Fuel and material irradiation hosting systems in the Jules Horowitz reactor
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1 Fuel and material irradiation hosting systems in the Jules Horowitz reactor CEA/Cadarache, DEN/DER/SRJH, F St Paul Lez Durance 14 FÉVRIER 2014 PAGE 1
2 CONTENTS Fuel and material irradiation hosting systems in the Jules Horowitz Reactor 1. JHR facility & experimental capacity 2. Irradiation hosting systems available at the JHR start-up 3. Irradiation hosting systems available after the JHR start-up 4. Conclusion 14 FÉVRIER 2014 PAGE 2
3 1.1 JHR facility & experimental capacity Nuclear auxiliary building A facility dedicated to experimental purposes within a modern safety frame Reactor building Reactor pool FP labs + Cubicles A modern facility : Large experimental areas Fission Product Laboratory Chemistry Laboratory I&C: 3 floors, 490 m 2 Cubicle: 3 floors, 700 m 2 Hot cells & and storage pools (NDE, α cell ) In reflector Up to 3.5E14 n/cm².s (th) Fixed irradiation positions (Φ100 mm & Φ200 mm) and on 6 displacement systems In core Up to 5.5E14 n/cm².s (E> 1 MeV) Up to 1.E15 n/cm².s (E> 0.1 MeV) 7 small locations (F ~ 32mm) 3 large locations (F ~ 80mm) Material ageing (up to 16 dpa/y) LWR fuel experiments + Material ageing (low ageing rate) Displacement systems - In water channels (reflector) - Flexible power variations - Experiment decoupled from the core PAGE 3
4 1.2 JHR facility & experimental capacity Non Destructive Examination (NDE) Benches Sample examination in hot cells Gamma and X-Ray tomography systems Multipurpose test benches Test device examination in pools Neutron imaging system in reactor pool Coupled X-ray & stand in reactor pool Coupled X-ray & stand in storage pool Pool bank fixing Bench Coupled X-ray & γ stands Device Shielding Penetration LINAC (X) Neutron Imaging System (See paper N 1010 at this conference) Y-table X-table Z-table XR-collimator XR-detector View from the core -detector Tunable front collimator Side cutaway Initial checks of the experimental loading Adjustment of the experimental protocol On-site NDE tests after the irradiation phase 14 FÉVRIER 2014 PAGE 4
5 CONTENTS Fuel and material irradiation hosting systems in the Jules Horowitz Reactor 1. JHR facility & experimental capacity 2. Irradiation hosting systems available at the JHR start-up 3. Irradiation hosting systems available after the JHR start-up 4. Conclusion 14 FÉVRIER 2014 PAGE 5
6 2.1 MADISON test device (1/2) Dedicated to reproduce normal operation of NPP Comparative instrumented irradiations : Fuel evolution (HBU ), Clad corrosion No clad failure expected in normal operation Located in reflector on displacement device A water loop Located in a dedicated cubicle Monitoring of thermal hydraulics conditions Monitoring of chemistry conditions An In-pile part Large hosting capacity Ability to reach high linear power for high BU fuel High performance instrumentation Experimental cubicle Fuel linear power (W/cm) Performance for an irradiation rig holding 2 rods (UO2 4,95% enriched fuel) Best-estimate curve Série1 Série2 Série3 Pool pipes % margin of performances FÉVRIER 2014 Burn Up (GW.d/t) Reactor pool Experimental device PAGE 6
7 2.1 MADISON test device (2/2) A large flexibility of use Thermal-hydraulics conditions PWR BWR VVER Chemistry conditions Normal chemistry (Including Br, Li) Specific chemistry conditions upon request Hosting capacity High embarking capacity Highly instrumented experiments In-pile Instrumentation Water loop instrumentation (thermal balance ) Fuel sample instrumentation T CT CL FL P Temperature measurement Clad thermocouple Clad Elongation Fuel Stack Elongation Fuel Plenum Pressure NF Neutron flux LVDTs Fuel samples (60 cm) In-core cable connectors for instrumentation CT Heat exchanger BWR experiments Top seal assembly PAGE 7
8 2.2 ADELINE test device For characterization and qualification of one LWR fuel rod under off-normal conditions (clad failure possible) Located in reflector on displacement device Based on the OSIRIS feedback (ISABELLE test device) A water loop: Located in a dedicated cubicle Monitoring of thermal hydraulics conditions Monitoring of chemistry conditions An In-pile part 1 st Rig designed for POWER RAMPS High linear power ramps up to 620 W/cm High power ramp rate up to 700 W/cm.min Quantitative clad elongation measurement (2 LVDT) Quantitative gamma spectrometry system Up to 4 ramps / JHR cycle (25 days) 250 C 620 W/cm ± 10 W/cm max 255 C heater 170 C piping penetrations jet pumps reactor pool Linear Power of the rod CFD experimental area hot side cold side 180 C M Circulating pumps moderating 190 C heat temperature exchanger M control valve diaphragme charging M pressure pumps relief valve Main heat exchanger 265 C 40 C M 65 C intermediary cooling residual circuit heat exchanger Intermediary heat exchanger secondary RSD RSD cooling system high power plateau up to 24h CUBICLE feed water tank volume control tank 2nd Rig Connection with FP laboratory (fuel rod with fission gas sweeping and on-line analysis) Additional instrumentation (ex : fuel centerline T, fuel stack elongation, plenum pressure ) 100 W/cm to 200 W/cm conditioning low power plateau from 12h to 7 days power ramp up to 700 W/cm/min irradiation time PAGE 8
