Status of the MYRRHA project at the end of 2017 Visit GMF: Group of European Municipalities with Nuclear Facilities. Mol, April 12 th, 2018

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Status of the MYRRHA project at the end of 2017 Visit GMF: Group of European Municipalities with Nuclear Facilities Mol, April 12 th, 2018

Outline What is & why MYRRHA? Present status MYRRHA Accelerator Specific requirements MYRRHA Scientific case Phased implementation & high level planning Conclusion 2

Key technical objective of the MYRRHA-project: an Accelerator Driven System MYRRHA An Accelerator Driven System Demonstrate the ADS concept at pre-industrial scale Can operate in critical and sub-critical modes Demonstrate transmutation Fast neutron source multipurpose and flexible irradiation facility Target main reaction spallation output 2 10 17 n/s material LBE (coolant) Accelerator particles protons beam energy 600 MeV beam current 2.4 to 4 ma Reactor power 65 to 100 MW th k eff 0,95 spectrum fast coolant LBE Source: SCK CEN MYRRHA Project Team 3

Brief recent history of ADS activity in Europe 1993 C. Rubbia, energy amplifier (CERN) 1994 H. Aït Abderrahim & Y. Jongen, ADONIS (BE) 1995 M. Salvatores, MUSE experiments (FR) 1995 C. Rubbia et al., FEAT/TARC experiments (CERN) 1996 C. Rubbia et al., EA-80 ADS Demo joint programme ENEA, Ansaldo Nucleare, INFN (IT) 1998 H. Aït Abderrahim et al., MYRRHA (BE) 1999 B. Carluec & M. Salvatores et al., EFIT-Gas AREVA,-CEA (FR) 2001 C. Rubbia et al., TRADE ENEA-Casaccia (IT) 2001 A. Kievitskaya et al., YALINA experiments (Belarus) 2002 V. Shvetsov et al., SAD facility in DUBNA (JINR/Russia) 2007 H. Aït Abderrahim et al., GUINEVERE (BE/FR) 2010 H. Aït Abderrahim et al., MYRRHA in ESFRI & BE-Gov. Declaration support for contruction (BE) 2011 A. Zelinsky et al., Neutron Source based ADS at KIPT (Ukraine) 2015 ithec ADS Project at INR in Troitsk (CH/RU) Source: SCK CEN MYRRHA Project Team 4

Outline What is & why MYRRHA? Present status MYRRHA Accelerator Specific requirements MYRRHA Scientific case Phased implementation & high level planning Conclusion 5

Pool-type: MYRRHA rev. 1.6 at the End of 2014 Size reduction Po issue O 2 concentration control Optimisation requested Source: SCK CEN MYRRHA Project Team 6

Option 0-D: evolution of existing design with innovative heat exchangers Layout of main components Source: SCK CEN MYRRHA Project Team 7

MYRRHA reactor design update Four MYRRHA primary system design options investigated to reduce the dimension of the reactor vessel (& associated cost) Option Reactor type Description 0 Pool Updated rev. 1.6 Innovative IVFHM & double-walled PHX 1 Pool Reduced size Innovative IVFHM & double-walled PHX Option 0 is now the reference design under further optimisation 2 Loop Bottom loading Existing IVFHM concept & external doublewalled PHX 3 Loop Top loading Source: SCK CEN MYRRHA Project Team 8

MYRRHA linac: Design frozen since 2014 Source: SCK CEN MYRRHA Project Team 9

Outline What is & why MYRRHA? Present status MYRRHA Accelerator Specific requirements MYRRHA Scientific case Phased implementation & high level planning Conclusion 10

Specific requirements of MYRRHA Accelerator High power proton beam (up to 2.4 MW) Proton energy 600 MeV Beam current Repetition rate 0.1 to 4.0 ma CW, 250 Hz Beam duty cycle 10-4 to 1 Beam power stability Beam footprint on reactor window Beam footprint stability # of allowed beam trips on reactor longer than 3 sec # of allowed beam trips on reactor longer than 0.1 sec # of allowed beam trips on reactor shorter than 0.1 sec < ± 2% on a time scale of 100ms Circular 85mm < ± 10% on a time scale of 1s 10 maximum per 3-month operation period 100 maximum per day unlimited Extreme reliability level: MTBF > 250 hrs Source: SCK CEN MYRRHA Project Team 11

Accelerator components Ion source LEBT Chopper RFQ CH NC cavities Single spoke cryomodules Elliptical cryomodules Source: SCK CEN MYRRHA Project Team 12

