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NEA-1622 IFPE/OSIRIS R3.

IFPE/OSIRIS R3, 4 PWR Rods Irradiated in the CEA Osiris Reactor

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1. NAME EXPERIMENT:  IFPE/OSIRIS.
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2. COMPUTERS
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Program name Package id Status Status date
IFPE/OSIRIS R3 NEA-1622/04 Arrived 20-JAN-2006

Machines used:

Package ID Orig. computer Test computer
NEA-1622/04 Many Computers
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3. DESCRIPTION OF PROGRAM OR FUNCTION

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.
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4. METHODS
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM
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6. TYPICAL RUNNING TIME
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7. UNUSUAL FEATURES
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8. RELATED OR AUXILIARY PROGRAMS
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9. STATUS
Package ID Status date Status
NEA-1622/04 20-JAN-2006 Arrived at NEADB
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10. REFERENCES
NEA-1622/04, included references:
- Rapport d'Assurance Qualite Crayon FF06E2BV/G07/1067 (22 Oct. 98)
- Rapport d'Assurance Qualite Crayon FF0EFELX/H09/5007 (22 Oct. 98)
- M. Menard:
Examens metallographiques du crayon FABRICE J12-5
Rapport DMT No.96/588 (Nov. 96)
- Rapport d'Assurance Qualite Crayon FF0LCMJV/J12/5105
- L. Marchand, J.P. Monin, D. Sapin:
Examens non destructifs crayon J12-5
Spectrometrie gamma - avant et apres reirradiation
Courants de Foucault - avant et apres reirradiation
Note E 96-1321 (22 octobre 1996)
- G. Bayon, D. Le Foll:
Examens non destructifs crayon J12-5
Neutronographie - Avant et apres reirradiation
Note E 96-1301 (25 mars 1996)
- D. Gouaillardou:
Dossiers 1 et 2 - FA 71BG
Rampe sur crayon J12.5, 2 cycles a OSIRIS
Rapport DMT No. 95-591 (Novembre 1995)
- P. Couffin:
Compte Rendu d'Irradiation Crayon J12-5 Cycle F 128
(CRi No.525, 18 mars 1996)
- END et Percage du Crayon J12-5 apres rampe
Note de Resultats LECM 96-055 (3 juin 1996)
- Ph. Aquilina et M. Vouillot:
Compte-Rendu de refabrication du crayon FABRICE X1 2-3
Rappport DMT 92/314 (23 juin 1992)
- Rapport d'Assurance Qualite Crayon FF06E2BV/K11/1090 (12 Nov. 98)
- G. Bayon, D. Le Foll:
Examens non destructifs Crayon K11-5
Neutronographie - avant et apres irradiation
Note E 95-1280 (21 juin 1995)
- P. Couffin:
Compte Rendu d'Irradiation Crayon K11-5 Cycle F 122
(CRi No.517, 3 juillet 1995)
- L. Marchand, J.P. Monin, D. Sapin:
Examens non destructifs crayon K11-5
Spectrometrie gamma - avant et apres reirradiation
Courants de Foucault - avant et apres reirradiation
Note E 95-1287 (7 decembre 1995)
- O. Rabouille, L. Belin:
Expertise au MEB du crayon K11-5 apres rampe de puissance
dans le reacteur OSIRIS
Rapport DMT 96/158 (Jan. 96)
- M. Vouillot:
Compte rendu de refabrication du crayon FABRICE K11-5 (GRAV III-1090)
Rapport DMT 94/240 (mai 94)
- D. Gouaillardou:
Dossier 1 - F.A.71BK Rampes de demonstration
Rapport DMT No. 93 - 554 (novembre 93)
- G.M. Decroix, P. Duigou, O. Rabouille, M. Menard, L. Belin:
Results from the examinations performed after power ramp testing on
the K11-5 fuel rod
DMT Report 96/147 (October 98)
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11. HARDWARE REQUIREMENTS
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12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
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13. SOFTWARE REQUIREMENTS
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS
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15. ESTABLISHMENT OF AUTHORS

CEA - Dept. des Reacteurs Nucleaires
91191 Gif-sur-Yvette Cedex
FRANCE

FRAMATOME
10 rue Juliette Recamier
69456 LYON Cedex 06
FRANCE

E.D.F. - SEPTEN
12-14, avenue Dutrievoz
F-69628 Villeurbanne Cedex
FRANCE

Data compiled by: J.A. Turnbull
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16. MATERIAL AVAILABLE
NEA-1622/04
SUMMARY.txt Description of the experiments
QA Report for EDF irradiations.doc QA Report
QA Report.pdf
CEA-G07.txt pre-characterization and PIE
G07-cs.dat Axial distribution of caesium
G07-dia.dat Axial distribution of rod diameter including oxide
G07-epm.dat Radial distribution as measured by EPMA of Nd, Pu & Xe
G07-his.dat Irradiation histories for rod PWR irradiation
G07-ox.dat Axial distribution of oxide thickness
CEA-H09.txt pre-characterization and PIE
H09-cs.dat Radial distribution of Cs as measured by EPMA
H09-dia.dat Axial distribution of rod diameter including oxide
H09-his.dat Irradiation histories for rod PWR irradiation
H09-nd.dat Radial distribution of Nd as measured by EPMA
H09-ox.dat Axial distribution of oxide thickness
H09-pu.dat Radial distribution of Pu as measured by EPMA
H09-xe.dat Radial distribution of Xe as measured by EPMA
CEA-J12.txt pre-characterization and PIE
J12-his.dat Irradiation histories for rod PWR irradiation
CEA-K11.txt pre-characterization and PIE
K11-cs.dat Axial distrib. of caesium along whole rod after base irradiation
K11-dia.dat Axial distrib. of whole rod diameter after base irradiation
K11-his.dat Irradiation histories for rod PWR irradiation
K11-ox.dat Axial distribution of oxide thickness
J12-5-d.dat Mean diameter measurements before & after OSIRIS ramp
J12-5-H.DAT Irradiation histories of re-fabricated sections
K11-5-d.dat Mean diameter before & after OSIRIS ramp
K11-5-H.DAT Irradiation histories of re-fabricated sections
Review of CEA-Osiris Experiments (Word and PDF Format)
README.txt Readme file
Documentation in PDF format
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17. CATEGORIES
  • Y. Integral Experiments Data, Databases, Benchmarks

Keywords: cladding, experimental data, fission gas release, fuel elements, fuel pellets, fuel rods, irradiation, pressurized water reactor.