Controlled Fusion and Energy Yesterday, Today, Tomorrow E. Velikhov, FEC-21, Chengdu, October 16, 2006 Evgeny Velikhov Fusion before ITER. ITER DEMO Energy Demands and Fusion Opportunities HISTORY 1928 july 29 G.Gamov theory 1932 Sovjet Goverment official N.Bucharin offer to Gamov full electrical power of Moscow region to make fusion experiment. Gamov decline I.Tamm publish a Theoretical Fondations of Electricity with first theory of magnetic toroidal surfases 1950 I.Tamm,A.Saharov MTR 1956 I.Kurchatov Harwell lecture Fusion before ITER 1970-s Novosibirsk conference. Tokamak-3 (USSR) opens tokamak era. Plasma temperature T ~ 1 keV and confinement time ~ 0,02 s reached - Tokamak becomes the main device in magnetic fusion research 1968 ATOMIC ENERGY REVIEW 14 4 (1976) Special Item The Current State and Prospects for the Development of Controlled Thermonuclear Fusion E.P. Velikhov, Kurchatov Institute, USSR E.E. Kintner, DOE, USA Important milestones The production and understanding of reactor- level hydrogen plasmas in The production of substantial quantities of fusion thermal energy by 1982 devices capable of reaching these objectives: TFTR (USA), T-10M (USSR), JET (EU) and JT-60 (Japan) Next generation of experimental devices for magnetic confinement of plasmas will permit studies of reactor- relevant plasmas and development of systems needed for power reactors Demonstration of practical fusion power can be attained by the end of the century 5 In energy development fusion will take its place with breeder reactors and solar electric.The potential advantages of fusion reactors are great : 1.An effectively infinite supply of fuel at very low cost is available; 2.Fuel for fusion reactors is available from oceans to all countries and therefore cannot be intercepted by other nations; 5 6 3.Fusion reactors will be inherently safe with no possibility of nuclear runaway; 4.There are no chemical combustion products; 5.Fusion reactors pose no afterheat problem in the case of an accidental loss of coolant; 6.Because fusion reactors will not require weapons-grade nuclear materials, there will be no possibility of theft for purposes of blackmail or sabotage; 7.The safety of fusion reactors means that plants could be sited near electrical power load centers - perchaps in cities; 6 7 8.In priciple, fusion plants will produce a lower amount of radioactive byproducts with significantly shorter half-lives than do fission reactors; 9.When used in combination with fission reactors (probably in the first stage of nuclear power development)one fusion reactor breeding fissile material from depleted or natural uranium or thorium can fuel about ten LWRs or HTGRs;(Poul Rebu,2006) 10.In the case of economic or engineering difficulties with fuel element reprocessing, the hybrid fusion power reactor can burn 7 8 up the depleted or natural uranium with an energy output of the order of GW*d/t, one order of magnitude better than that of power reactors; 11.The fusion reactor as a high energy neutron source is a unique means for production and transmutation of elements; 12.The long neutron free path in materials permits the nuclear reaction zone to be separated from the energy release area.That, in principle, opens the way for high temperature heat and synthetic fuel production. 8 9 Plan - ITER(PEPR/ITR in in USSR) in 1985 DEMO in 2000 Reality - ITER : start, finish; DEMO in 2030? 9 Fusion before ITER ITER DEMO Energy Demands and Fusion Opportunities Soviet Union proposes to build a next generation tokamak experimental device on a collaborative basis The ITER Conceptual Design Activities began among the four ITER Parties EC, Japan, USA and Russia The Parties agreed jointly (and on the basis of equality) to produce a detailed, complete and fully integrated engineering design of ITER ITER Project Timescale The first ITER design has been completed. To reduce the cost the EDA phase was extended to July 2001 US withdrew from the project On the initiative of Russian Federation the ITER Explorations activities began Completion of the ITER EDA Canada joins the project Canada offers site for ITER construction Coordinated Technical Activities (CTA), International Tokamak Physics Activity (ITPA) and ITER Negotiations began. ITER Project Timescale The first ITER design has been completed. To reduce the cost the EDA phase was extended to July 2001 US withdrew from the project On the initiative of Russian Federation the ITER Explorations activities began Completion of the ITER EDA Canada joins the project Canada offers site for ITER construction Coordinated Technical Activities (CTA), International Tokamak Physics Activity (ITPA), and ITER Negotiations began Offers for ITER sites at Vandellos (Spain), Cadarache (France) and at Rokkasho-mura (Japan) 2002 ITER Project Timescale 2005 