9 Gamma heating (W/g C) 2.3 MICA test device Investigation of physical properties of material (vs flux, fluence and temperature) Static NaK capsule Based on the OSIRIS feedback (CHOUCA test device) 2 concentric tubes delimiting a gas gap In core location External diameter: 32 mm Dose : up to 16 dpa/y (100 MW) Samples temperature adjustment (< 450 C): Gamma heating Gas gap dimension / nature of gas Electric heating elements In the center of a fuel element Experimental area & NaK Operating range 25 He thickness : 0,5mm / min elec. heat. He thickness : 0,5mm / max elec. heat Temperature ( C) He thickness : 0,25mm / min elec. heat. He thickness : 0,25mm / max elec. heat He thickness : 0,1mm / min elec. heat. He thickness : 0,1mm / max elec. heat upper reactor pow er Limit 100MW (16,1 W/g) upper reactor pow er limit 70MW (11,3 W/g) low er reactor pow er limit 70MW(8,1 W/g) Limit of SS negligible creep (450 C) Sample holder (experimental area) Outer diameter: 24 mm Compromise between the number of samples and the quantity of instrumentation (TC, elongation sensor, diameter gauge, loading system ) 14 FÉVRIER 2014 PAGE 9
10 CONTENTS Fuel and material irradiation hosting systems in the Jules Horowitz Reactor 1. JHR facility & experimental capacity 2. Irradiation hosting systems available at the JHR start-up 3. Irradiation hosting systems available after the JHR start-up 4. Conclusion 14 FÉVRIER 2014 PAGE 10
11 3.1 CALIPSO test device In the center of a fuel element Investigation of physical properties of material Thermodynamic loop integrated within the test device Heat Exchanger (HE) / Electrical Heater (EH) Innovative electromagnetic pump (L 450 mm, D 80 mm) NaK flow (2 m 3 /h) Improvement of the sample temperature mastering From 250 up to 450 C (setting of HE & EH parameters) Δθ < 8 C (Tmax Tmin all along the samples stack) P P P P P P P Pump (EM) On-going qualification of the design with a CALIPSO prototype 14 FÉVRIER 2014 PAGE 11 First successful tests of the electromagnetic pump
12 3.2 OCCITANE test device Investigation of physical properties after irradiation of NPP pressure vessel steels Static Helium capsule Based on the OSIRIS feedback (IRMA test device, 150 irradiation cycles) Ex-core location Fixed location Dose :up to 100 mdpa/y (1 MeV) Samples temperature adjustment C Gamma heating Gas gap dimension Electric heating elements At least, 18 thermocouples, and 45 dose integrators Equivalent carrying volume: 30x62.5x500mm 3 Helium gas C (furnace with 6 heating zones) 100 mdpa/year 14 FÉVRIER 2014 PAGE 12
13 3.3 CLOE test device Need of a corrosion loop to perform integral experiments India in-kind contribution (DAE-BARC) CEA corrosion loops feedback, MTR+i3 European project LWR conditions: well controlled and adjusted water chemistry, temperatures, Fixed location Ex-core with a large diameter In-core with a smaller diameter (taking into account safety aspect) In-situ measurements: ECP, ph, H2, load, LVDT, cracking propagation, DCPD 14 FÉVRIER 2014 PAGE 13
14 Re-irradiation Emptying 3.4 LORELEI test device IAEC Dedicated to LOCA mechanisms investigation LOCA type sequence Thermal-mechanical behaviour of fuel Radiological consequences Integrated water loop capsule (single fuel rod) Re-irradiation phase (Thermo-siphon + production of short half-life fission products) Dry out phase (He injection) High temperature plateau Quenching phase (water injection) Adequate monitoring of fuel environment Neutron shielding to flatten neutron flux Electrical heater (homogeneous temperature) Monitoring of temperature heat-up (10-20 C/s) High temperature targeted (up to 1200 C) FP release analysis connection to the JHR FP laboratory Preliminary design review early 2014 with IAEC Temperature Power Adiabatic phase Cladding burst FP FP Clad temperature Nuclear power Cooling and quenching phase FP Time 14 FÉVRIER 2014 PAGE 14
15 CONTENTS Fuel and material irradiation hosting systems in the Jules Horowitz Reactor 1. JHR facility & experimental capacity 2. Irradiation hosting systems available at the JHR start-up 3. Irradiation hosting systems available after the JHR start-up 4. Conclusion 14 FÉVRIER 2014 PAGE 15
16 4. CONCLUSION Summary Development of an experimental capacity for JHR in support to fuel & materials irradiation programs : A set of test devices (some of them available at the JHR start-up) NDE systems Analysis laboratories Modern equipments with a design taking into account: OSIRIS and HRP feedback and knowhow New approach and innovative technologies from the JHR consortium partners Up-to-date safety frame JHR (50 y) PAGE 16
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