MYRRHA Multipurpose hYbrid Research Reactor for High-tech Applications Contributing to the 3rd Pillar of the European Strategy for P&T

ESNII + summer school –– Stockholm MYRRHA ESNII + summer school –– Stockholm May 18-20, 2014 Marc Schyns SCK•CEN, Boeretang 200, 2400 Mol, Belgium mschyns@sckcen.be or myrrha@sckcen.be

Content SCK•CEN presentation MYRRHA project

www.sckcen.be Belgian Nuclear Research Centre is a foundation cradle of nuclear research, applications and energy development in Belgium major international player in the field of nuclear R&D creator of "spin-off's": IRE, BN, BP, VITO tutorship: federal Secretary of Energy Melchior Wathelet today: ~700 staff, >50% with academic degree + 70 PhD students annual turnover: 125 M€ 45% government support 55% contract work research towards sustainability www.sckcen.be

Statutory mission of SCK•CEN research on safety waste management protection of man and environment fissile and other strategic materials societal implications of endurable energy training and education services towards nuclear industry the medical sector the authorities in the field of nuclear applications

Environment Health Safety 'Analyse' Radiation Effects

Nuclear Material Science

99Mo/99mTc Production 30-40 Million medical procedures per year = 100.000 patients per day 65% (peak) - 25% (yearly) from BR2 but most existing research reactors are getting old

research, development needs education, training 1950 1970 1990 2010 2030 2050 2070 2090 1950 1970 1990 2010 2030 2050 2070 2090 research, development needs education, training

Some pioneering highlights 1st pressurized water reactor outside of US: BR3 Inventor of innovative nuclear fuel: MOX Highest performing material testing reactor in Europe: BR2 World’s first lead-based ADS: GUINEVERE World’s premiere project for transmutation of nuclear waste: MYRRHA World’s first underground laboratory for R&D on HL waste disposal: HADES

MYRRHA - Accelerator Driven System Reactor Subcritical or Critical modes 65 to 100 MWth Accelerator (600 MeV - 4 mA proton) Fast Neutron Source Spallation Source Lead-Bismuth coolant Multipurpose Flexible Irradiation Facility Innovative & Unique

MYRRHA Accelerator Challenge fundamental parameters (ADS) particle p beam energy 600 MeV beam current 4 mA mode CW MTBF > 250 h challenge ! failure = beam trip > 3 s implementation superconducting linac frequency 176.1 / 352.2 / 704.4 MHz reliability = redundancy double injector “fault tolerant” scheme

About beam trips

MYRRHA Accelerator Challenge

MYRRHA linac

Reactor layout Reactor Vessel Reactor Cover Core Support Structure Core Barrel Core Support Plate Jacket Core Reflector Assemblies Dummy Assemblies Fuel Assemblies Spallation Target Assembly and Beam Line Above Core Structure Core Plug Multifunctional Channels Core Restraint System Control Rods, Safety Rods, Mo-99 production units Primary Heat Exchangers Primary Pumps Si-doping Facility Diaphragm IVFS IVFHS IVFHM

Core and Fuel Assemblies 151 positions 37 multifunctional plugs

Core and Fuel Assemblies Cladding in 15-15 Ti Wire wrap Wrapper

Cooling systems Decay heat removal (DHR) through secondary loops 4 independent loops redundancy (each loop has 100% capability) passive operation (natural convection in primary, secondary and tertiary loop) Ultimate DHR through RVCS (natural convection)

Cooling systems

Integration into building

Remote Handling

Remote Handling (Fuel recovery)

Multipurpose facility Fuel research Φtot = 0.5 to 1.1015 n/cm².s F = 1 to 5.1014 n/cm².s (ppm He/dpa ~ 10) in medium-large volumes Material research FFast = 1 to 5.1014 n/cm².s (En>1 MeV) in large volumes Fission GEN IV Fusion Multipurpose hYbrid Research Reactor for High-tech Applications High energy LINAC 600 MeV – 1 GeV Long irradiation time 50 to 100 MWth FFast = ~1015 n/cm².s (En>0.75 MeV) Fundamental research Waste Fth = 0.5 to 2.1015 n/cm².s (En<0.4 eV) Fth = 0.1 to 1.1014 n/cm².s (En<0.4 eV) Radio- isotopes Silicon doping

Motivation for transmutation spent fuel reprocessing no reprocessing Uranium naturel Time (years) Relative radiotoxicity transmutation of spent fuel Duration Reduction 1.000x Volume Reduction 100x

Fast Neutron are unavoidable for transmutation To transmute MAs, we need to fission them The ration Fission/Capture is more favorable with fast neutrons

European Strategy for P&T The implementation of P&T of a large part of the high-level nuclear wastes in Europe needs the demonstration of its feasibility at an “engineering” level. The respective R&D activities could be arranged in four “building blocks”: Demonstration of the capability to process a sizable amount of spent fuel from commercial LWRs in order to separate plutonium (Pu), uranium (U) and minor actinides (MA), Demonstration of the capability to fabricate at a semi-industrial level the dedicated fuel needed to load in a dedicated transmuter (JRC/ITU), Design and construction of one or more dedicated transmuters, Provision of a specific installation for processing of the dedicated fuel unloaded from the transmuter, which can be of a different type than the one used to process the original spent fuel unloaded from the commercial power plants, together with the fabrication of new dedicated fuel.

