A Roadmap to the realization of fusion energy Francesco Romanelli European Fusion Development Agreement EFDA Leader and JET Leader 17 May 2013 Acknoledgments:

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Presentation transcript:

A Roadmap to the realization of fusion energy Francesco Romanelli European Fusion Development Agreement EFDA Leader and JET Leader 17 May 2013 Acknoledgments: P. Barabaschi,D. Borba, G. Federici, L. Horton, R. Neu, D. Stork, H. Zohm Download at

Energy challenge for Europe Sustainability Security of supply Economic competitiveness Fusion Energy Unlimited and diffuse energy source No greenhouse gases Intrinsically safe Environmentally responsible

How to make fusion? Reacting nuclei are charged  they repel each other Heat nuclei up to 200Million o C Matter is in the plasma state D T n He

The Joint European Torus (JET)

Fusion power has been produced on JET 25MW of auxiliary power to heat the plasma

The present roadmap Pragmatic approach to fusion energy. Focus the effort of European laboratories around 8 Missions Ensure innovation through early industrial involvement Exploit the opportunities arising from international collaborations The challenge of confining a hot plasma is achieved! What do we need to make a power plant? European Commission proposal for Horizon 2020 states the need of an ambitious yet realistic roadmap to fusion electricity by  Require DEMO construction in ~ 2030 ITER The key facility in the roadmap

Mission 1: Plasma regimes for a reactor Demonstrate a net energy gain Energy losses increase at most as the radius R of the device Fusion power increases as the volume (≈R 3 ) MAKE LARGER DEVICES 25 MW 16 MW 50 MW 500 MW

Mission 1: Plasma regimes for a reactor Control plasma instabilities

Mission 1: Plasma regimes for a reactor Control plasma instabilities TCV Lausanne

Mission 1: Plasma regimes for a reactor Compatibility between plasma and wall materials ITER ASDEX U JET Tungsten foreseen for a reactor to minimize erosion

Plasma operation 1.Heat exhaust 2.Materials 1.Tritium breeding 1.Safety 2.DEMO 3.Low cost 1.Stellarator The Roadmap in a nutshell Steady state Inductive European Medium Size Tokamaks + International Collaborators JET JT60-SA DEMO decision

Mission 2: Heat and particle exhaust Baseline strategy W macrobrush: 15 MW/m 2 x 1000 cycles CFC monoblock 20 MW/m 2 x 2000 cycles Up to 30MW/m 2 in ITER (60MW/m 2 in a reactor ~ heat flux on the surface of the Sun!) Divertor detachment

Mission 2: Heat and particle exhaust Alternative strategies Proof-of-principle on medium size experiments Assess reactor-relevance in parallel Liquid-metals

Baseline strategy Advanced configuration and materials European Medium Size Tokamaks +linear plasma + Divertor Tokamak Test Facility + International Collaborators Tokamaks The Roadmap in a nutshell Steady state Inductive European Medium Size Tokamaks + International Collaborators JET JT60-SA DEMO decision 1.Plasma operation 1.Heat exhaust 2.Materials 1.Tritium breeding 1.Safety 2.DEMO 3.Low cost 1.Stellarator

Mission 3: Develop neutron resistant materials Reduction of structural properties Activation Not a problem for ITER but must be solved for a reactor! 2 displacements per atom (dpa) in ITER 150 dpa in a fusion plant S. Dudarev D. Stork et al. Material Assessment Report

Mission 3: Develop neutron resistant materials Existing candidate: Low activation EUROFER Selected range of temperature (300/550 o C) Tested in fission reactors up to 60 dpa Advanced materials under examination ODS steels (650 o C) High-Temperature Ferritic-Martensitic steels Activation falls times after 100 years No need for permanent waste repository

Mission 3: Develop neutron resistant materials QUALIFICATION OF MATERIALS REQUIRES A DEDICATED 14MeV NEUTRON SOURCE PRODUCING THE RELEVANT NEUTRON SPECTRUM 100x30 mm 2 125mA x 1 Still to be optimised: 15 dpa – 20cm 3 >2 dpa – 0.5L IFMIF Early Neutron Source Onset of 14MeV effects Calibration of 14Mev effects Full database for the full exposure DEMO Phase120dpa (Fe) o C 20cc 20dpa (Fe) o C 70cc 20dpa (Fe) o C 300cc DEMO Phase250dpa (Fe) o C 20cc 50dpa (Fe) o C 70cc 50dpa (Fe) o C 300cc Reactor100dpa (Fe) o C 70cc 100dpa (Fe) o C 300cc

Baseline strategy Advanced configuration and materials European Medium Size Tokamaks +linear plasma + Divertor Tokamak Test Facility + International Collaborators Tokamaks The Roadmap in a nutshell Steady state Inductive European Medium Size Tokamaks + International Collaborators JET JT60-SA DEMO decision 1.Plasma operation 1.Heat exhaust 2.Materials 1.Tritium breeding 1.Safety 2.DEMO 3.Low cost 1.Stellarator

