Post Irradiation Examination for the Spent Fuel Samples

Outline of JPDR-I


Outline of Reactor and Post Irradiation Examination

JPDR-I is naturally circulated BWR at Japan Atomic Energy Research Institute. Fuel assembly is type of 6 by 6. Post irradiation examination was conducted for three fuel assembly, A-14, A-18, A-20. And isotopic composition of 30 samples are taken.

 

Main parameters of reactor

 

Reactor Name JPDR-I
Type of Reactor Naturally Circulated BWR
Power 45MWth
Initial U235 Enrichment (%) 2.6
Operation 1963-1969
Fuel Pin Pellet Material UO2 sintered pellet, solid
Fuel Pellet Diameter (mm) 12.5
Pellet Height(mm) 12.7
Pellet Density[c/cm^3] 10.4
Length of Pellet Stack in Fuel Rods (mm) 1466.7(721+-3/segment)
Clad Thickness (mm) 0.76
Clad Outer Diameber(mm) 14.12
Weight of UO2 in a Segment (g) 921+-25
Dy2O3 content in End Pellet(wt%) 0.42
Clad Material Zry-2
Fuel Assembly Rod Array 6*6
Number of Rods 36
Fuel Rod Pitch (mm) 19.56
Volume Ratio of Mederator to Fuel in Lattice 1.84
Channel Box Material Zry-4
Core Equivalent Diameter (mm) 1270
Active Height (mm) 1470
Number of Assembly 72
Inlet Temp (deg.) -
Core-Averaged Volume Ratio of Mederator to Fuel 2.7
Operating Pressure[kg/cm^2,G] 61.5
Temperature of Coolant[Deg] 277
Maximum Temperature of Fuel Center[Deg] 1610
Average Power Density[KW/l] 22.5
Radial Power Peaking Factor 1.4
Average Power Peaking Facor 1.5
Average Thermal Neutron Flux[n/cm^2* sec] 1.42*10^13
Maximum Heat Flux[kcal/m^2*ht] 823000
Average Heat Flux[kcal/cm^2*sec] 226100
Average Void Fraction 19
Core-exit Steam Quality[%] 4.7

 

Operation History

 

Spent Fuel Composition Data

 

Sample Name
Type U-235
Enrichment[%]
Burn up(GWd/t)*
Sampling Position
Assembly
Pin
JPNJP1BWR-1
UO2
2.6
4.13
JPNJP1BWR-2
UO2
2.6
5.54
JPNJP1BWR-3
UO2
2.6
3.38
JPNJP1BWR-4
UO2
2.6
2.94
JPNJP1BWR-5
UO2
2.6
4.35
JPNJP1BWR-6
UO2
2.6
2.77
JPNJP1BWR-7
UO2
2.6
6.85
JPNJP1BWR-8
UO2
2.6
7.17
JPNJP1BWR-9
UO2
2.6
6.29
JPNJP1BWR-10
UO2
2.6
6.45
JPNJP1BWR-11
UO2
2.6
6.66
JPNJP1BWR-12
UO2
2.6
7.11
JPNJP1BWR-13
UO2
2.6
5.35
JPNJP1BWR-14
UO2
2.6
5.76
JPNJP1BWR-15
UO2
2.6
2.21
JPNJP1BWR-16
UO2
2.6
3.95
JPNJP1BWR-17
UO2
2.6
5.17
JPNJP1BWR-18
UO2
2.6
5.88
JPNJP1BWR-19
UO2
2.6
6.18
JPNJP1BWR-20
UO2
2.6
6.22
JPNJP1BWR-21
UO2
2.6
5.98
JPNJP1BWR-22
UO2
2.6
5.20
JPNJP1BWR-23
UO2
2.6
4.16
JPNJP1BWR-24
UO2
2.6
2.71
JPNJP1BWR-25
UO2
2.6
5.04
JPNJP1BWR-26
UO2
2.6
5.99
JPNJP1BWR-27
UO2
2.6
5.50
JPNJP1BWR-28
UO2
2.6
5.73
JPNJP1BWR-29
UO2
2.6
5.44
JPNJP1BWR-30
UO2
2.6
6.66

*Nd-148 Method

 

 

Core Configuration

The following shows the outline of JPDR-I. When you click a assembly name, you can see the detail of assembly.

 

 

 

References

  1. H.Natsume et.al. Gamma-Ray Spectrometry and Chemical Analysis Data of JPDR-I Spent Fuel. J. Nucl. Sci. Technology, 14(10) pp.745-761, 1977.

  2. T.Suzaki et.al. Non-Destructive and Destructive Measurements on Burnup Characteristics of Japan Power Demonstration Reactor-I Full-Core Fuel Assemblies. J. Nucl. Sci. Technology, 23(1) pp.53-72, 1986.

  3. T.Suzaki et.al. Non-Destructive Gamma-Ray Spectrometry and Analysis on Spent Fuel Assemblies of the JPDR-I. JAERI 1296, 1985. A-14集合体詳細 A-18集合体詳細 A-20集合体詳細