P&T inspired many Euratom projects TOPIC FP5 FP6 FP7   Coupling MUSE DM2 ECATS FREYA Fuels FUTURE DM3 AFTRA FAIRFUELS Materials MEGAPIE DM4 DEMETRA MATTER SPIRE, TECLA GETMAT Design PDS-XADS DM1 DESIGN CDT MAX ADOPT EUROTRANS SERIM G4 Thermal-Hydraulics ASCHLIM THINS LFR - ESLY LEADER Infrastructures VELLA, MTRI3 ADRIANA, SARGEN, NEWLANCER Scenario Studies PATEROS ARCAS Safety SEARCH, SILER, MAXSIMA 28 M€ 31 M€ 31 M€

Is sub-criticality a luxury? Both Critical reactors as well as ADS can be used as MAs transmuters Nevertheless, critical reactors, heavily loaded with MAs, can experience severe safety issue due to reactivity effet induced by a smaller fraction of delayed neutrons. ADS can operate in a more flexible and safer manner even if heavily loaded with MAs hence leading to efficient transmutation therefore we say that sub-criticality is not a luxury but a necessity. Proton Beam Spallation Target accelerator

ADS is the most efficient system for burning MAs Pu Production Rate (grams / GWh) MA Production Rate (grams / GWh) * Mike Cappiello, (LANL), “The Potential Role of Accelerator Driven Systems in the US”, ICRS-10/RPS’2004, Madeira (PT), 2004

FP6-PATEROS A European approach to P&T P&T useful for countries in phase out with active nuclear programme Reduction of volume & heat load of waste P&T should be seen at a regional/European level Scenario studies: 4 country groups A: stagnant or phase-out B: continuation and Pu optimisation for FRs C: subset of A in “nuclear renaissance” D: non-nuclear to go nuclear

Even with completely different national NE policies European solution for HLW works with ADS Advantages for A ADS shared with B ADS burn A’s Pu& MA Smaller Fu-Cycle units & shared SHARED Scenario 1 objective: elimination of A’s spent fuel by 2100 A = Countries Phasing Out, B = Countries Continuing

If an ADS can’t produce electricity than it can’t also transmute ! Indeed, the 1st Objectif of an ADS is to burn efficiently and in a concentrated manner MAs ! If it burns MAs, this means it produces heat that can be turned into electricity. The total thermal efficiency of an ADS is related to the two following yields: The accelerator yield hacc = P->reactor / Pe (Acc) The yield of the thermal-dynamic cycle of the sub-critical reactor hth= Pe (net) / Pth

MYRRHA: hTotal = 0.14 ΔPe = +12 MWe 600 MeV x 4 mA = 2.4 MW hacc = 0.15 Pacc = 16 MWe Pth = 85 MWth hth = 0.33 Pe = 28 MWe ΔPe = +12 MWe

EFIT: hTotal = 0.32 ΔPe = +126 MWe 600 MeV x 20 mA = 12 MW hacc = 0.35 Pacc = ~34 MWe Pth = 400 MWth hth = 0.40 Pe = 160 MWe ΔPe = +126 MWe

JADS: hTotal = 0.37 ΔPe = +293 MWe 1500 MeV x 20 mA = 30 MW hacc = 0.45 Pacc = ~67 MWe Pth = 800 MWth hth = 0.45 Pe = 360 MWe ΔPe = +293 MWe

But MYRRHA is more than research on ADS & Transmutation

Multipurpose facility Fuel research Φtot = 0.5 to 1.1015 n/cm².s F = 1 to 5.1014 n/cm².s (ppm He/dpa ~ 10) in medium-large volumes Material research FFast = 1 to 5.1014 n/cm².s (En>1 MeV) in large volumes Fission GEN IV Fusion Multipurpose hYbrid Research Reactor for High-tech Applications High energy LINAC 600 MeV – 1 GeV Long irradiation time 50 to 100 MWth FFast = ~1015 n/cm².s (En>0.75 MeV) Fundamental research Waste Fth = 0.5 to 2.1015 n/cm².s (En<0.4 eV) Fth = 0.1 to 1.1014 n/cm².s (En<0.4 eV) Radio- isotopes Silicon doping