Mission 4: Ensure tritium self-sufficiency A 1.5GWe reactor uses ~0.5kg Tritium/day Breeder solid liquid Coolant water helium self-cooled Multiplier Be Pb Efficient T extraction Efficient electricity generation (balance of plant)

Baseline strategy Advanced configuration and materials European Medium Size Tokamaks +linear plasma + Divertor Tokamak Test Facility + International Collaborators Tokamaks ITER Test blanket programme Parallel Blanket Concepts CFETR (CN) FNSF (US) The Roadmap in a nutshell Steady state Inductive European Medium Size Tokamaks + International Collaborators JET JT60-SA DEMO decision 1.Plasma operation 1.Heat exhaust 2.Materials 1.Tritium breeding 1.Safety 2.DEMO 3.Low cost 1.Stellarator

Mission 5: Implementation of inherent fusion safety features in DEMO design Temperature evolution in the most loaded FW region without any active cooling Fermi pile Fusion reactor

D 10m Mission 6: DEMO design Magnets Vacuum Vessel Remote Handling Heating Systems Tritium Cycle Balance of Plant ITER

Challenge 5: Deal with complexity

Mission 7: Low cost of electricity ITER is a moderate extrapolation from JET (x2) The Power Plant (1.5GWe) expected to be a moderate extrapolation from ITER (x1-1.5) depending on the assumptions on physics and technology solutions (A=conservative; D=advanced) EFDA Power Plant Conceptual Study Cost of electricity from fusion expected to be competitive with other sources (IEA Levelised Cost Approach) FusionFusion UK electricity costs (Royal Academy of Engineering) D 10m ITER 6m3m 1.5m TCV

Baseline strategy Advanced configuration and materials European Medium Size Tokamaks +linear plasma + Divertor Tokamak Test Facility + International Collaborators Tokamaks ITER Test blanket programme Parallel Blanket Concepts CFETR (CN) FNSF (US) The Roadmap in a nutshell Low capital cost and long term technologies CDA +EDAConstructionOperation Fusion electricity Steady state Inductive European Medium Size Tokamaks + International Collaborators JET JT60-SA DEMO decision Primary safety boundary the vacuum vessel (ITER approach) Tritium management: define appropriate detritiation techniques and disposal routes Reduced activation features expected to be incorporated already for the first set of DEMO components. Primary safety boundary the vacuum vessel (ITER approach) Tritium management: define appropriate detritiation techniques and disposal routes Reduced activation features expected to be incorporated already for the first set of DEMO components. 1.Plasma operation 1.Heat exhaust 2.Materials 1.Tritium breeding 1.Safety 2.DEMO 3.Low cost 1.Stellarator

Baseline strategy Advanced configuration and materials European Medium Size Tokamaks +linear plasma + Divertor Tokamak Test Facility + International Collaborators Tokamaks ITER Test blanket programme Parallel Blanket Concepts CFETR (CN) FNSF (US) The Roadmap in a nutshell Low capital cost and long term technologies CDA +EDAConstructionOperation Fusion electricity Steady state Inductive European Medium Size Tokamaks + International Collaborators JET JT60-SA DEMO decision Targeted R&D on - Magnets (low-T supercond) - Heating systems - Remote Handling - Vacuum and pumping - Balance of Plant Targeted R&D on - Magnets (low-T supercond) - Heating systems - Remote Handling - Vacuum and pumping - Balance of Plant 1.Plasma operation 1.Heat exhaust 2.Materials 1.Tritium breeding 1.Safety 2.DEMO 3.Low cost 1.Stellarator

Baseline strategy Advanced configuration and materials European Medium Size Tokamaks +linear plasma + Divertor Tokamak Test Facility + International Collaborators Tokamaks ITER Test blanket programme Parallel Blanket Concepts CFETR (CN) FNSF (US) The Roadmap in a nutshell Low capital cost and long term technologies CDA +EDAConstructionOperation Fusion electricity Steady state Inductive European Medium Size Tokamaks + International Collaborators JET JT60-SA DEMO decision Ensure low capital cost of DEMO! Targeted R&D on - High-T supercond - Advanced cooling Ensure low capital cost of DEMO! Targeted R&D on - High-T supercond - Advanced cooling 1.Plasma operation 1.Heat exhaust 2.Materials 1.Tritium breeding 1.Safety 2.DEMO 3.Low cost 1.Stellarator

Baseline strategy Advanced configuration and materials European Medium Size Tokamaks +linear plasma + Divertor Tokamak Test Facility + International Collaborators Tokamaks Stellarator optimization Burning Plasma Stellarator ITER Test blanket programme Parallel Blanket Concepts CFETR (CN) FNSF (US) The Roadmap in a nutshell Low capital cost and long term technologies CDA +EDAConstructionOperation Fusion electricity Steady state Inductive European Medium Size Tokamaks + International Collaborators JET JT60-SA DEMO decision 1.Plasma operation 1.Heat exhaust 2.Materials 1.Tritium breeding 1.Safety 2.DEMO 3.Low cost 1.Stellarator

Conclusions The roadmap will be a living document, reviewed regularly in response to the physics, technology and budgetary developments.