Presentation is loading. Please wait.

Presentation is loading. Please wait.

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

Published byCharlotte Harris Modified over 9 years ago

Similar presentations

Presentation on theme: "A Roadmap to the realization of fusion energy Francesco Romanelli European Fusion Development Agreement EFDA Leader and JET Leader 17 May 2013 Acknoledgments:"— Presentation transcript:

1 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 www.efda.org

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

3 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

4 The Joint European Torus (JET)

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

6 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 ITER The key facility in the roadmap

7 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

8 Mission 1: Plasma regimes for a reactor Control plasma instabilities

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

10 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

11 2010 2020 20302040 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

12 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

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

14 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 2010 2020 20302040 2050

15 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

16 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 10000 times after 100 years No need for permanent waste repository

17 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) 250-350 o C 20cc 20dpa (Fe) 250-550 o C 70cc 20dpa (Fe) 250-550 o C 300cc DEMO Phase250dpa (Fe) 250-350 o C 20cc 50dpa (Fe) 250-550 o C 70cc 50dpa (Fe) 250-550 o C 300cc Reactor100dpa (Fe) 250-1200 o C 70cc 100dpa (Fe) 250-1200 o C 300cc

18 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 2010 2020 20302040 2050

19 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)

20 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 2010 2020 20302040 2050

21 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

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

23 Challenge 5: Deal with complexity

24 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

25 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 2010 2020 20302040 2050

26 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 2010 2020 20302040 2050

27 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 2010 2020 20302040 2050

28 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 2010 2020 20302040 2050

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

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

Similar presentations

Jerome Pamela PWI meeting, 31 October 2007 1 New Horizons for EFDA PWI meeting, October 2007 Jerome Pamela EFDA Leader.

Jerome Pamela PWI meeting, 31 October New Horizons for EFDA PWI meeting, October 2007 Jerome Pamela EFDA Leader.
Extension of IEA Implementing Agreement on Large Tokamak Facilities Presented to Committee on Energy Research Technologies October 18-19, 2005 Paris, France.

Extension of IEA Implementing Agreement on Large Tokamak Facilities Presented to Committee on Energy Research Technologies October 18-19, 2005 Paris, France.
1 Summary Slides on FNST Top-level Technical Issues and on FNSF objectives, requirements and R&D Presented at FNST Meeting, UCLA August 18-20, 2009 Mohamed.

1 Summary Slides on FNST Top-level Technical Issues and on FNSF objectives, requirements and R&D Presented at FNST Meeting, UCLA August 18-20, 2009 Mohamed.
PhD studies report: FUSION energy: basic principles, equipment and materials Birutė Bobrovaitė; Supervisor dr. Liudas Pranevičius.

PhD studies report: "FUSION energy: basic principles, equipment and materials" Birutė Bobrovaitė; Supervisor dr. Liudas Pranevičius.
Conceptual design of a demonstration reactor for electric power generation Y. Asaoka 1), R. Hiwatari 1), K. Okano 1), Y. Ogawa 2), H. Ise 3), Y. Nomoto.

Conceptual design of a demonstration reactor for electric power generation Y. Asaoka 1), R. Hiwatari 1), K. Okano 1), Y. Ogawa 2), H. Ise 3), Y. Nomoto.
Nuclear Energy University Programs MS-RC1 - Reactor Concepts RD&D August 10, 2011 Christopher Grandy Argonne National Laboratory.

Nuclear Energy University Programs MS-RC1 - Reactor Concepts RD&D August 10, 2011 Christopher Grandy Argonne National Laboratory.
EFDA Fusion Roadmap Status of implementation Francesco Romanelli EFDA Leader.

EFDA Fusion Roadmap Status of implementation Francesco Romanelli EFDA Leader.
Implications of Plasma-Material Interactions Dennis Whyte, MIT PSFC & PSI Science Center With contributions from Jeff Brooks (Purdue), Russ Doerner (UCSD),

Implications of Plasma-Material Interactions Dennis Whyte, MIT PSFC & PSI Science Center With contributions from Jeff Brooks (Purdue), Russ Doerner (UCSD),
The Path to Fusion Power Chris Llewellyn Smith Director UKAEA Culham Chairman Consultative Committee for Euratom on Fusion Chair ITER Council.

The Path to Fusion Power Chris Llewellyn Smith Director UKAEA Culham Chairman Consultative Committee for Euratom on Fusion Chair ITER Council.
Physics of fusion power Lecture 14: Anomalous transport / ITER.

Physics of fusion power Lecture 14: Anomalous transport / ITER.
FNSF Blanket Testing Mission and Strategy Summary of previous workshops 1 Conclusions Derived Primarily from Previous FNST Workshop, August 12-14, 2008.

FNSF Blanket Testing Mission and Strategy Summary of previous workshops 1 Conclusions Derived Primarily from Previous FNST Workshop, August 12-14, 2008.
The Tokamak тороидальная камера в магнитных катушках Invented in the 1950s Leading candidate for fusion energy production Startup Plasma heating –Ohmic.

The Tokamak "тороидальная камера в магнитных катушках" Invented in the 1950s Leading candidate for fusion energy production Startup Plasma heating –Ohmic.
Page 1 of 14 Reflections on the energy mission and goals of a fusion test reactor ARIES Design Brainstorming Workshop 24-25 April 2005 M. S. Tillack.

Page 1 of 14 Reflections on the energy mission and goals of a fusion test reactor ARIES Design Brainstorming Workshop April 2005 M. S. Tillack.
Burning Plasma Gap Between ITER and DEMO Dale Meade Fusion Innovation Research and Energy US-Japan Workshop Fusion Power Plants and Related Advanced Technologies.

Burning Plasma Gap Between ITER and DEMO Dale Meade Fusion Innovation Research and Energy US-Japan Workshop Fusion Power Plants and Related Advanced Technologies.
Overview of Advanced Design White Paper Farrokh Najmabadi Virtual Laboratory for Technology Meeting June 23, 1998 OFES Headquarters, Germantown.

Overview of Advanced Design White Paper Farrokh Najmabadi Virtual Laboratory for Technology Meeting June 23, 1998 OFES Headquarters, Germantown.
Role of ITER in Fusion Development Farrokh Najmabadi University of California, San Diego, La Jolla, CA FPA Annual Meeting September 27-28, 2006 Washington,

Role of ITER in Fusion Development Farrokh Najmabadi University of California, San Diego, La Jolla, CA FPA Annual Meeting September 27-28, 2006 Washington,
Y. ASAOKA, R. HIWATARI and K

Y. ASAOKA, R. HIWATARI and K
1 Lecture #24 Fusion ENGR 303I. 2 Outline Fusion →Definition →Atoms usually used Previous attempts at fusion Current attempts at fusion →International.

1 Lecture #24 Fusion ENGR 303I. 2 Outline Fusion →Definition →Atoms usually used Previous attempts at fusion Current attempts at fusion →International.
Nuclear Fusion Energy Rishi Gohil ChE 379: Energy Technology and Policy Dr. Thomas Edgar Fall 2007.

Nuclear Fusion Energy Rishi Gohil ChE 379: Energy Technology and Policy Dr. Thomas Edgar Fall 2007.
Indian Fusion Test Reactor

Indian Fusion Test Reactor

Similar presentations

Ads by Google