OSIRIS J12-5

Overview

This test is of a segmented PWR rod base-irradiated in the Electricity of France (EDF) Gravline 5 PWR (IAEA, 2008-2012). The segment was then re-fabricated and ramp-tested in the French Alternative Energies and Atomic Energy Commission (CEA) OSIRIS reactor to investigate PCMI resistance. This experiment was chosen because it allows for an evaluation of several aspects of the code, including fully coupled thermo-mechanics, contact, and several nonlinear material models.

Test Description

Rod Design Specifications

The geometric input parameters for the OSIRIS J12 test are summarized in Table 1.

Table 1: OSIRIS J12 Test Rod Specifications

Fuel RodMeasurementUnit
Overall length0.5224m
Fuel stack height432.95m
Nominal plenum height89.44mm
Number of pellets per rod32
Fill gas compositionHe
Fill gas pressure2.6MPa
FuelMeasurementUnit
MaterialUO
Enrichment4.5
Density95.73
Outer diameter8.192mm
Pellet geometryDished
Grain diameter10m
Pellet Dishing (no chamfers)MeasurementUnit
Dish diameter6mm
Dish depth0.32mm
CladdingMeasurementUnit
MaterialZr-2
Outer diameter9.5mm
Inner diameter8.36mm
Wall thickness0.57mm

Operating Conditions and Irradiation History

The approximately 0.522 m segmented Zircaloy-4 clad rod was irradiated for 2 cycles in the EDF Gravline 5 PWR to a final discharge burn-up of 23.852 MWd/kgU. The average powers in the 2 cycles were approximately 16 and 23 kW/m. The rod segment designated J12-5, which was irradiated in the fifth span from the lower end of the assembly, was refabricated with new end plugs without altering either the fuel column or the internal fill gas. After a conditioning period of 762 minutes at 21 kW/m, the power was increased quickly (9 kW/m/min.) and held at 39.5 kW/m for 739 minutes. The axial profile was flat during base irradiation. The peaking factors during the bump test varied from approximately 0.75 at the ends of the segment to 1 at the center. The power history is presented in Figure 1, and the power ramp is shown in Figure 2. The initial fill-gas (Helium) pressure was 2.6 MPa, and the coolant pressure was 15.5 MPa. The external clad temperature was defined as a function of time and constant in space over the section of rod, the specified clad temperature in Figure 3 was used in this simulation. The clad temperature was about 585 K during base irradiation and about 615 K during the ramp. The fast neutron flux in the clad was supplied via input using experimental data supplied with the experiment. Operational input parameters are summarized in Table 2.

Table 2: Operational input parameters.

Base Irradiation
Coolant inlet temperatureC
Coolant pressureMPa15.5
Fast neutron fluxn/(ms) per (W/m)4.8
Power Ramp
Coolant inlet temperatureC
Coolant pressureMPa14.7
Fast neutron fluxn/(ms) per (W/m)4.8

Figure 1: OSIRIS J12 power history in the Gravlines 5 PWR.

Figure 2: OSIRIS J12 power ramp

Figure 3: OSIRIS J12 clad temperature

Model Description

Geometry and Mesh

Figure 4: OSIRIS J12-5 mesh with temperature contour.

The rod specifications in Table 1 were used as input for the geometry for this simulation. The J12-5 rod was modeled as a 2D-RZ axisymmetric discrete pellet mesh with quadratic elements. Each pellet consisted of 16 axial elements and 9 radial elements. The clad was meshed with 4 elements through the thickness. Figure 4 is a section of the mesh with a temperature contour.

Material and Behavioral Models

The following material and behavioral models were used for the fuel:

  • UO2Sifgrs: fission gas release model used with the gaseous swelling model UO2VolumetricSwellingEigenstrain

For the clad material, a constant thermal conductivity of 16 W/m-K was used and both thermal (primary and secondary) and irradiation creep were considered. The following material and thermal behavior models were used for the cladding:

Input files

The BISON input and all supporting files (power histories, axial power profile, fast neutron flux history, etc.) for this case are provided with the code distribution at bison/assessment/LWR/validation/OSIRIS_J12/analysis.

Results Comparison

Clad Diameter

A comparison of the predicted and measured rod outer diameter is shown in Figure 5. The solid blue line is the as-manufactured rod diameter, prior to irradiation. The experimental data, shown as "+" (post-ramp) and "x" (pre-ramp) symbols, indicate the measured average rod diameter at both the end and middle fuel pellet locations, giving an indication of rod ridging due to pellet hour-glassing. The green solid line is the predicted rod diameter following the power bump and the red solid line is the predicted rod diameter prior to the ramp.

Figure 5: OSIRIS J12 experimental measurements and BISON calculation results from before and after the power ramp.

BISON under predicts clad creep down resulting in a larger than measured diameter. The overall shape of the rod after the ramp is captured well with BISON, as well as the clad ridging caused by the hour glassing (bamboo effect) of the discrete pellets.

References

  1. IAEA. Improvement of Computer Codes Used for Fuel Behaviour Simulation (FUMEX-III): Report of a Coordinated Research Project 2008-2012. Technical Report IAEA-TECDOC-1697, International Atomic Energy Agency, 2008-2012.[BibTeX]