Future MTR capabilities : Jules Horowitz Reactor Jean-François VILLARD, Gilles BIGNAN French alternative energies and atomic energy commission Nuclear Energy Division – Reactor Studies Department Cadarache – F-13108 St Paul Lez Durance, France Joint ICTP/IAEA Workshop “Research Reactors for Development of Materials and Fuels for Innovative Nuclear Energy Systems” 6-10 November 2017, ICTP - Trieste, Italy | PAGE 1
Future MTR capabilities : Jules Horowitz Reactor Summary 1. Context and objectives of the JHR 2. General figures of the JHR 3. Experimental capabilities of the JHR 4. JHR consortium and collaborations 5. Status of the reactor construction PAGE 2
1. Context and objectives of the JHR CEA | 10 AVRIL 2012 | PAGE 3 6 NOVEMBRE 2017
1. Context and objectives of the JHR In-pile testing in support of the nuclear Industry Just for France, 58 NPPs means more than 10 000 fuel assemblies under irradiation at a time… The fuel has to be carefully designed, with enough Safety Analysis Design Margins + new fuel managements need to generate additional margins + new LWR standards … 1. Improve Modeling, Calculation tools and Testing 2. Improve Safety Analysis design Methods 3. Improve Fuel Product In-pile data required ! PAGE 4
1. Context and objectives of the JHR The Key-Role of Material Testing Reactors for Fuel and Material qualification under irradiation BASIS RESEARCH CODES Validation & NUMERICAL QUALIFICATION DESIGN SIMULATION Documents EXPERIMENTAL DATA EXPERTISE CEA MANUFACTURING POST IRRADIATION SINGLE EFFECT REFABRICATION EXAMINATIONS EXPERIMENTS CHARACTERIZATION Hot Lab. Hot lab. for PIE BEHAVIOUR UNDER IRRADIATION Material Test Reactor PAGE 5
1. Context and objectives of the JHR MTRs in France SILOE Shutdown 1997 OSIRIS Shutdown 2015 PHENIX Shutdown 2010 PAGE 6
1. Context and objectives of the JHR Jules Horowitz Reactor Main objectives 1. R&D in support to nuclear Industry Safety and Plant life time management (ageing & new plants) Fuel behavior validation in incidental and accidental situation Assess innovations and related safety for future NPPs 2. Radio-isotopes supply for medical application 99 Mo production JHR will supply 25% of the European demand (today about 8 millions protocols/year) + Up to 50% upon specific request 3. A key tool to support expertise Training new generations (JHR simulator, secondees program) Maintaining a national expertise staff and credibility for public acceptance Assessing safety requirements evolution and international regulation harmonization PAGE 7
2. General figures of the JHR CEA | 10 AVRIL 2012 | PAGE 8 6 NOVEMBRE 2017
2. General figures of the JHR JHR: a modern 100 MWth pool-type light water MTR optimized for fuel and material testing PAGE 9
2. General figures of the JHR General layout of the JHR site Nuclear Auxiliary Building Reactor Building Laboratories Reactor pool Control room (DD, NDE) Hot cells Experimental (NDE + handling) rooms Storage pools (NDE) About 200 aseismic pads Warehouse and Cooling systems cold workshop Changing rooms + power supply Offices PAGE 10
2. General figures of the JHR Reactor building I&C rooms for loop + test device piping penetration Connection lines Cubicle ; Control of Thy conditions and water treatment Reactor vessel Test Core device FP laboratory dedicated to on-line FP measurement PAGE 11
2. General figures of the JHR Thermal neutron flux The core is under moderated: High fast neutron flux in the core High thermal neutron flux in the reflector ~20 simultaneous In core In reflector experiments 14 n/cm Up to 5.5 10 ² .s > 1 MeV 14 n/cm Up to 5.5 10 ² .s 15 n/cm Up to 10 ² .s > 0.1 MeV ~20 fixed positions ( 100mm ; 1 position 200mm) 7 Small locations ( F ~ 32 mm) and 6 displacement systems 3 Large locations ( F ~ 80 mm) Fuel studies: up to Fuel experiment 600 W/cm with a – GEN IV) (fast neutron flux 235 1% U PWR rod Material ageing Material ageing (up to 16 dpa/y ) (low ageing rate) GEN II & III + GEN IV Displacement systems: • Adjust the fissile power 1/Lethargy • Study transients Core Designed for UMo Al fuel Start - up with U Si - Al fuel 3 2 70 MWth / 100 MWth 25 to 30 days cycle length PAGE 12 6 - 7 days shutdown
