui

1A

64

2.25

29,168.2

16,943

_

_

16,943

11,861

0.944

28,457.6

141.736

IB

1 (#1GC)

2.25

455.8

15,950

7,210

23,160

253.35

0.663

441.1

2.497

2A

63

2.8

28,171.8

16,448

8,700

25,148

17,003

0.920

27,199.1

161.330

2B

1 (#2FE)

2.8

447.2

14,934

8,721

8,040

31,695

340.17

0.653

428.2

2.719

ЗА

63

3.3

27,499.5

13,280

10,132

8,671

32,083

21,175

0.921

26,320.8

171.258

3B

1 (#3HD)

3.3

436.5

10,194

8,553

8,601

t

t

t

t

t

4A

63

3.2

29,039.1

10,242

10,743

t

t

t

t

t

4B

1 (#4FG)

3.2

460.9

6,828

11,051

t

І

*

t

t

Thermal energy per cycle, GWh

Я/ = 24 X 10~6 Ujf ABjic 32,188 20,044 §

Duration of irrad.,yr 8766XJ250X a9 1-2553 0.7817 8 1

Receive Revenue from Sole of Electricity

Zu-

ZFa"

ZSh =

Zr =

о

C

X

cShU

CRU’

CpPf’

c0.Uf’f"

Times — ty.

lFa

t Ґ

t2 t2t2

lSh

Ir

V=tp

Figure 3.25 Schematic flow sheet for lot 2A fuel cycle, showing material and service quantities and timing of transactions.

It is assumed that /’ = 0.99 fraction of uranium charged in the form of UF6 will be recovered as fabricated fuel. Hence, to provide U’= 28,171.8 kg of fabricated uranium, 28,171.8/0.99 = 28,456.364 kg uranium in the form of UF6 must be purchased. The direct cost of this UF6 is 28,456.364 X 848.66 = $24,149,778.

A similar procedure is used to calculate the other components of the direct cost shown in Table 3.6. Other assumptions are as follows:

Fraction of uranium and plutonium recovered in reprocessing, f" = 0.99.

Fraction of recovered uranium converted to UF6,/’" = 0.995.

The fabrication unit cost of $130/kg includes cost of converting UF6 to U02 and packaging U02 in fuel assemblies.

The shipping cost of $30/kg includes storage charges at the reactor for around 150 days to permit fuel radioactivity to decrease.

The reprocessing and conversion cost of $180/kg includes charges by the government for perpetual storage of radioactive wastes.

Financing charges. A company generating electricity that pays out Z dollars for fuel-cycle costs t years before it receives revenue from generation of electricity from that fuel must pay to the bondholders and stockholders who advanced the funds for the fuel the return they require on their investment, and must also pay income taxes to the government on the profits from which the stockholders’ return is obtained. It is possible to represent all of these financing charges as the product yZt, where у is known as the annual cost of money before income taxes. For a privately owned U. S. electric company, a value of у = 0.151 per year is representative.

To find the total fuel financing charge, it is necessary to find the amount of money advanced for fuel as a function of time. Figure 3.26 is a schematic plot of the amount of

Figure 3.26 Plot of dollars invested in fuel versus time.
money invested in fuel cycle as a function of time for an example like sublot 2A, in which revenue is assumed received from the sale of electricity at two times during irradiation, from sale of Ex kWh at time r, in cycle 1 and from sale of E2 kWh at time t2 in cycle 2. The generalization to a more realistic case, in which revenue is received at more times, should be clear.

At time fu’, Zxj’ dollars are invested in enriched uranium. This amount of money is invested for tFa — tV’ years, until tFm when ZFa more dollars are paid out to fabricate fuel. The financing cost of carrying the initial investment of Zy> dollars for tFa — ty’ years is the product of the cost of money before income taxes, y, and the area of region A, Zy(tFa — fu’)-

Between tFtt, when fabrication is paid for, and f1; when revenue is received from production of Ex kWh of electricity, the dollars invested in fuel is Zy’ + ZFm and financing costs are the product of у and area B, (Zu’ + ZFa)(tx ~ tFa).

