Post Irradiation Examination for the Spent Fuel Samples
Fukushima-Daiichi-3
Outline of Reactor and Post Irradiation Examination
Fukushima-Daiich-3 is BWR in Japan. Fuel Assembly is 8 by 8 type. From seven fuel assemblies, F3A1, F3A3, F3A5, F3A6, F3A7, F3A8, F3A9, 36 spent fuel samples were taken for the measurement of isotopic composition. The measurement was conducted in Japan Nuclear Fuel Development(NFD) under the auspices of Nuclear Power Engineering Corporation (NUPEC).Main parameters of reactor
| Reactor Name | Fukushima Daiichi-3 | |
|---|---|---|
| Type of Reactor |
BWR
|
|
| Power |
784 MWe
|
|
| Initial U235 Enrichment (%) |
1.45/1.87/2.22/3.01
|
|
| Operation |
1977-1982
|
|
| Fuel Pin | Fuel Pellet Diameter (mm) |
11
|
| Length of Pellet Stack in Fuel Rods (mm) |
3658
|
|
| Clad Thickness (mm) |
0.86
|
|
| Clad Material |
Zry-2
|
|
| Fuel Assembly | Rod Array |
8*8
|
| Number of Rods |
63
|
|
| Fuel Rod Pitch (mm) |
16.3
|
|
| Control Rod Absorbing Material |
-
|
|
| Core | Equivalent Diameter (mm) |
-
|
| Active Height (mm) |
-
|
|
| Number of Assembly |
548
|
|
| Inlet Temp (deg.) |
-
|
|
| Outlet Temp (deg.) |
-
|
|
Operation History
|
Assembly
|
Burn-up [MWd/t]
|
|||
|
1st Cycle
|
2nd Cycle
|
3rd Cycle
|
4th Cycle
|
|
|
F3A5
|
5800
|
-
|
-
|
-
|
|
F3A8
|
6100
|
-
|
-
|
-
|
|
F3A1
|
5400
|
14500
|
-
|
-
|
|
F3A6
|
5800
|
13800
|
-
|
-
|
|
F3A7
|
5600
|
14300
|
21300
|
-
|
|
F3A3
|
5500
|
14000
|
21100
|
28600
|
|
F3A9
|
5600
|
14300
|
20300
|
26100
|
|
F3A2
|
5700
|
13900
|
20300
|
27100
|
|
F3A4
|
5800
|
13300
|
19000
|
25900
|
|
F3A10
|
5600
|
15000
|
21000
|
28000
|
Spent Fuel Composition Data
|
Sample ID
|
Type |
U-235
Entichment[%] |
Burn up (GWd/t)
|
Sampling Position
|
|
|
Assembly
|
Pin
|
||||
| JPN1F3BWR-1 | UO2 |
1.45
|
19.20
|
||
| JPN1F3BWR-2 | UO2 |
1.45
|
15.74
|
||
| JPN1F3BWR-3 | UO2 |
3.01
|
14.69
|
||
| JPN1F3BWR-4 | UO2 |
3.01
|
15.94
|
||
| JPN1F3BWR-5 | UO2-Gd2O3 |
3.01
|
13.92
|
||
| JPN1F3BWR-6 | UO2-Gd2O3 |
3.01
|
14.59
|
||
| JPN1F3BWR-7 | UO2 |
1.45
|
29.47
|
||
| JPN1F3BWR-8 | UO2 |
1.45
|
33.60
|
||
| JPN1F3BWR-9 | UO2-Gd2O3 |
3.01
|
28.13
|
||
| JPN1F3BWR-10 | UO2-Gd2O3 |
3.01
|
27.46
|
||
| JPN1F3BWR-11 | UO2 |
1.87
|
27.46
|
||
| JPN1F3BWR-12 | UO2 |
1.87
|
26.50
|
||
| JPN1F3BWR-13 | UO2 |
1.45
|
7.92
|
||
| JPN1F3BWR-14 | UO2 |
1.45
|
6.15
|
||
| JPN1F3BWR-15 | UO2 |
3.01
|
7.44
|
||
| JPN1F3BWR-16 | UO2 |
3.01
|
5.85
|
||
| JPN1F3BWR-17 | UO2-Gd2O3 |
3.01
|
5.59
|
||
| JPN1F3BWR-18 | UO2-Gd2O3 |
3.01
|
4.24
|
||
| JPN1F3BWR-19 | UO2 |
1.45
|
17.57
|
||
| JPN1F3BWR-20 | UO2 |
1.45
|
18.14
|
||
| JPN1F3BWR-21 | UO2 |
1.45
|
24.38
|
||
| JPN1F3BWR-22 | UO2 |
1.45
|
25.82
|
||
| JPN1F3BWR-23 | UO2 |
3.01
|
21.89
|
||
| JPN1F3BWR-24 | UO2 |
3.01
|
18.53
|
||
| JPN1F3BWR-25 | UO2-Gd2O3 |
3.01
|
21.98
|
||
| JPN1F3BWR-26 | UO2-Gd2O3 |
3.01
|
20.35
|
||
| JPN1F3BWR-27 | UO2 |
1.45
|
6.86
|
||
| JPN1F3BWR-28 | UO2 |
1.45
|
5.25
|
||
| JPN1F3BWR-29 | UO2 |
3.01
|
7.19
|
||
| JPN1F3BWR-30 | UO2 |
3.01
|
5.04
|
||
| JPN1F3BWR-31 | UO2-Gd2O3 |
3.01
|
5.75
|
||
| JPN1F3BWR-32 | UO2-Gd2O3 |
3.01
|
4.14
|
||
| JPN1F3BWR-33 | UO2 |
3.01
|
30.91
|
||
| JPN1F3BWR-34 | UO2 |
3.01
|
32.45
|
||
| JPN1F3BWR-35 | UO2 |
1.87
|
31.49
|
||
| JPN1F3BWR-36 | UO2 |
1.87
|
31.30
|
||
Core Configuration and Assembly Shuffling Information
| No. | Assemblies | No. | Assemblies |
|---|---|---|---|
| 1 | F3A1 | 6 | F3A6 |
| 2 | F3A2 | 7 | F3A7 |
| 3 | F3A3 | 8 | F3A8 |
| 4 | F3A4 | 9 | F3A9 |
| 5 | F3A5 | 10 | F3A10 |
References
-
Kurosawa,M., Naito,Y., Sakamoto,H., and Kaneko,T., "The Isotopic Compositions Database System on Spent Fuels in Light Water Reactors(SFCOMPO)," JAERI-Data/Code 96-036, Japan Atomic Energy Research Institute (February 1997).
Last reviewed: 20 March 2012