1. Copyright © 2012 SCKCEN 3 rd LEADER International workshop Pisa & Bologna, 4-7 September 2012 Didier De Bruyn (SCKCEN) 1 Different ADS concepts in the world: EFIT, MYRRHA & the others

2. Copyright © 2012 SCKCEN Contents Nuclear energy in Europe Dealing with radioactive waste Some ADS concepts from the past, within and outside Europe Some more recent concepts  next presentation Conclusion 2

3. Copyright © 2012 SCKCEN 3 Nuclear energy in Europe 152 reactors in 15 countries in EU-27, producing 31% of EU’s electricity The largest source of low carbon energy Excellent safety record Europe, a world leader –but competition is building (Russia, Japan, USA, China, India) Energy consumption shares in EU-25 (2005) Electricity generation shares in EU-25 (2005) 3

4. Copyright © 2012 SCKCEN 4 Nuclear fission in Europe’s low carbon energy policy Nuclear fission contributes today 31% of EU electricity – the largest low carbon energy source Target 2020 : Maintain competitiveness in fission technology and provide long term waste management solutions For the longer term, we need to act now to: Complete the demonstration of Gen IV with closed fuel cycle for increasing sustainability, Enlarge the nuclear fission applications beyond electricity production, namely towards H 2, heat, H 2 0 desalination. Ambitious R&D and Demo programmes need to start now to meet the required breakthroughs 4

5. Copyright © 2012 SCKCEN waste minimisation better use of resources reduced proliferation risks 5

6. Copyright © 2012 SCKCEN Contents Nuclear energy in Europe Dealing with radioactive waste Some ADS concepts from the past, within and outside Europe Some more recent concepts  next presentation Conclusion 6

7. Copyright © 2012 SCKCEN Fission generates High-Level Nuclear Waste 7 U 235 n Pu NpAm Cm Actinides Minor Actinides Neutron Uranium Fission Fuel U 238 n n n U 235 U 238 PlutoniumNeptuniumAmericiumCurium Minor Actinides high radiotoxicity long lived waste that are difficult to store due to:  Long lived (>1,000 years)  Highly radiotoxic  Heat emitting

8. Copyright © 2012 SCKCEN spent fuel reprocessing no reprocessing Uranium naturel Time (years) Relative radiotoxicity transmutation of spent fuel Duration Reduction 1.000x Volume Reduction 100x Rad waste reduction is the motivation for Transmutation 8

9. Copyright © 2012 SCKCEN 9 9 GEN-IV FR Losses Pu+MA Multirecycling Repository UOX PWR Fuel fabrication Reprocessing CR = Conversion ratio = fissile material produced/fissile material destroyed. CR 1 : breeder From M. Salvatores et al. (GLOBAL 2009) A first option : the FR introduction Multiple recycle of TRU is feasible in a Fast Reactor (FR), whatever its coolant and fuel type: oxide, metal, carbide or nitride 2-5% MA in the fuel: close to standard fuel, if homogeneous recycle chosen and CR>0.8 Some impact on the fuel cycle, e.g. at fuel fabrication, due to the Cm-244 spontaneous fission neutron emission Reprocessing needed to recover not- separated TRU (enhanced proliferation resistance)

10. Copyright © 2012 SCKCEN 10 multirecycling Repository UOX PWR MOX PWR Dedicated transmuter system Pu MA+Pu Pu Losses MA+Pu MA Fuel fabrication Reprocessing Losses The second option : the ADS scenario Called "Double strata" Still considering Pu as a resource Gen-IV FR deployment delayed Pu inventory can be stabilized MA management in dedicated transmuter systems: e.g. ADS or critical FR with low CR. Fuel: New fuel (with high MA content) needs to be developed Reprocessing: to be developed in particular for U-free fuels. Choice of support matrix in fuel is relevant. Potential impact on the fuel cycle (high decay heat, high neutron emissions) From M. Salvatores et al. (GLOBAL 2009)

11. Copyright © 2012 SCKCEN 11 ADS: Accelerator Driven System for transmutation Both critical reactors and sub- critical Accelerator Driven Systems are potential candidates as dedicated transmutation systems. Critical reactors, however, loaded with fuel containing large amounts of MA pose safety problems caused by unfavorable reactivity coefficients and small delayed neutron fraction. ADS operates flexible and safe at high transmutation rate 11 Proton Beam Spallation Target accelerator

