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| Program name | Package id | Status | Status date |
|---|---|---|---|
| IFPE/OSIRIS | NEA-1622/04 | Arrived | 20-JAN-2006 |
Machines used:
| Package ID | Orig. computer | Test computer |
|---|---|---|
| NEA-1622/04 | Many Computers |
This data set contains details of 4 PWR rods irradiated in EDF commercial reactors. Two of the rods were re-fabricated and ramp tested in the CEA OSIRIS reactor to investigate their PCI resistance. The data set contains details of the pre-characterization of the fuel pellets, the cladding tube and the assembled fuel rod. The following is an outline of each fuel rod and the data available.
Rod G07:
This is rod FF06E2BV/G07/1067 irradiated for 3 cycles in the EDF Gravline 3 PWR to a final discharge burn-up of 34.783 MWd/kgU. The average powers in the 3 cycles were approximately 17, 24 and 21 kW/m. The final fission gas release was measured as 0.49 %. Data available from this rod include:
Axial caesium distribution measured by gamma scanning.
Length changes measured by neutron radiography.
Axial diameter (including oxide) and oxide thickness.
Fission gas release including isotopic composition of released Kr and Xe.
Whole pellet density measurements at 2 locations.
Hydrogen content of the cladding at 3 locations.
Local whole pellet burn-up from the neodymium concentration at 2 locations.
Radial distribution of Nd, Pu and Xe measured by EPMA at one location.
Metallography at one location.
Rod H09:
This is rod FF0EFELX/H09/5007 irradiated for 4 cycles in the EDF Cruas 2 PWR to a final discharge burn-up of 46.060 MWd/kgU. The average powers in the 4 cycles were approximately 22, 20, 18 and 15 kW/m. The final fission gas release was measured as 0.8 %. Data available from this rod include:
Length changes measured by neutron radiography.
Axial diameter (excluding oxide thickness) and oxide thickness.
Fission gas release.
Whole pellet density measurements at 11 locations.
Hydrogen content of the cladding at 4 locations.
Radial distribution of Cs, Nd, Pu and Xe measured by EPMA at 2 locations.
Metallography at 2 locations.
Rod J12:
This is rod FF0LCMJV/J12/5105 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.
A section of this rod was cut from span 5 between grids and ramp tested as J12-5 in the CEA OSIRIS reactor. After conditioning at 21 kW/m it was quickly ramped and held at 39.5 kW/m and discharged without failure. The final fission gas release after ramping was measured as 0.74 %. Data available from this rod include:
Fission gas release including isotopic composition of released Kr and Xe.
Metallography at 2 locations.
Rod K11:
This is rod FF06E2BV/K11/1090 irradiated for 2 cycles in the EDF Gravline 3 PWR to a final discharge burn-up of 25.437 MWd/kgU. The average powers in the 2 cycles were approximately 21 and 23 kW/m. The final fission gas release was measured as 0.2 %. Data available from this rod include: Axial caesium distribution measured by gamma scanning.
Length changes measured by neutron radiography.
Axial diameter (including oxide) and oxide thickness.
Fission gas release including isotopic composition of released Kr and Xe.
Hydrogen content of the cladding at 6 locations.
Local whole pellet burn-up from the neodymium concentration at 2 locations.
Radial distribution of Nd, Pu and Xe measured by EPMA at 3 locations.
Metallography at one location.
A section of this rod was cut from span 5 between grids and ramp tested as K11-5 in the CEA OSIRIS reactor. After conditioning at 24 kW/m it was quickly ramped and held at 43.7 kW/m and discharged without failure. The final fission gas release after ramping was measured as 6.3 %. Data available from this rod include:
Diameter measurements along the length of K11-5 before and after ramp.
Fission gas release including isotopic composition of released Kr and Xe.
Metallography at 4 locations showing evidence of dimple filling.
Keywords: cladding, experimental data, fission gas release, fuel elements, fuel pellets, fuel rods, irradiation, pressurized water reactor.