Broader approach Site selection (Cadarache, France) India joins ITER 2003The Transitional Arrangements for ITER started United States rejoins ITER Peoples Republic of China joins ITER The Republic of Korea joins ITER Canada withdrew from ITER project 2006 Director General and Principal Deputy Director General Nominees. Initialing in May (Brussels) the Agreement on the Establishment of the ITER International Energy Organization for the Joint Implementation of the ITER Project Expected time for signature of the ITER Agreement November 2006 ITER management structure and Parties dynamics 1988 2006 Management Advisory Committee Scientific and Technical Advisory Committee Director Joint Central Team EuropeJapanRussiaUSA ITER Council ITER Design and Technology Contributions CENTRAL SOLENOID MODEL COIL REMOTE MAINTENANCE OF DIVERTOR CASSETTE Attachment Tolerance 2 mm DIVERTOR CASSETTE Heat Flux >15 MW/m 2, CFC/W Height 4 m Width 3 m B max =7.8 T I max = 80kA 4 t Blanket Sector Attachment Tolerance 0.25 mm Double-Wall, Tolerance 5 mm HIP Joining Tech Size : 1.6 m x 0.93 m x 0.35 m REMOTE MAINTENANCE OF BLANKET BLANKET MODULE VACUUM VESSEL SECTOR TOROIDAL FIELD MODEL COIL Radius 3.5 m Height 2.8m B max =13 T W = 640 MJ 0.6 T/sec ITER Parameters Total fusion power 500 MW (700 MW) * Average 14 MeV neutron wall loading 0.57 MWm -2 (0.8 MW m -2 ) Plasma inductive burn time at 15 MA > 400 s Non-inductive burn time at 500 MW 3000 s Plasma major radius ( R ) and minor radius ( a ) 6.2/2.0 m Plasma current ( I p ) 15 MA (17 MA) * Vertical elongation at 95% flux surface/separatrix ( 95 ) 1.70/1.85 (1.85/2.0) ** Triangularity at 95% flux surface/separatrix ( 95 ) 0.33/0.48 (0.45/0.55) ** Toroidal field at 6.2 m radius ( B T ) 5.3 T Plasma volume 831 m 3 ITER Construction ITER Project Needs GRID Technology and Remote Participation The main reasons for the ITER project success The international collaboration Success of Large Tokamak and Stellarator Programmes (TFTR, JET, JT-60, DIII-D, TORE-SUPRA, T-15, W7-AS, LHD) in physics basis development Progress in tokamak technologies (Magnets, Heating&CD, MHD control) Broader Approach Fast growth of the energy demands in the world Fusion before ITER ITER DEMO Energy Demands and Fusion Opportunities I (MA)159 B /B max (T)5.3/ / /14.6 a (m) R (m) T i (0) (keV) q /nG /nG 0.850/751.0 H H98(y,2) * (10 -3 ) 1) * 2) NN f BS f NI 3) P fus (MW) P heat (MW) 5) W th (MJ) P rad,total (MW) 6) Q = P fus /P aux ParameterITER inductive ITER steady state Demo example steady state [5] f disruption ~0.1 (per pulse) ~0.1 (per pulse) 1 (per year) Comparison of ITER and DEMO design parameters ITER together with satellite experiments opens the DEMO phase Physics issues and their resolution (adapted from L. Smith C.) IssueTodays experiments ITERDemo* Power plant Energetic particle effects1366 Self heating and burn stability1346 Understanding confinement2244 Fuelling2356 Density limits2345 Tearing mode stability3356 Resistive wall mode stability3256 Power and particle exhaust1356 Edge localized modes3356 Disruption avoidance/mitigation2366 Steady-state operation1355 Divertor performance2366 Burning plasma (Q>10)-366 Power plant plasma performance1366 Diagnostics and neutrons1356 Key: 1 Will help to resolve the issue 2 May resolve the issue 3 Should resolve the issue 4 Confirmation of resolution needed 5 Solution is desirable 6 Solution is a requirement * Risk would be reduced and options expanded by operating several alternative Demo plants in parallel Divertor plates No ideal material The need to often replace the divertor by remote handling. For a given material, the erosion is proportional to the energy flux. At the same stress and temperature variations, the divertor plate lifetime varies as the square of the energy flux inverse, as the material thickness increases. For long operation at high power, there is no satisfactory solution for the divertor even for ITER. In my view, the divertor is the most critical component on the way to the reactor. Test beds at high power, are needed, but the real tests has to take place in reactors. Divertor plate erosion The power density is very high. On ITER, the total surface is less than 4 m 2. At Q = 10, 30 MW fall on the plates with 80% radiated, a mean power density of 8 MW/m 2, an upper limit for copper or CFCs. It is difficult to avoid surface melting and or evaporation in presence of ELMs. The sputtering induced by Hydrogen and impurities ions is also a basic problem. High Z material like W are less sensitive to sputtering but 100 times more dangerous for the plasma The eroded material will redeposit with Tritium Is a high density radiative divertor a solution with ELMs? The X point limiter We may take advantage of the H mode physics by installing a limiter in the vicinity of the X point rather