2. General figures of the JHR Neutron spectra In core and in reflector 0.25 In reflector (moving system) 1,E+14 Thermal flux Fast flux Position 103 Position 101 0.2 Position C313 1,E+13 SFR core reference Flux par unité de léthargie (n/cm 2 /s) 0.15 1/Lethargy 1,E+12 0.1 1,E+11 0.05 1,E+10 T12 à 0 mm T12 à 50 mm 0 1.0E-09 1.0E-07 1.0E-05 1.0E-03 1.0E-01 1.0E+01 T12 à 100 mm 1,E+09 T12 à 150 mm E [MeV] T12 à 200 mm 1,E+08 1,0E-09 1,0E-08 1,0E-07 1,0E-06 1,0E-05 1,0E-04 1,0E-03 1,0E-02 1,0E-01 1,0E+00 1,0E+01 1,0E+02 Energie (MeV) 4,4 3,0 2,6 2,6 A large range of neutron fluxes and spectra (and possible adaptation with « neutron filters ») PAGE 13
3. Experimental capabilities of the JHR CEA | 10 AVRIL 2012 | PAGE 14 6 NOVEMBRE 2017
3. Experimental capabilities of the JHR Hosting experimental systems (dedicated to LWR material testing) OCCITANE For pressure vessel steel testing CALIPSO, MICA For material testing under high dpa and accurate temperature control Four 1 Four 1 (+ mechanical loading) specimen for µ structure evolution, tensile test ; Four 3 Four 3 Four 2 Four 2 for 1 or 2 D creep tests ; for bending tests (stress releiving experiments) ; … Four 4 Four 4 Four 5 Four 5 Four 6 Four 6 - I rradiated material behaviour Tensile tests, resilience test (Charpy), crack propagation tests ….. - Behaviour of Thermal CLOE Corrosion loop for “ Zr alloy Corrosion” and affected zones “Irradiation Assisted Stress Corrosion Cracking” 6 NOVEMBRE 2017 PAGE 15
3. Experimental capabilities of the JHR Hosting experimental systems (dedicated to LWR fuel testing) LORELEI fuel testing under ADELINE accidental conditions (LOCA) For fuel testing under off-normal conditions Power transient, post clad failure fuel behavior, • Source Term (FP releases) Lift- off experiment… • Rod thermal-mechanical behaviour Ballooning and clad burst (fuel relocation) Corrosion at high temperature Quenching and post-quench behaviour MADISON For fuel testing under nominal conditions PAGE 16
3. Experimental capabilities of the JHR Other possible hosting experimental systems (conceptual studies) High temp.material irradiation (600-1000°C) Large capacity MICA (material irrad) adapted to 1000°C gas conditions (Phaeton type – Osiris technology) minicomposite Transmutation studies Containment Other topics by-pass Expected Experimental He Content and HM Depletion a 10.000% LWR : Adeline « FP » ; Adeline “ power to melt ” 9.000% 8.000% 7.000% LWR severe accident studies JHR baseline % of HM depletion 6.000% 5.000% GFR : fuel irradiation (normal and off-normal conditions) 4.000% SFR reference 3.000% Fuel characterization : basic properties under irradiation 2.000% expected DIAMINO results 1.000% 15% and 7.5% Am (thermal diffusivity, thermal creep,..) 0.000% 0.00E+00 2.00E-01 4.00E-01 6.00E-01 8.00E-01 1.00E+00 1.20E+00 1.40E+ mg He/g initial HM CALIPSO adapted to SFR fuel and material Water flow Water flow Neutron flux Neutron flux Normal=> in core Off normal => in reflector (SCK possible contribution) NaK guide tube NaK guide tube PAGE 17
3. Experimental capabilities of the JHR Non Destructive Examination (NDE) Benches Test device examination in pools Sample examination Neutron imaging system in hot cells in reactor pool Coupled X-ray & Gamma and X-Ray bench in reactor pool tomography systems Coupled X-ray & Multipurpose test benches bench in storage pool Neutron Imaging System Coupled Gamma &X-ray bench Device Shielding Pool bank fixing Penetration Initial checks of the experimental loading LINAC (X) Bench Adjustment of the experimental protocol Y-table On-site NDE tests after the irradiation phase X-table XR-collimator XR-detector Z-table -detector Tunable front collimator View from the core Side cutaway PAGE 18
4. JHR consortium and collaborations CEA | 10 AVRIL 2012 | PAGE 19 6 NOVEMBRE 2017
4. JHR consortium and collaborations JHR Consortium : economical model for investment & operation CEA = Owner & nuclear operator with all liabilities JHR Consortium Members own Guaranteed Access Rights (in proportion of their financial commitment to the construction) A Member can use totally or partly his access rights for implementing proprietary programs with full property of results and/or for participating to the Joint International Programs open to non-members Open to new member entrance until JHR completion JHR Consortium current partnership: Research centers & Industrial companies IAEC Associated Partnership: JAEA PAGE 20
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