minor-actinides transmutation in an accelerator driven ... · 11-iempt, san francisco, nov. 1-5...
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11-IEMPT, San Francisco, Nov. 1-5 2010 F. Delage 1
Minor-Actinides transmutation in an Accelerator Driven System prototype: results from fuel developments within the
European integrated program EUROTRANS.
F. Delage, R. Belin, J.P. Ottaviani (CEA)X.-N. Chen, W. Maschek, A. Rineiski (KIT)
E. D’Agata, A. Fernandez, J. Somers, D. Staicu (JRC)F. Klaassen, S. Knol (NRG)
V. Sobolev (SCK CEN)R. Thetford (Serco for UK-NNL)
J. Wallenius (KTH)B. Wernli (PSI)
OUTLINES:Objectives & background
Items addressedIn-pile tests results
Major outcomes
11-IEMPT, San Francisco, Nov. 1-5 2010 F. Delage 2
Objectives & background for fuel developments• Objectives of domain AFTRA:
Ranking of ADS fuel concepts for European Facility for Industrial Transmutation (400 MWth, U-free fuel, Pb coolant) according to in-pile behaviour, out-of-pile properties, predicted behaviour
in normal operating conditions and safety performance Recommendations for the most promising fuel
• Fuel candidates:• Emphasis in Europe on oxide-based fuels
- reference: CERCER (Pu, MA)O2 + MgO and CERMET (Pu, MA)O2 + enrMo- solid-solution (Pu,MA,Zr)O2 as an alternativeFirst development in the frame of the FP5 - FUTURE program: best candidates according toperformance, safety and fabricability criteria + synthesis of oxide compounds + out-of-pilecharacterisationStrong synergy with transmutation target programs (ex: ECRIX-H)Large industrial experience on oxide fuel fabrication for critical reactors
• Nitride-based fuels (Pu,MA,Zr)N as a backup
Development by JAEA (EUROTRANS partner): JAEA ADS fuel compo. ~Pu0.2Am0.3Zr0.5NDevelopment in the frame of the FP5 - CONFIRM program: (Am,Zr)N synthesis, irradiationof (Pu,Zr)N pellets in HFR, out-of-pile measurements
11-IEMPT, San Francisco, Nov. 1-5 2010 F. Delage 3
Items addressed within AFTRA• CERCER & CERMET fuel element design and performance assessment:
– Pu/MA ratio, IM content, size & configurations of pellets, pins and SAs– Neutronic and thermo-mechanical behaviour from BOL to EOL
• Safety Analysis:– transients conditions: ULOF, UTOP, …– severe accidents
• In-pile experiments:– PIE on one pin of ADS fuel precursor (Pu0.3Zr0.7N ), irradiated in HFR (480W.cm-1,
10.4at%) within CONFIRM program– FUTURIX-FTA test in PHENIX– HELIOS test in HFR– BODEX test in HFR and Post Irradiation Examinations
• Out of pile experiments:– Thermal and mechanical properties of CERMET, CERCER fuels– Chemical compatibility : fuel/clad, fuel/coolant, TRU compounds/Inert Matrices– Oxygen potential– Pu-Am-O phase diagram
11-IEMPT, San Francisco, Nov. 1-5 2010 F. Delage 4
• Comparison of irradiation behaviour in EFIT representative conditions for 3 fuel types : oxides (european development), nitrides (JAEA development), metallic fuels (US development)
Collaboration DOE-JAEA-ITU-CEA• Investigation on MgO-CERCER and Mo-CERMET fuels under EUROTRANS umbrella
– Test successfully completed in March 2009 after 235 EFPD• CERMET fuel capsule:
– Pin 5: LHR ~130W/cm & BU~18at%
– Pin 6: LHR~130W/cm & BU~13at%
• CERCER fuel capsule:
– Pin 7: LHR~100W/cm & BU~9at%
– Pin 8: LHR~90W/cm & BU~6at%
– PIE scheduled in FP-7 FAIRFUELS project
Futurix-FTA experiment
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CERCER
CERMET
Pin nb composition Am (g/cm3)
TRU (g/cm3)
5 Pu0.8Am0.2O2-x + 86%vol Mo 0.3 1.3
6 Pu0.23Am0.25Zr0.52O2-x + 60%vol Mo 1.0 1.8
7 Pu0.5Am0.5O2-x + 80%vol MgO 1.0 2.0
8 Pu0.2Am0.8O2-x + 75%vol MgO 1.9 2.5
11-IEMPT, San Francisco, Nov. 1-5 2010 F. Delage 5
• Role of microstructure and T° on fuel swelling as well as helium build-up & release: – Pin 1: Am pyrochlore particles (~5-50µm) dispersed in MgO matrix with tailored open porosity– Pins 2&3 (T° instrumented): AmO2 in Yttrium stabilised ZrO2 crystal lattice w/o Pu– Pins 4&5: beads (>65µm) embedded in Mo w/o Pu
– Irradiation test successfully completed on Feb. 19, 2010 after ~241 EFPD & internal temperatures measured in pins 2&3 lower (~100°C) than expected
– PIE under progress within FP-7 FAIRFUELS project
HELIOS experiment
11-IEMPT, San Francisco, Nov. 1-5 2010 F. Delage 6
CERCER and CERMET pellets fabrication
ITU flowsheet / CERMET: CEA flowsheet / CERCER:
• Steps: particle synthesis by 2 routes and then conventional powder metallurgy
atomisation
gelation in ammonia
11-IEMPT, San Francisco, Nov. 1-5 2010 F. Delage 7
BODEX experiment (1/5)• Investigation of He build-up and release mechanisms in Inert Matrices
• 10B surrogate of 241Am to simulate He production:• Advantages: few wt% of 10B sufficient to be representative of He production, short irradiation time,
easy fabrication and handling.