than a standard divertor. The advantages are in a given machine: - Better plasma performances a larger plasma volume, a factor 1,3 in the case presented an increase of the plasma current by 1,2 an increase of the plasma pressure by 1,1 a higher fusion power by a factor 1,5 - Better technical solution a simpler technical solution with a larger wetted area an easier possibility to sweep and move the contact area X point limiters H mode plasma have been possible on JET with the X point pushed into the wall. such solutions would be beneficial for ITER and for a reactor A X point limiter on an ITER type plasma The Divertor physics Divertor is a possible solution for ITER Other approaches (lithium limiter, dust limiter) are to be tested European Fast Track Approach is the Basis for Fusion Development Additional efforts&activity: faster DEMO, FPP, Hybrid reactor, Divertor alternatives ITER Accompanying Programme (adapted from D. Campbell) ITER The transition to superconducting tokamaks happens to date. Russia plans to restart T-15 with divertor/limiter Swelling of different austenitic steels under irradiation Swelling (V/V), % Displacement damage dose, dpa Irradiation temperature of C Cr16-Ni15-Mo3-Nb + 20% Cr16-Ni15-Mo3-Nb-B + 20% Swelling of ferritic-martensitic (low activation) steels under irradiation Swelling (V/V), % Displacement damage dose, dpa Irradiation temperature of C Cr13-Mo2-Nb-V-B Relative dimensional changes of GR-280 graphite irradiated in test reactors at different temperatures. Perpendicular orientation. Thermal conductivity of C-C composites UAM-92-5D under irradiation Materials for Fusion -IFMIF -Fast neutron reactors material database -Modeling the spectrum effects Is this triad sufficient for choice? -May be, with reasonable risks Is the Component Test Facility possible before DEMO? -Open question! May be not. Basic physics challenges Burning plasma transport and stability First wall and divertor physics Stability control at high fusion power Steady state regimes Boundary plasma arrangement Technology challenges Simplicity Neutron compatibility Reliability/Availability Integration Steady State Operation Low cost Industrial manufacturing Divertor alternatives (lithium limiter/jets???) ????? DEMO era DEMO and Material development should be international WHY?? Fusion community needs integration of resources at this stage Both will be faster, this means cheaper. IAEA supervising the fusion development will be natural. 39 40 41 Fusion before ITER ITER DEMO Energy Demands and Fusion Opportunities Energy pressure Globalization is the dominating characteristic of our time, leads to intensive spread of the modern technologies around the world with accompanying it energy needs Energy problem one of the key problems of the mankind We face limitation of resources and energy resources in the first place Energy Problem A quarter of the Earth population does not still use electricity!!! 2 Energy market highlights Energy is a product for everyone living on the Earth 6 billion customers! International Energy Agency evaluates investments in Energy brunch as 16 trillion dollars within next 30 yeas. Russian investments ~trillion dollars The Energy Sector is global and requires huge efforts! 2 Energy pressure Mtoe 3862 Mtoe 1965 Distribution of people by their per capita energy consumption Mtoe The relation specific energy consumption in two groups of people with (large -qL) and (small -qS) calculated by two techniques. -average speed of rapprochement, -slow speed of rapprochement - fast speed of rapprochement The forecast of manufacture of power resources also three variants of growth of needs Energy production under forecast I - also that it means variants of rapprochement. Energy pressure - The energy consumption is leveling with time - Leveling of the energy consumption doesnt necessarily mean the leveling of welfare it rather indicates the growing capabilities of the developing countries to consume more energy (i.e. a technological leveling) - Present economic mechanisms promote active transfer of capital to the developing countries, the only alternative of assuring the welfare of the developed countries would be a new technological breakthrough, capable to provide their relative energy independence Conclusion -Success of ITER is the result of worldwide integration in magnetic fusion physics and technology. I believe that this approach under IAEA auspices will allow to have fusion reactors in the next future. -The physics, technology and political problems on this way are complex but solvable. - ITER history gives the way for DEMO and for starting the Fusion Power Plant --Fusion has good perspectives to become one of primary energy sources in this century. We should move faster and work harder to make controlled fusion practical!