Ion source LEBT - Chopper Source: SCK CEN MYRRHA Project Team 13

RFQ Radiofrequency quadrupole First accelerating structure 4--rod 30keV 1.5MeV 176.1MHz 4m long aluminium structure Stems: OFHC Copper &Thick copper plating Complex water cooling system Source: SCK CEN MYRRHA Project Team 14

CH room temperature cavities Second accelerating section 1.5MeV 17MeV 176.1MHz Stainless steel structures Thin copper plating Source: SCK CEN MYRRHA Project Team 15

Single spoke cavity cryomodules Source: SCK CEN MYRRHA Project Team 16

Single spoke cavity Source: SCK CEN MYRRHA Project Team 17

Elliptical cavity cryomodules Fourth and fifth accelerating section 100MeV 600MeV Superconducting RF structures 100 200MeV: double spoke or elliptical cavities (352.2 or 704.4MHz) 200 600MeV: elliptical cavities (704.4MHz) 2 cavity cryomodules: ~ 3m long 4 cavity cryomodules: ~ 8m long Source: SCK CEN MYRRHA Project Team 18

Outline What is & why MYRRHA? Present status MYRRHA Accelerator Specific requirements MYRRHA Scientific case Phased implementation & high level planning Conclusion 19

MYRRHA R&D applications portfolio SNF*/ Waste Fission GEN IV Multipurpose hybrid Research Reactor for High-tech Applications Fusion Fundamental research *SNF = Spent Nuclear Fuel Radio-isotopes SMR LFR Source: SCK CEN MYRRHA Project Team, MYRRHA Business Plan 20

Transmutation is the better solution for Spent Nuclear Fuel SNF 1000 transmutation of spent fuel spent fuel reprocessing no reprocessing ~300 year +10,000 year +300,000 year Natural Uranium 1 *SNF = Spent Nuclear Fuel Duration Reduction 1.000x Volume Reduction 100x Source: European Commission Strategy Paper on Partitioning & Transmutation (2005), SCK CEN MYRRHA Project Team 21

European Strategy for P&T (2005) with objective of possible industrialisation from 2030-35 EU P&T Strategy 2005: 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 : P&T building blocks Description Name & Location 1 Advanced Partitioning Demonstrate capability to process a sizable amount of spent fuel from commercial Light Water Reactors to separate plutonium, uranium and minor actinides Atalante (FR) 2 MA Fuel production Demonstrate the capability to fabricate at a semi-industrial level the dedicated fuel with MA needed to load in a dedicated transmuter JRC-ITU (EU) 3 Transmutation Design and construct one or more dedicated transmuters MYRRHA (BE) 4 MA Fuel Reprocessing Specific installation to process fuel unloaded from transmuter Not necessarily based on aqueous process original spent fuel unloaded from commercial power plants The European Commission contributes to the 4 building blocks and fosters the national programmes towards this strategy for demonstration at engineering level. Source: European Commission Strategy Paper on Partitioning & Transmutation (2005) 22

Three options for Minor Actinide transmutation Studied in ARCAS FP7 project EU is presently considering two approaches for transmutation: via FR or ADS FR heterogeneous FR homogeneous ADS Driver fuel Blanket with MA Fuel with MA Blanket Fuel with MA Core safety parameters limit the amount of MA that can be loaded in the critical core for transmutation, leading to transmutation rates of: FR = 2 to 4 kg/twh ADS = 35 kg/twh (based on a 400 MW th EFIT design) Source: SCK CEN MYRRHA Project Team, MYRRHA Business Plan 23

Even with completely different national NE policies European solution for HLW works with ADS Spent fuel A Reprocessing A Reprocessing B Pu + MA MA ADS fuel fabrication Pu + MA ADS fuel reprocessing ADS Spent fuel ADS GROUP A SHARED REGIONAL FACILITIES Advantages for A ADS shared with B ADS burn A s Pu& MA Smaller Fu-Cycle units & shared Pu MOX Fabrication UOX Fabrication Enriched U PWR MOX PWR UOX Spent fuel B GROUP B Scenario 1 objective: elimination of A s spent fuel by 2100 A = Countries Phasing Out, B = Countries Continuing Source: SCK CEN MYRRHA Project Team, MYRRHA Business Plan Advantages for B ADS shared with B ADS burn B s MA A s uses B s Pu (part) as resource in FR FR fleet not contam with MA s Smaller Fu-Cycle units & shared 24

