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A Roadmap to the realization of fusion energy
Francesco RomanelliEuropean Fusion Development AgreementEFDA Leader and JET Leader17 May 2013
Acknoledgments: P. Barabaschi,D. Borba, G. Federici, L. Horton, R. Neu, D. Stork, H. Zohm
Download at www.efda.org
Energy challenge for Europe
SustainabilitySecurity of supplyEconomic competitiveness
Fusion Energy
Unlimited and diffuse energy sourceNo greenhouse gasesIntrinsically safeEnvironmentally responsible
How to make fusion?
Reacting nuclei are charged they repel each other
Heat nuclei up to 200Million oC
Matter is in the plasma state
DT
nHe
Fusion power has been produced on JET
Fusion power has been produced on JETFusion 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 2050. Require DEMO construction in ~ 2030
Mission 1: Plasma regimes for a reactorDemonstrate a net energy gain
•Energy losses increase at most as the radius R of the device
•Fusion power increases as the volume (≈R3)
MAKE LARGER DEVICES
25 MW25 MW 16 MW16 MW
50 MW50 MW 500 MW500 MW
Mission 1: Plasma regimes for a reactorCompatibility between plasma and wall
materials
ITER
ASDEX U
JET
Tungsten foreseen for a reactor to minimize erosion
2010 2020 2030 2040 2050 2010 2020 2030 2040 2050
1. 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 exhaustBaseline strategy
W macrobrush:15 MW/m2 x 1000 cyclesCFC monoblock20 MW/m2 x 2000 cycles
Up to 30MW/m2 in ITER(60MW/m2 in a reactor ~ heat flux on the surface of the Sun!)
Divertor detachment
Mission 2: Heat and particle exhaustAlternative strategies
• Proof-of-principle on medium size experiments
• Assess reactor-relevance in parallel
Liquid-metals
Baseline strategy
Advanced configuration and materialsEuropean 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
2010 2020 2030 2040 2050 2010 2020 2030 2040 2050
Mission 3: Develop neutron resistant materials
Reduction of structural propertiesActivation
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 EUROFERSelected range of temperature (300/550oC)Tested in fission reactors up to 60 dpa
Advanced materials under examinationODS steels (650oC)High-Temperature Ferritic-Martensitic steels
Activation falls 10000 times after 100 yearsNo need for permanent waste repository
Mission 3: Develop neutron resistant materials
QUALIFICATION OF MATERIALSREQUIRES A DEDICATED 14MeV NEUTRON SOURCEPRODUCING THE RELEVANT NEUTRON SPECTRUM
LMH
Accelerator(125 mA x 2)
Test Cell
Beam shape:200 x 50 mm2 High (>20 dpa/y, 0.5 L)
Medium (>1 dpa/y, 6 L)Low (<1 dpa/y, > 8 L)
100 keV 5 MeV 9 14.5 26 40 MeV
HEBTSource
140 mA D+
LEBTRFQ
MEBT
RF Power System
Half Wave ResonatorSuperconducting Linac
Lithium Target25± 1 mm thick, 15 m/s
100x30 mm2
125mA x 1
Still to be optimised: 15 dpa – 20cm3
>2 dpa – 0.5LIFMIFEarly Neutron Source
Onset of 14MeV effects
Calibration of 14Mev effects
Full database for the full exposure
DEMO Phase1 20dpa (Fe)250-350oC 20cc
20dpa (Fe)250-550oC 70cc
20dpa (Fe)250-550oC 300cc
DEMO Phase2 50dpa (Fe)250-350oC 20cc
50dpa (Fe)250-550oC 70cc
50dpa (Fe)250-550oC 300cc
Reactor 100dpa (Fe)250-1200oC 70cc
100dpa (Fe)250-1200oC 300cc
Baseline strategy
Advanced configuration and materialsEuropean 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
2010 2020 2030 2040 2050 2010 2020 2030 2040 2050
Mission 4: Ensure tritium self-sufficiency
A 1.5GWe reactor uses ~0.5kg Tritium/day
Breedersolidliquid
Coolantwaterheliumself-cooled
MultiplierBePb
Efficient T extractionEfficient electricity generation (balance of plant)
Baseline strategy
Advanced configuration and materialsEuropean 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
2010 2020 2030 2040 2050 2010 2020 2030 2040 2050
Mission 5: Implementation of inherent fusion safety features in DEMO design
Temperature evolution in the most loaded FW regionwithout any active coolingFermi pile Fusion reactor
D
10m
Mission 6: DEMO design
Magnets
Vacuum Vessel
Remote Handling
Heating Systems
Tritium Cycle
Balance ofPlant
ITER
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 fusionexpected to be competitive with other sources(IEA Levelised Cost Approach)
Fusion
UK electricity costs(Royal Academy of Engineering)
D
10m
ITER
6m3m1.5mTCV
Baseline strategy
Advanced configuration and materialsEuropean 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 +EDA Construction Operation
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
2010 2020 2030 2040 2050 2010 2020 2030 2040 2050
Baseline strategy
Advanced configuration and materialsEuropean 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 +EDA Construction Operation
Fusion electricity
Steady state
Inductive
European Medium Size Tokamaks+ International Collaborators
JET
JT60-SA
DEMO decisionTargeted 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
2010 2020 2030 2040 2050 2010 2020 2030 2040 2050
Baseline strategy
Advanced configuration and materialsEuropean 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 +EDA Construction Operation
Fusion electricity
Steady state
Inductive
European Medium Size Tokamaks+ International Collaborators
JET
JT60-SA
DEMO decisionEnsure 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
2010 2020 2030 2040 2050 2010 2020 2030 2040 2050
Baseline strategy
Advanced configuration and materialsEuropean Medium Size Tokamaks +linear plasma + Divertor Tokamak Test Facility + International Collaborators Tokamaks
Stellarator optimization
Burning PlasmaStellarator
ITER Test blanket programme
Parallel Blanket Concepts
CFETR (CN) FNSF (US)
The Roadmap in a nutshell
Low capital cost and long term technologies
CDA +EDA Construction Operation
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
2010 2020 2030 2040 2050 2010 2020 2030 2040 2050