USNRC (U.S. Nuclear Regulatory Commission). 1976. Final Generic Environmental Statement on the Use of Recycled Plutonium in Mixed Oxide Fuel in Light-Water Cooled Reactors (GESMO). NUREG-0002. Washington, DC.

USNRC, 1987. Case Histories of West Valley Spent Fuel Shipments. NUREG/CR-4847. January. Washington, D.C,


Walker, J.S. 2004. Three Mile Island: A Nuclear Crisis in Historical Perspective. University of California Press. Berkeley, California.

TABLE D.1 Range of Dimensions and Weights for Light Water Reactor Fuel Assemblies Used in Operating Reactors in the United States.

Physical Characteristics of Typical LWR Fuel Assemblies

Reactor Type

BWR

BWR

PWR

PWR

PWR

PWR

PWR

PWR

PWR

PWR

PWR

PWR

Fuel Designer

GE

GE

B&W

B&W

GE

GE

W

W

W

W

W

W

Fuel Rod Array

7×7

8×8

15×15

17×17

14×14

16×16

14×14

14×14

15×15

15×15

17×l7

17×l7

Artive Fuel Leugth (in.)

144

144

144

143

137

150

120

144

121

144

144

168

Nominal Envelope (in.)

5.438

5.47

8.536

8.536

8.25

8.25

7.763

7.763

8.449

8.426

8.426

8.426

Fuel Assembly Length (in.)

176

176

166

166

157

177

137

161

137

160

160

Weight (lba.)

600

600

1.516

1.502

581 kg

501 kg

573 kg

594 kg

654 kg

665 kg

Fuel Rod

Number

49

63

208

264

164

224.236

180

179

204

204

264

264

Length (in.)

163

153

147

161

127

152

127

152

152

Pitch. Square (in.)

0.798

0.640

0.568

0.501

0.580

0.506

0.556

0.556

0.563

0.563

0.496

0.496

O.D. (in.)

0.570

0.493

0.430

0.379

0.440

0.382

0.422

0.422

0.422

0.422

0.374

0.360

Clad Thickness (mils.)

35.5

34

26.5

23.5

26

25

16.5

24.3

16.5

24.3

22.5

22.5

Clad Material

Zr 2

Zr 2

Zr 4

Zr 4

Zr 4

Zr 4

sst

Zr 4

sst

Zr 4

Zr 4

Zr 4

Pellet O.D. (in.)

0.488

0.416

0.370

0.3232

0.3795

0.325

0.3835

0.3659

0.3835

0.3659

0.3225

0.3088

Peilet Length (in.)

0.375

0.650

0.390

0.600

0.600

0.600

0.600

0.530

0.530

Gap, Radial (poits)

5.5

4.5

3.5

3.1

4.3

3.5

2.8

3.8

2.8

3.8

3.3

3.3

Density (STD)

92.5–95.0

93.5–95.0

93.0–95.0

94.75

93.0–94.0

92.0

93.0–94.0

92.0

95.0

95.0

Poison

Gd1O2

Gd1O2

None

None

B1C/A12O2

B1C/A12O2

Nonfueled Rods

Number

0

1

17

25

6

6

16

17

21

21

25

25

Material

Zr 2

Zr 4

Zr 4

Zr 4

Zr 4

304 sst

Zr 4

304 sst

Zr 4

Zr 4

Zr 4

Spacer Grids

Number

7

7

8

8

8

12

Material

Inconel x

Inconel X

Inconel 718

Inconel 718

Zr 4

Zr 4

 

SOURCE: American Nuclear Society (1988).



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