Material Irradiation Performances Critical@100 MW IPS in Chan [0 0 0] IPS in Chan [2 0 0] Sample n° dpa/EFPY Φtot 8 18.1 2.38E+15 16.2 2.12E+15 7 23.0 2.85E+15 20.7 2.54E+15 6 25.9 3.19E+15 23.3 5 27.5 3.37E+15 24.5 3.02E+15 4 27.2 3.39E+15 3.03E+15 3 25.7 3.23E+15 22.9 2.89E+15 2 22.3 2.92E+15 19.9 2.62E+15 1 17.3 2.50E+15 15.5 2.23E+15

Irradiation capabilities of IPS Sub-critical @ 73 MW Total flux, n/(cm2s) Fast (> 0.75 MeV) flux, n/(cm2s) Radiation damage, DPA/FPY Helium production, appm/FPY Ratio appm He/DPA 1 2.64×1015 4.20×1014 22.3 7.66 0.343 2 2.72×1015 4.29×1014 23.0 10.41 0.452 3 2.75×1015 23.1 5.94 0.257 4 4.18×1014 22.5 6.59 0.293 5 2.70×1015 4.35×1014 22.7 6.52 0.288 6 2.68×1015 4.23×1014 22.8 10.78 0.474

Prepare the path for Fusion DEMO Irradiation capabilities under the spallation target +10 cm 0 cm -30 cm

MYRRHA-IMIFF for fusion material In critical mode (fast reactor), appmHe/dpa ~ 0.2 to 1  not optimal for fusion materials experiments In sub-critical mode (ADS), high appmHe/dpa ratio is reached, specially in the region of the window of spallation source Volume of 1 lt with appmHe/dpa ~ 12 close to spallation target Useful volume 30 lt with range from 5 to 20 appmHe/dpa

MYRRHA for fusion irradiations Estimated damage induced in DEMO and proposed irradiation conditions in IFMIF and MYRRHA-IMIFF

Multipurpose facility Fuel research Φtot = 0.5 to 1.1015 n/cm².s F = 1 to 5.1014 n/cm².s (ppm He/dpa ~ 10) in medium-large volumes Material research FFast = 1 to 5.1014 n/cm².s (En>1 MeV) in large volumes Fission GEN IV Fusion Multipurpose hYbrid Research Reactor for High-tech Applications High energy LINAC 600 MeV – 1 GeV Long irradiation time 50 to 100 MWth FFast = ~1015 n/cm².s (En>0.75 MeV) Fundamental research Waste Fth = 0.5 to 2.1015 n/cm².s (En<0.4 eV) Fth = 0.1 to 1.1014 n/cm².s (En<0.4 eV) Radio- isotopes Silicon doping

MYRRHA - Concept ISOL@MYRRHA - Concept MYRRHA - Concept thin refractory metal foils carbide powders liquid targets surface ion source ECR ion source RILIS

Beam-Splitting System (Concept) Questions: - Is there a (big) interest for the users community to upgrade the linac from 600 MeV to 1 GeV? 600 MeV ~ 100 - 200 mA pulsed beam (up to 250 Hz) 600 - 800 MeV 2 - 4 mA CW

Applications (ISOL@MYRRHA Applications) Nuclear Physics Astro-physics Atomic Physics Fundamental Interactions Medical Applications Day Week Month Year Typical Beam Time/Experiment Condensed Matter Chemistry Biology d<r2>, m, Q Masses Decay (log ft, Pxn/yp) Reactions (s, B(E2), C2S) QED tests in HCI Rare decays: GTGR, bxn/yp, cluster decay, SHE Extreme precision: e.g., crystal spectrometry Prototyping Ft values, Correlations (b-n,…), EDM Correlations (b-n, ...), EDM: Statistics + control systematic effects of setup Mössbauer, b-NMR, PAC, EC-SLI Systematic sample measurements SHE chemistry Mn, Fe, Ni, Cu, Zn b-NMR in proteins Radiopharmacy (prototyping) Radiotherapy (prototyping) Systematic production of Radiopharmaceuticals Dedicated radiotherapy center Ultra-high selectivity: LIST configuration Bohr-Weisskopf: A- and g-factors

I@M - Highlights

Multipurpose facility Fuel research Φtot = 0.5 to 1.1015 n/cm².s F = 1 to 5.1014 n/cm².s (ppm He/dpa ~ 10) in medium-large volumes Material research FFast = 1 to 5.1014 n/cm².s (En>1 MeV) in large volumes Fission GEN IV Fusion Multipurpose hYbrid Research Reactor for High-tech Applications High energy LINAC 600 MeV – 1 GeV Long irradiation time 50 to 100 MWth FFast = ~1015 n/cm².s (En>0.75 MeV) Fundamental research Waste Fth = 0.1 to 1.1014 n/cm².s (En<0.4 eV) Radio- isotopes Silicon doping Fth = 0.5 to 2.1015 n/cm².s (En<0.4 eV)

