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PHENIX: The irradiation programme for transmutation experiments J. Guidez Head of PHENIX reactor

PHENIX: The irradiation programme for transmutation experiments J. Guidez Head of PHENIX reactor. GENERAL DESIGN of the PLANT. PLANT DATA. First criticality: 31st August 1973 First connection to the grid: 13th December 1973 Commercial operation: 14th July 1974

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PHENIX: The irradiation programme for transmutation experiments J. Guidez Head of PHENIX reactor

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  1. PHENIX: The irradiation programme for transmutation experiments J. Guidez Head of PHENIX reactor

  2. GENERAL DESIGN of the PLANT

  3. PLANT DATA • First criticality: 31st August 1973 First connection to the grid: 13th December 1973 Commercial operation: 14th July 1974 • Nominal Power: 563 MWth (250 MWe) Since 1993 Power limited to 350 MWth (145 MWe), on two secondary loop operation. • Total number of Equivalent Full Power Days: 3990 Total operating hours: 106 000 h Gross electrical output: 23 123 400 MWh

  4. PLANT LIFETIME EXTENSION WORK • 6 years of work in two phases from 1994 to 1997 and 1999 to 2003, separated by one operating cycle. • 250 million € of studies and renovation works • 5000 contract entered into, 350 sub-contracting companies • 4500 agents working for the sub-contractors (up to 700 per day) [PHENIX staff : 210 CEA + 70 EDF]

  5. PLANT OPERATING DIAGRAM 2004 52 ème cycle 51th cycle 350 300 AM1 AT2 200 100 Janvier Février Mars Avril Mai Juin Juillet Août Sept Oct Nov Déc 2004 51th cycle: 210 Days at nominal power 131 EFPD Availability factor: 94% Load factor: 85% Power operation Operation schedule

  6. FUTURE OPERATION of the PLANT 6 cycles of 120 EFPD equivalent to about 5.5 years of operation 2004 2005 2006 1 2 3 4 5 6 7 8 9 10 11 12 1 2 3 4 5 6 7 8 9 10 11 12 1 2 3 4 5 6 7 8 9 10 11 12 52-1 53-1 53-2 54-1 52-2 51 - 2 2007 2008 2009 1 2 3 4 5 6 7 8 9 10 11 12 1 2 3 4 5 6 7 8 9 10 11 12 1 2 3 4 5 6 7 8 9 10 11 12 54-2 56-1 55-1 55-2 56-2 80% Load factor

  7. Fast flux (n/cm2.s) Thermal flux (n/cm2.s) Dose rate PWR power reactor 1.3.1014 0.9.1014 2 dpa/year OSIRIS, HFR, BR2 type research reactor … 2 to 4.1014 4 à 7.1014 3 dpa/year Phénix reactor 2.5.1015 4.4 . 10 15 18 dpa/ 6-month cycle Type 1 moderate flux* 3.6.1015 12 dpa/ cycle Type 2 moderate flux* 1.5.1015 3.7.1013 4 dpa/ 6-mont cy cle EXPERIMENTAL CONDITIONS AT PHENIX COMPARISON OF NEUTRON FLUX * Types 1 and 2 correspond to the type of moderating carrier used : 1: 11B4C , 2: CaHx

  8. EXPERIMENTAL CONDITIONS AT PHENIX TEMPERATURE Core inlet/outlet: 380/550°C Device developed for material irradiation up to 1000°C MEASUREMENTS Sodium inlet/outlet Temperature Sodium sampling at S/A outlet Argon gas blanket analysis

  9. EXPERIMENTAL CONDITIONS AT PHENIX EXPERIMENTAL RIG AND CARRIER

  10. PHENIX EXPERIMENTAL TRANSMUTATION PROGRAMME • General irradiation data acquisition • Neutronic data measurements • Fuel irradiation for homogeneous transmutation mode • Target irradiation for heterogeneous transmutation mode • Constituent materials (Inert matrices, moderators) • Irradiation of actinide-based compounds (primarily Americium) • Irradiation of targets containing long-lived fission products (Technetium 99) • Irradiation of high Pu content fuel • Fuel irradiation for future systems (dedicated critical or sub-critical transmutation systems, GFR...)

