Post Irradiation Examination for the Spent Fuel Samples

Fukushima-Daini-2

Outline of Reactor and Post Irradiation Examination

Fukushima-Daini-2 is BWR operated by Tokyo Electric Power Company in Japan. The PIE was conducted under the auspices of Science and Technology Agency of Japan. From the fuel assemblies, 2F2DN23, 18 samples were taken and isotopic composition was measured for irradiated UO2 and UO2-Gd2O3 fuel.

Main parameters of reactor

 

Reactor Name Fukushima Daini-2
Type of Reactor
BWR
Power
3293 MWth
Initial U235 Enrichment (%)
1.89/2.72/3.18/3.22/3.63
Operation
1989-1992
Fuel Pin Fuel Pellet Diameter (mm)
10.3
Length of Pellet Stack in Fuel Rods (mm)
3710
Clad Thickness (mm)
0.86 (Zr lining 1mm)
Clad Material
Zry-2
Fuel Assembly Rod Array
8 *8
Number of Rods
62
Fuel Rod Pitch (mm)
16.3
Control Rod Absorbing Material
-
Core Equivalent Diameter (mm)
4750
Active Height (mm)
3710
Number of Assembly
-
Inlet Temp (deg.)
-
Outlet Temp (deg.)
-

 

Number of Loop 2
Total Flow Rate of Coolant 48.3 x 10^3 t/h
Sub-cooling at Inlet of Core 11.4 kcal/kg
Average Steam Weight Ratio at Outlet of Core 13.2 wt%
Dome Pressure in Reactor Pressure Vessel 70.0 kg/cm2g
CORE
Active Height 3710 mm
Core Diameter 4750 mm
Uranium weight 133 t
Steam Pressure 70.7 kg/cm2g
Steam Temp. 286 deg.
PELLET
Enrichment 3.0wt% 235U
Diameter 10.3 mm
Height 10 mm
Density 95 %T.D.
Gd Enrichment less than 6 wt%
CLAD
Material Zry-2 (Zr-lining)
Outer Diameter 12.3 mm
Thickness 0.86mm (Zr-lining 1.0mm)
Pellet-Clad Clearance 0.24 mm
Plenum
Plenum Volume Ratio 0.1
Fuel Rod
He Pressure 3 a
Stack Length 3710 mm
Outer Diameter of Water Rod 15.0 mm
Fuel Assembly
Total Length
(including Handling Mech.)		 4470 mm

 

Axial U-235 Distribution for B-2 and C-2 rod

 

Initial Uranium Composition

 
Initial Composition [wt%]
U-234
U-235
U-238
SF98
0.04
3.91
96.05
SF99
0.03
3.41
96.56

 

Operation History

 

Start Stop Days Status
1989/ 1/14 1989/ 6/ 4 141 Burnup
1989/ 6/ 4 1989/ 6/25 21 Cool
1989/ 6/25 1990/ 3/ 9 257 Burnup
1990/ 3/ 9 1990/ 7/ 4 117 Cool
1990/ 7/ 4 1991/ 5/22 322 Burnup
1991/ 5/22 1991/ 5/31 9 Cool
1991/ 5/31 1991/ 8/25 86 Burnup
1991/ 8/25 1991/11/14 81 Cool
1991/11/14 1992/11/16 368 Burnup

 

Spent Fuel Composition Data

 

Sample ID
Sample Name
 Type U-235
Enrichment[wt%]
Burn up (GWd/t)
Sampling Position
Assembly
Pin
UO2
3.91
4.15
2F2DN23
UO2
3.91
26.51
UO2
3.91
36.94
UO2
3.91
42.35
UO2
3.91
43.99
UO2
3.91
39.92
UO2
3.91
39.41
UO2
3.91
27.18
UO2-Gd2O3
3.41
7.53
UO2-Gd2O3
3.41
22.63
UO2-Gd2O3
3.41
32.44
UO2-Gd2O3
3.41
35.42
UO2-Gd2O3
3.41
37.41
UO2-Gd2O3
3.41
32.36
UO2-Gd2O3
3.41
32.13
UO2-Gd2O3
3.41
21.83
UO2-Gd2O3
3.41
16.65
UO2-Gd2O3
3.41
7.15

 

Remarks

 

Core Configuration and Assembly Shuffling Information

Not opened in reference.

 

Sampling Position and Location of Different Type Fuel Rods in Bundles 2F2DN23

This figure shows the outline of 2F2DN23 fuel assembly, irradiated in Fukushima-Daini-2 reactor. When you click positions of fuel rods, axial positions of samples taken from the rods are shown.

 

 

References

  1. (Eds.) Y.Nakahara, K.Suyama and T.Suzaki, "Technical Development on Burn-up Credit for Spent Fuels," JAERI-Tech 2000-071, Japan Atomic Energy Research Institute, October 2000(in Japanese).

  2. (Eds.) Y.Nakahara, K.Suyama and T.Suzaki, "Technical Development on Burn-up Credit for Spent Fuels[English Translation]," JAERI-Tech 2000-071(ORNL/TR-2001/01),Oak Ridge National Laboratory(January 2002). (This report is English translation of reference 1).

  3. Yoshinori Nakahara, Kenya Suyama, Jun Inagawa, Ryuji Nagaishi, Setsumi Kurosawa, Nobuaki Kohno, Mamoru Onuki, and Hiroki Mochizuki, "Nuclide Composition Benchmark Data for Verifying Burn-up Codes on Light Water Reactor Fuels," Nuclear Technology,137(2),pp.111-126(February 2002).

 

B-2 C-2