12. Copyright © 2012 SCKCEN Contents Nuclear energy in Europe Dealing with radioactive waste Some ADS concepts from the past, within and outside Europe Some more recent concepts  next presentation Conclusion 12

13. Copyright © 2012 SCKCEN ADS in Europe: past and present Energy Amplifier (EA) developed at CERN in the 90’s: devoted to a better use of resources; EA evolved then to XADS ADONIS project in Belgium (1995-1996): solely devoted to the production of radio-isotopes for the medical industry; ADONIS evolved to MYRRHA in 1997; this project still exists Both projects (XADS, MYRRHA) have been brought together in FP5 project PDS-XADS  FP6 IP-EUROTRANS, finally  FP7 CDT PDS-XADS (2002-2004): 80 MWth LBE-cooled and gas-cooled, 50 MWth small-scale EUROTRANS (2005-2010): two designs MYRRHA, 70 MWth small-scale short-term, EFIT, 400 MWth mid-scale long-term CDT (2009-2012): MYRRHA/FASTEF, 70-100 MWth short-term, sub- critical & critical 13

14. Copyright © 2012 SCKCEN 14 The EFIT concept Within the EUROTRANS project, the EFIT concept is developed for the transmutation of MAs EFIT stays for European Feasibility for Industrial Transmutation Its main features: ADS with k eff (t) ≤ 0,97 Lead-cooled sub-critical core (Tin=400 °C, Tout=480°C) MA & Pu Oxide fuel in inert matrix (MgO) several hundreds MW power 14

15. Copyright © 2012 SCKCEN 1 Reactor Core 2 Active Zone 3 Diagrid 4 Primary Pump 5 Cylindrical Inner Vessel 6 Reactor Vessel 7 Reactor Cavity 8 Reactor Roof 9 Reactor Vessel Support 10 Rotating Plug 12 Above Core Structure 13 Target Unit 14 Steam Generator Unit 15 Fuel Handling Machine 16 Filter Unit 17 Core Instrumentation 18 Rotor Lift Machine 19 DHR Dip Cooler EFIT Reactor Assembly 15

16. Copyright © 2012 SCKCEN EFIT main process parameters 16 Reactor Thermal Power, max design capability416 MW Proton beam power, max (800 MeV, 20 mA)16 MW Core Thermal Power395 MW Primary coolant flow rate, total36,000 kg/s Core inlet temperature400 °C Core outlet temperature, mean480 °C Feed water mass flow rate250 kg/s Feed water Inlet Temperature335 °C Steam Temperature450 °C Steam Pressure14 MPa

17. Copyright © 2012 SCKCEN Main data Proton Beam Energy, MeV800 Max proton beam current, mA20 Proton beam energy deposited, MW11.2 Primary Pb Coolant inlet Temp. (°C)400 Primary Pb Coolant outlet Temp. (°C)450 Primary Pb d Coolant Flow-rate (kg/s)1500 Target Pb Coolant Cold Temp. (°C)419 Target Pb Coolant Hot Temp. (°C)515 Target Pb Coolant Flow-rate (kg/s)800 FA positions occupied 19 Outside diameter 78.2 cm EFIT Windowless Spallation Target Concept 17

18. Copyright © 2012 SCKCEN 252 position for Dummy Assemblies and Absorber Elements 42 FA 66 FA 72 FA 19 position for Target Inner, Intermediate, Outer FA Design and Core Section Enrichment = Pu/(Pu+MA) = 45.7% EFIT Core Configuration 18

19. Copyright © 2012 SCKCEN Contents Nuclear energy in Europe Dealing with radioactive waste Some ADS concepts from the past, within and outside Europe Some more recent concepts  next presentation Conclusion 19

20. Copyright © 2012 SCKCEN ADS outside Europe: past and present Japan (JAEA): Experimental scale 30 MWth, then 60 MWth Cooled by LBE (backup option being sodium) Keff ~ 0,93 Industrial scale 800 MWth (see later) Korea (KAERI) HYPER (Hybrid Power Extraction Reactor) designed since 1997 Designed to transmute TC-99 and I-129 coming from PWRs 1000 MWth; LBE-cooled Keff ~ 0,98 20