  11. PROFIL-R pins Spacers Profil-R pins Reference standard pin PROFIL-R SUB-ASSEMBLY Measurement of actinides and fission products cross sections in fast (PROFIL-R) and moderated (PROFIL-M) neutron flux Body Cask Isotope Height 10 mm PROFIL-R container Containers

  12. 7 1 U 1 9 P u 1 0 Z r . 6 7 U 1 9 P u 1 0 Z r 2 A . M . 2 T . R 6 6 U 1 9 P u 1 0 Z r 5 A . M . 6 1 U 1 9 P u 1 0 Z r 5 A . M . 5 T . R . HOMOGENEOUS TRANSMUTATION EXPERIMENT METAPHIX: Irradiation of Actinides diluted in metal fuel (UPuZr+MA+RE) Contract with ITU Karsrhue for CRIEPI Core center plane 3 capsules containing 3 pins each Standard pins Experimental pins 1 2 3 Capsule content

  13. INERT MATRIX TESTING • MATINA 1A: re-irradiation of MATINA 1 experiment dismantled in 1996 (first selection of most promising inert matrices for heterogeneous transmutation). • MATINA 2-3 (scheduled in 2005): Testing of: CERCER targets with a MgO matrix and micro-dispersed and macro-dispersed particles, new materials (pyrochlore Ce2Zr2O7 and yttriated zirconia ZrYO compounds)

  14. ECRIX EXPERIMENTS: OBJECTIVES First experiment of Am transmutation in specific target in a fast reactor Testing two concepts of « once trough » transmutation by using local moderation spectrum: • 11B4C : ECRIX-B • CaH2 : ECRIX-H • Fuel fabrication process (metallurgy powder) which can be applied to the industrial scale • Development of fabrication and characterisation techniques • Fabrication of 100 pellets • Property measurements* • Irradiation started at Phenix * Collaboration with ITU/Karlsruhe

  15. ECRIX B and H : Transmutation of Americium in MgO inert matrix, pins located inside special moderating carriers) ECRIX EXPERIMENTS: SUB-ASSEMBLY DESIGN ECRIX : moderator sub-assembly and capsule cross section

  16. DMC 2 MODERATOR CARRIER AND CAPSULE Capsule KMC Moderator CaHx thickness 9,5 mmheight 300 mm Steel cylinder DMC 2 Steel spacers

  17. TRANSMUTATION RATES IN PWR COMPARED TO PHENIX MODERATED FLUX

  18. Cladding UO2 pellets Fissile columnwith americiumtarget - pellets Black elements : porosities White elements : AmOx particle Grey area : magnesia UO2 pellets ECRIX EXPERIMENTS: PIN DESIGN Microstruture : CERCER Microdispersed type Inert matrix : MgO Fuel Particles: AmOx Am content : 0,7g of Am/cm3 Height density : 97%

  19. LLFP TRANSMUTATION: ANTICORP 1 • Capsule: 3 pins with two pieces of 99Tc metal • Moderator carrier • Transmutation rate target: 25%

  20. CAPRIX 1 EXPERIMENT Irradiation of high Pu content fuel To assess: • Thermal-mechanical behaviour of the pin • Radial Pu redistribution • Cladding Internal corrosion • Reprocessing • 2 pins: 45% Pu /(U+Pu) enrichment pellets with 17 driver fuel pins in a capsule • Target burn-up : 10 at%

  21. CORE LOCATION OF TRANSMUTATION EXPERIMENTS

  22. FUTURE EXPERIMENTS Optimisation of target for Americium transmutation • CAMIX (Composé d’AMéricium dans PhénIX) :optimisation of actinide compound COCHIX (Conception Optimisée vis-à-vis des miCrostructures dans pHénIX) :testing of new microstructures (macromasses) dispersed in inert matrix • MATINA 2-3 testing of CERamics/CERamics targets with a MgO matrix and macrodispersed particles and of new materials Fuel for future systems • FUTURIX/FTA (FUels for Transmutation of transURanien elements in PhénIX/Fortes Teneurs en Actinides testing of Metal, nitride, CER/MET, CER/CER fuels with high TRU content Collaboration with US/DOE, ITU, CRIEPI • three further experiments planned (fuel and materials for Gas-cooled FR)

  23. CONCLUSIONS • Successful re-start after a major safety upgrading of the PHENIX plant ( the unique fast breeder reactor in Europe ) (Availability factor 94% in 2004) • Transmutation experimental programme in progress for: • Americium , Technetium 99 ,inert matrix for heterogeneous transmutation(ECRIX, ANTICORP, MATINA) • Homogeneous transmutation (METAPHIX ) • High PU content fuel (CAPRIX) • Neutronic datas (PROFIL) which shall provide a validation of a wide range of concepts • Preparation of future experiments for the next cycles.

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