Production of space specific radioisotopes in MYRRHA thermal neutron flux-traps Core lay-out: In reflector positions Cooled by water In thermalized neutron field Transport by rabbit system Positions also usable for testing of materials in thermal field! => Both are possible in MYRRHA: Testing of materials/fuels in fast (core) field Testing of materials/fuels in thermalized (peripheral) field Target plates in IPS:

priority list projects European Context Knowledge Economy Energy Independence ESFRI European Strategic Forum for Research Infrastructure SET Plan European Strategic Energy Plan 27.11.2010 Confirmed on ESFRI priority list projects 15.11.2010 in ESNII (SNETP goals)

Belgian commitment: secured International consortium: under construction 2nd phase (11 y) others 576 M€ 960 M€ (2009) Consortium Belgium 324 M€ (36 M€/y x 9 y) Belgium 60 M€ (12 M€/y x 5 y)

management and investment structure The project schedule 2010-2014 Front End Engineering Design 2015 Tendering & Procurement 2016-2018 Construction of components & civil engineering 2019 On site assembly 2020-2022 Commissioning 2023 Progressive start-up 2024- Full exploitation Minimise technological risks Secure the licensing Secure a sound management and investment structure PDP preliminary dismantling plan PSAR preliminary safety assesment EIAR environmental impact assesment FEED (Front End Engineering Design) 2010-2014 Central Project Team Owner Consortium Group Owner Engineering Team

MYRRHA international network

International Members Consortium – Phase 1 As of early 2012 INVESTMENT PHASE International Members Consortium – Phase 1 As of early 2012 BE EU countries Asian country EU ROW SCK•CEN (on behalf of Belgian Federal Government) EU country Public foundation EU participation ROW participation Belgian Federal Ministry of Energy (50%) of Science Policy (50%) 40 % Major European partners A major Asian partner EU FP7 (RTD) / SET-Plan (Energy) (*) European Research Infrastructure Consortium «ERIC» (*) Contribution to investment capital (960 M€’09) Participation vehicle (Consortium members) Primary «investors» IPR management rules tbd

International Members Consortium - Phase 2 OPERATION PHASE International Members Consortium - Phase 2 Members of Consortium Individual research of a member of Consortium Collaborative research amongst members of Consortium - 3 years program commitment CLOSED/ SHARED INFORMATION for MoC Open User Facility Governments funding Criteria of research excellence Independant program access committee (PAC) Collaborative research - Distribution of information to participants Contract research….. Commercial services RI NTD Silicon ~25% OPEN INFORMATION SHARED INFORMATION for participants CLOSED «ERIC» (*) (*) European Research Infrastructure Consortium BENEFITS for Members of Consortium Board position to control overal operation Priority of access Potential benefit of low price (compensation profit from commercial revenues) Capacity transfer flexibility (rules tbd) SCK•CEN as qualified and licenced operator of the MYRRHA infrastructure under contractual arrangement with ERIC

ECR source & Injector Building MYRRHA: EXPERIMENTAL ACCELERATOR DRIVEN SYSTEM A pan-European, innovative and unique facility at Mol (BE) BR2 reactor (existing) Utilities buildings MYRRHA reactor building MYRRHA LINAC high energy tunnel ECR source & Injector Building

SCK•CEN in brief SCK•CEN is an internationally renowned research centre SCK•CEN’s innovative research is directed to the safe application of nuclear energy on both short and long term; SCK•CEN contributes in an important manner to non-power related society-relevant applications of nuclear energy; SCK•CEN emphasizes the need for fundamental knowledge, education and training: the SCK•CEN Academy for Nuclear Science and Technology; SCK•CEN has an innovative future-oriented project MYRRHA;

Conclusions MYRRHA As a Multipurpose Fast Spetrum irradiation facility selected by ESFRI, is responding to: The issue of addressing the nuclear waste legacy of present reactor technology through advance options (ADS, P&T) The SNETP need for a multipurpose research infrastructure expressed in its Strategic Research Agenda whatever the considered technology for Gen.IV systems The Objective of Belgium and SCK•CEN to maintain a high level expertise in the country in the nuclear safety, nuclear technology and nuclear competencies independently of the future of NE The objective of the European Commission to make available a series of relevant irradiations facilities for the fusion material research community towards the DEMO construction Secure society needs for RI for medical applications and Dopped-Si for renewable Energy

Q&A

Copyright © 2013 - SCKCEN SCK•CEN PLEASE NOTE! This presentation contains data, information and formats for dedicated use ONLY and may not be copied, distributed or cited without the explicit permission of the SCK•CEN. If this has been obtained, please reference it as a “personal communication. By courtesy of SCK•CEN”. SCK•CEN 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