• Design:
• HFR irradiation conditions: 57 EFPD - 10B burn-up: ~65% - He production: ~6x1020atoms/cm3
2x3 capsules : 3 pellets doped with 10B + 1 pellet doped with 11B + 1 undoped pellet
2 legs & on-line pressure measurements / 2 capsules
3 boron compounds : Mo2B / Mo ZrB2 / Y-ZrO2 Mg3B2O6 / MgO
2 T° : 800 - ~1200°C1 wt% B3 matrices : Mo, MgO, ZrO2
10B10B 10B 11B 0B
density >90% density> 90% density: 76-82%
hot leg
cold leg
containment shroud capsule
Thermocouples
Pressure transducers
α42
73
10
105 +→+ LinB
11-IEMPT, San Francisco, Nov. 1-5 2010 F. Delage 8
BODEX experiment (2/5)
• Behaviour of Mo samples:
He release (1200°C): 9 %
Non doped samples
Irradiation T°800°C 1200°C
before irradiation
before irradiation
Irradiation T°800°C 1200°C
10B doped samples
cracks
Vol. changes linked with 10B& T° increase
crack effects
(high density)
Global stabilityat both T°
11-IEMPT, San Francisco, Nov. 1-5 2010 F. Delage 9
BODEX experiment (3/5)
• Behaviour of MgO samples:
He release:- 32 % (800°C)- 35% (1200°C)
Non doped samples
Irradiation T°1200°C
before irradiation
10B doped samples
Swelling linked with 10B
Spread resultsLower swelling
at high T°
Irradiation T°1200°C
before irradiation
No cracks but very fragile materials
Extra-sintering of pure MgO
at 1200°C
(high open porosity)
11-IEMPT, San Francisco, Nov. 1-5 2010 F. Delage 10
BODEX experiment (4/5)
• Behaviour of ZrO2 samples:
He release (1200°C): 27%
Non doped samples
Irradiation T°1200°C
before irradiation
10B doped samples
Limited swelling
Irradiation T°1200°C
before irradiation
No cracks but fragile
materials
Higher ΔPo at 800°C
(high density)
11-IEMPT, San Francisco, Nov. 1-5 2010 F. Delage 11
BODEX experiment (5/5)
• Summary:
• Conclusion: – Molybdenum (high density): low helium release – significant swelling at 1200°C -
very good performance at 800°C
– MgO (high porosity): large He release – significant swelling at 800°C –
possible extra-sintering at 1200°C
– YSZ (high density): large He release - low swelling at both temperatures
Swelling ranges are manageable in all cases
10B- doped samples
Average swelling (%)
Open Porosity (%) He release (%)
Visual inspectionBOI EOI
Mo-800°C 2 2.4 2.3 N/Acracks
Mo-1200°C 9 2.5 4.6 9
MgO-800°C 8 21.3 27.1 32
fragileMgO-1200°C 3 22.7 24.7 35
YSZ-800°C 1.2 4.0 7.6 N/AYSZ-1200°C 4.1 3.5 5.1 27
11-IEMPT, San Francisco, Nov. 1-5 2010 F. Delage 12
– Fabrication of Am bearing fuels: demonstrated at laboratory scale with• Am content up to 36 wt% (1.9 g/cm3)• TRU-oxide fraction up to 40 vol%
– Fuel behaviour under irradiation:• first irradiation tests completed on ADS type fuels: FUTURIX-FTA & HELIOS• results gained in BODEX: swelling of Mo & MgO manageable
– Physical-chemical properties:• accurate data on thermal properties: heat capacity, thermal diffusivity, oxygen potential
and high T° species• first results on mechanical properties for (Pu,Am)O2: creep rate• chemical compatibility (normal operation T° conditions and short time) for
– MgO and Mo / PuO2 and Pu0.5Am0.5O2
– Pb / TRU-oxides, MgO and Mo– T91 / Pu0.8Am0.2O2-x, T91/Mo and T91/MgO, T91 / CERMET samples
• phase diagram investigation: Am drives the crystallographic structures of (Pu,Am)O2-y
– Am rich systems: hexagonal Am2O3 type structure– Pu rich systems: strong modifications with Am increase from fcc PuO2 to bcc Am2O3 structures
Major Outcomes on CERCER and CERMET fuels (1/2)
11-IEMPT, San Francisco, Nov. 1-5 2010 F. Delage 13
– Neutronic & transmutation performances under normal operation conditions:• fuel element configurations found to meet EFIT core specifications given by designers• similar performances with MgO-CERCER and enrMo-CERMET fuels
– Thermo-mechanical performances under normal operation conditions:• description of fission gas behaviour in heterogeneous media improved in models• good behaviour calculated (MACROS, TRAFIC) of both fuels
– Safety analysis: • sufficient safety margins for MgO-CERCER fuel • larger margins for Mo-CERMET fuel• T91 clad failure limits pose main restriction on safety (and design)
Reinforced interest for both enrMo-CERMET and MgO-CERCER for EFIT
Ranking between the 2 primary candidates seems premature without at least results of FUTURIX-FTA & HELIOS PIE scheduled in FP7-FAIRFUELS program (2009-2013)
Major Outcomes on CERCER and CERMET fuels (2/2)