21. Copyright © 2012 SCKCEN Conceptual Design Study of the JAEA Reference ADS 21  The JAEA design study has been concentrated on the concept of a “commercial-size” one with a thermal power of 800 MWth.  A superconducting linear accelerator is adopted to deliver a 1,5 GeV * 20 mA = 30 MW (maximum value) proton beam.  Lead-bismuth eutectic (LBE) is used as core coolant and spallation target.  Spallation target and accelerator are separated by a beam duct and a beam window inserted down to the active core.  Dedicated nitride fuel (MA, Pu)N + ZrN, where nitrogen is enriched up to 99 % with 15 N, is a primary candidate, which can be recycled by a pyrochemical process with recovering 15 N. Concept of JAEA’s 800MWth ADS

22. Copyright © 2012 SCKCEN JAEA Design Study : ADS Plant System 22

23. Copyright © 2012 SCKCEN JAEA Design Study : Seismic Design 23 Three-dimensional entire building seismic isolation system 3D seismic isolation devices support the entire reactor building. The 3D isolator, absorbs vertical vibration by the air spring, while the horizontal one is absorbed primarily by the laminated rubber bearing.

24. Copyright © 2012 SCKCEN JAEA Design Study : Beam Window Expected window life : 2 years Shape & thickness determined by Thermal stresses Structural stresses (LBE outside pressure) Material : T91 Irradiation damage taken into account As well as corrosion rate 24

25. Copyright © 2012 SCKCEN Comparison JAEA – EFIT designs 25 JAEAEFIT Plant Proton energy1.5 GeV x 20 mA800 MeV x 20 mA Spallation target conceptLBE, Centered, window, cooled with primary coolant Pb, Centered, windowless, cooled with independent Pb coolant loop Maximum k eff 0.97 Power (MWth)800384 Thermal efficiency32%40% Fuel amount (HMt)4.175.4 Transmutation performance43.4kg/TWhth45kg/TWhth Reactivity swing compensationProton current Seismic designThree-dimensional anti-seismic supportsHorizontal anti-seismic supports Coolant Primary coolantLBEPure Lead Primary system temperature range (C)inlet: 300, outlet: 407inlet: 400, outlet: 480 Coolant velocity (m/s)22 Secondary coolantLow pressure boiling waterSuperheated water cycle Assembly Maximum Power density (W/cm 3 )449243 Linear power density244 W/cm (average)<200W/cm(Cer-Cer) Fuel assembly typeWrapperlessWrapper Fuel (Pu,MA)N+ZrN(Pu, AM)O 2 +MgO(or Mo) Practical density90%90%(CERCER),93%(CERMET) Average burn-up115 GWd/t78GWd/t Clad Cladding material9Cr-1MoT91 Maximum cladding temperature580550

26. Copyright © 2012 SCKCEN Contents Nuclear energy in Europe Dealing with radioactive waste Some ADS concepts from the past, within and outside Europe Some more recent concepts  next presentation Conclusion 26

27. Copyright © 2012 SCKCEN Conclusion Advanced nuclear fuel cycles are required to meet now the objective of making nuclear fission sustainable The objectives of sustainability: waste minimisation, better use of the natural resources and reduced proliferation risks can be met with both fast reactors and dedicated burners (ADS) Design studies have been performed within and outside Europe Demonstrations (prototypes) should be planned and realized, to go from paper work to real work Through the new MYRRHA research infrastructure (see next presentation), Belgium is contributing to this international endeavour. 27

28. Copyright © 2012 SCKCEN Copyright © 2012 - SCK  CEN PLEASE NOTE! This presentation contains preliminary data for dedicated use ONLY and may not be cited without the explicit permission of the author. If this has been obtained, please reference it as a “personal communication. Copyright SCKCEN”. SCKCEN Studiecentrum voor Kernenergie Centre d'Etude de l'Energie Nucléaire Belgian Nuclear Research Centre Stichting van Openbaar Nut Fondation d'Utilité Publique Foundation of Public Utility Registered Office: Avenue Herrmann-Debrouxlaan 40 – BE-1160 BRUSSELS Operational Office: Boeretang 200 – BE-2400 MOL