MYRRHA R&D applications portfolio SNF*/ Waste Fission GEN IV Multipurpose hybrid Research Reactor for High-tech Applications Fusion Fundamental research *SNF = Spent Nuclear Fuel Radio-isotopes LSMFR** **LSMFR = Lead-cooled Small Modular Fast Reactor Source: SCK CEN MYRRHA Project Team, MYRRHA Business Plan 25

Unique infrastructure and experiments developed for materials research & qualification Mechanical properties in liquid metals Hotcell testing MYRRHA materials qualification Environmen t. Fatigue Irradiation in liquid metal Corrosion testing Source: SCK CEN MYRRHA Project Team 26

Cross cutting of the MYRRHA materials program Gen-II/III Materials testing Innovative materials development AFA, FeCrAl, ODS, MAXphases Myrrha materials expertise Gen-IV Structural materials testing & qualification Fusion Liquid metal testing, materials testing Source: SCK CEN MYRRHA Project Team, 27

Irradiation experiments chain Twin-ASTIR (BR2) Lexur II (BOR-60) FP6 EUROTRANS FP7 GETMAT LBE, PWR water, 1.5 2.5 dpa Irradiation experiments (MYRRHA) GenIV and SMR FP7 GETMAT LBE, Pb, 6 35 dpa Under development (BR2) Compatibility of materials and surface modifications with LBE&Pb under irradiation MYRRHA materials qualification Development and qualification of new materials and fuel Source: SCK CEN MYRRHA Project Team, 28

MYRRHA R&D applications portfolio SNF*/ Waste Fission GEN IV Multipurpose hybrid Research Reactor for High-tech Applications Fusion Fundamental research *SNF = Spent Nuclear Fuel Radio-isotopes SMR LFR Source: SCK CEN MYRRHA Project Team, MYRRHA Business Plan 29

MYRRHA in support of Fusion Materials Development 30

Technology R&D Structural Test Materials Blanket Modules Components SC Magnets Tritium Handling System Plasma Facing Components Remote Maintenance System Heating System Safety Plasma Physics R&D Confinement Impurity Control Stability Role of Material Test Facility Blanket tests in ITER ITER MTR/IFMIF DEMO Fusion Power Plants 31

DONES: DEMO-oriented neutron source Deployment to operation: 2025 best case scenario Task: qualify Early DEMO materials IFMIF: International Fusion Material Irradiation Facility Deployment: 2030 base case scenario Task: qualify DEMO materials DEMO construction 2040: Phase I IFMIF design: 2014-2020 Todays Roadmap for Fusion Materials SCK CEN Contributions today & tomorrow DONES ITER operation 2028-2035 MYRRHA-IMIFF (2034) IFMIF commissioning From 2030 2018-2030 MYRRHA-100 MeV (2024) BR2 (up to 2026) Usage of IMIFF to complement IFMIF Usage of MTRs 32

MYRRHA-IMIFF & MYRRHA Core irradiations for fusion material Estimated damage induced and irradiation conditions in existing facilities and DEMO, IFMIF and MYRRHA-IMIFF 33

MYRRHA R&D applications portfolio SNF*/ Waste Fission GEN IV Multipurpose hybrid Research Reactor for High-tech Applications Fusion Fundamental research *SNF = Spent Nuclear Fuel Radio-isotopes SMR LFR Source: SCK CEN MYRRHA Project Team, MYRRHA Business Plan 34

ISOL@MYRRHA Project ISOL@MYRRHA Feasibility Study (pre-conceptual design and scientific case) carried out within BriX-IAP6 (2007-2012) Technical & Scientific report submitted to NuPECC 2010 Technical Design of ISOL@MYRRHA included in the long-range plan of NuPECC Detailing the Design, updating the Scientific Case and building the Users Group through a series of topical workshops - BriX-IAP7 (2012-2017) Fundamental interactions (10/2011) Detailed decay spectroscopy (04/2012) RIB production & HP target stations (09/2013) jointly organized with: ISOLDE-CERN, Spiral2-GANIL, ARIEL-TRIUMF Medical applications of RIBs (11/2014) Laser spectroscopy and atomic physics Solid state and biology Belgian Consortium recently created Source: SCK CEN MYRRHA Project Team Aim: Coordinated RTD programme Joining a large European collaboration 35

ISOL@MYRRHA - Concept ECR 1+ Surface IS RILIS + liquid targets Source: SCK CEN MYRRHA Project Team 36

Physics Case ISOL@MYRRHA will prioritize experimental programmes which require of extended beam times with stable operation Experiments which hunt for very rare phenomena need high statistics need many time-consuming systematic measurements have inherent limited detection efficiency http://isolmyrrha.sckcen.be/~/media/files/isol/documents/isolmyrrhareport.pdf ISOL@MYRRHA Nuclear Phys. Atomic Phys. Condensed Matter Fundam. Int. &Biology Medical Applic. Source: SCK CEN MYRRHA Project Team 37