If the total electricity production of the lot of fuel is I, mEm (Ex + E2 for sublot 2A) and the net direct fuel-cycle cost is Z/Z/=Z (where Zj is the direct cost of the /’th fuel-cycle step and ZjZj = $26,439,162 for sublot 2A), the amount of money invested in fuel after tx should be reduced by ZExl(Ex + E2 ). Between fj and t2, when the second (and in this case, the last) revenue is received from production of E2 kWh of electricity, the dollars invested in fuel is Zy + ZFa — ZExl(Ex + E2), and financing costs are the product of у and area C, [Zy< + ZFa-ZEi/(Ex +E2)} (t2-tx).

The amount of electricity generated by sublot 2A in cycle 1, Et, is obtained from the thermal efficiency of the power plant

77 = ilr = 032615 (ЗЛ4)

the average burnup increment of sublot 2A in cycle 1, AB12a = 16,448 MWd/MT from Table 3.5, and the mass of uranium, U2a =28,171.8 kg. Hence

Ex = 24n ABxzaU’ia = (24)(0.32615)(16,448)(28,171.8) = 3.6271 X 109 kWhe (3.15) Similarly, the amount of electricity generated by sublot 2A in cycle 2 is

E2 = (24)(0.32615) (8700)(28,171.8) = 1.9185 X 109 kWhe (3.16)

The total electric generation is

E = Ex +E2 = (3.6271 + 1.9185) X 109 = 5.5456 X 109 kWhe (3.17)

Between t2 and t$h when payment is made for shipping fuel, the dollars invested in fuel is the difference between the initial outlay Zy’ + ZFa and the direct fuel-cycle cost Z, which is equivalent to

Zy’+ ZFa — Z = Zy" + Z? — Zsh — ZR (3.18)

The financing cost for this time interval is the product of у and area D, (Zy" + ZP — Zr —ZSh)(tsh ~h)-

Between tgh and tR, when payment is made for reprocessing fuel and converting uranium to UF6, the dollars invested in fuel is Zy" + Zp — ZR. The financing cost for this time interval is the product of у and area E, (Zy" + ZP — ZR)(tR — tsh).

If credit for plutonium and uranium is received at a time ty“ later than tR, an additional financing charge is incurred on the value of this uranium and plutonium, Zy" + ZP, for the time interval ty" — tR, equal to the product of у and the area F, (Zy" + ZPX? u" — tR).

[*r

The sum of areas А, В, C, D, E, and F is

+ (Zu" + Zp — ZR —Zsh)(fsh + Zp ~ZR)(tR — tsf,)

+ (Zu — + Zp)(tV" — tR) = Zu — — tl)j

_l *7 (Eiti+E2t2 . ±T {Eiti +E2t2 „

Zf‘ VT^T* Fa) ^{еГ+е, tsh)

* — ‘*) — (z“-+z-> fihrir — —

Thus, the area under the curve is the sum of the product of each expenditure or credit times the difference between the mean time for receipt of revenue t

i= Eiti + E2t2

Ei +E2

and the time when the expenditure or credit is paid. This result generalizes to an expression for the area of

(3.21)

where Zj is the outlay for fuel-cycle step / (negative if a credit) at f;- and tm is the time at which revenue is received, for production of Em kWh of electricity. The fuel-cycle cost e in mills per kilowatt-hour then is

The assumptions of Table 3.7 are made to obtain the times needed to calculate the carrying-charge term for sublot 2A:

{EttT ~'<) й E’- <3-22>

A time basis of zero is taken for the start of cycle 1 (t = 0).

The mean time for receipt of revenue from sale of electricity, t, is

r= EiU +E2t2 _ (3.6271)(0.7920)+ (1.9185)(1.9355) _ , ,0„._

1- ~ЁГПГ~~————————— ШпТШБ 1 1876 yr (3-23)

From the foregoing transaction times and the direct fuel-cycle costs or credits of Table 3.6, the carrying charges and total fuel-cycle costs may be calculated, as shown in Table 3.8 for sublot 2A. Division of the total fuel-cycle cost of $33,173,168 by the electricity generated by sublot 2A, 5.5456 X 109 kWhe, and conversion to mills per kilowatt-hour of electricity by Eq.

(3.21) gives 5.9819 mills/kWhe for the unit fuel-cycle cost of lot 2A.

Table 3.8 shows that more than 20 percent of the fuel-cycle cost arises from carrying charges.