The way from protons and target material to the patient MYRRHA accelerator proton beam chemical purification of produced isotopes Isotopesproduction target MYRRHA Using a fraction of the proton-beam from MYRRHA on a high-power target Production of classical & innovative isotopes radiolabeling Injection to the patient Advances in nuclear medicine and modern health care Source: SCK CEN MYRRHA Project Team 38

Conclusion MYRRHA will place SCK CEN on unique position in the field of medicalisotopes production BR 2 Reactor-based isotopes Acceleratorbased isotopes MYRR HA Innovative ISOLbased isotopes Source: SCK CEN MYRRHA Project Team 39

Outline What is & why MYRRHA? Present status MYRRHA Accelerator Specific requirements MYRRHA Scientific case Phased implementation & high level planning Conclusion 40

MYRRHA s phased implementation strategy Benefits of phased approach: Reducing technical risk Spreading investment cost First R&D facility available in Mol end of 2024 Phase 1 100 MeV Phase 2 600 MeV Phase 3 Reactor Source:SCK CEN MYRRHA Project Team 41

Phased implementation plan MYRRHA Project (2018-2030) > Implementation High-Level overview Cut-off decision: Economic / Consortium / FANC-AFCN High level global planning of MYRRHA Project (2018-2030) 2010 2011 2012 2013 2014 2015 2016 2017 2018 2019 2020 2021 2022 2023 2024 2025 2026 2027 2028 2029 2030 2031 2032 2033 2034 Pre-Licensing Phase (Full MYRRHA view) Licensing Phase (Full MYRRHA view) Phase 1: Total Phase 1 - MINERVA: 100 MeV Accelerator + ISOL Prototyping, Tendering, and Construction Commission MINERVA Phase 1 - R&D: Supporting 600 MeV and Reactor MINERVA formal licensing Royal Decree Phase 2-600MeV : Total Phase 2-600 MeV Accelerator: Tendering, Construction, and Commissioning Phase 3 - Reactor: Total Phase 3 - Reactor: Commission Full MYRRHA: pre-licensing Full MYRRHA: formal licensing Full MYRRHA: follow-up regulator during construction FANC / AFCN license full MYRRHA Start Operation Phase 1: 18-24 Phase 2&3: 25-30 Source: SCK CEN MYRRHA Project Team 42

CapEx: MYRRHA Total investment budget (Summary) Phase 1 (2018-2024) EUR M* Phase 2 (2025-2030) EUR M* Total (2018-2030) EUR M* 375 375 1.274 1.274 31 31 21 21 13 12 104 299 79 101 1.649 52 312 1.649 18 52 183 49 44 167 835 1.076 936 1.295 219 73 By installation By activity 52 57 By installation 52 By activity 167 130 52 By installation 52 By activity Project Mgmt. Acc. 100-600 Mev Reactor Acc. 0-100 Mev Target Stations Licensing Integration engineering R&D PP&E** Nuclear fuel purchase Notes: *All numbers expressed in constant 2018 EUR **PP&E = Property, Plant & Equipment Source: SCK CEN MYRRHA Project Team, MYRRHA Business Plan 43

MYRRHA is embedded in an international R&D network Source: SCK CEN MYRRHA Project Team 44

Conclusions ADS is not anymore an Emerging Nuclear Energy System It has accomplished many impressive progresses in various fields, thanks to MYRRHA: Accelerator technology Pb and Pb-Bi technology HLM instrumentation (O 2 -meters, Flow meters, US-Visu, Sub-criticality monitoring, etc ) Material behavior in HLM (corrosion, erosion LME, etc ) ZPR experiments (FEAT/TARC, MUSE, YALINA, GUINEVERE, ) Large Scale HLM reactor mock-ups (ESCAPE, CLEAR-S) What is then the danger for this technology? Not to succeed to cross the valley of death for moving from R&D enthusiasm compensating small money to pre-industrial scale needing large money, rigorous industrial approach and severe safety and licensing judgement MYRRHA is aiming to cross the valley in a stepwise but breaking the ground in 2020 Source: SCK CEN MYRRHA Project Team 45

The valley of death for innovation 46

With a positive decision in 2017, we will break ground in 2020 47

Pioneering innovation in Europe Through a pan-european Reasearch Facility in Belgium 48

Copyright 2018 - 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 49