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Towards Attractive Fusion Power Plants Farrokh Najmabadi University of California San Diego Presented at Korean National Fusion Research Center Daejon,

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Presentation on theme: "Towards Attractive Fusion Power Plants Farrokh Najmabadi University of California San Diego Presented at Korean National Fusion Research Center Daejon,"— Presentation transcript:

1 Towards Attractive Fusion Power Plants Farrokh Najmabadi University of California San Diego Presented at Korean National Fusion Research Center Daejon, Korea April 20, 2006 Electronic copy: http://aries.ucsd.edu/najmabadi/ ARIES Web Site: http:/aries.ucsd.edu/ARIES

2 The ARIES Team Has Examined Several Magnetic Fusion Concept as Power Plants in the Past 15 Years TITAN reversed-field pinch (1988) ARIES-I first-stability tokamak (1990) ARIES-III D- 3 He-fueled tokamak (1991) ARIES-II and -IV second-stability tokamaks (1992) Pulsar pulsed-plasma tokamak (1993) SPPS stellarator (1994) Starlite study (1995) (goals & technical requirements for power plants & Demo) ARIES-RS reversed-shear tokamak (1996) ARIES-ST spherical torus (1999) Fusion neutron source study (2000) ARIES-AT advanced technology and advanced tokamak (2000) ARIES-IFE assessment of Inertial Fusion chambers, targets, and drivers (2003) ARIES-CS compact stellarator (2006)

3 Framework: Assessment Based on Attractiveness & Feasibility Periodic Input from Energy Industry Goals and Requirements Scientific & Technical Achievements Evaluation Based on Customer Attributes Attractiveness Characterization of Critical Issues Feasibility Projections and Design Options Balanced Assessment of Attractiveness & Feasibility No: Redesign R&D Needs and Development Plan Yes

4 Elements of the Case for Fusion Power Were Developed through Interaction with Representatives of U.S. Electric Utilities and Energy Industry  Have an economically competitive life-cycle cost of electricity  Gain Public acceptance by having excellent safety and environmental characteristics No disturbance of public’s day-to-day activities No local or global atmospheric impact No need for evacuation plan No high-level waste Ease of licensing  Reliable, available, and stable as an electrical power source Have operational reliability and high availability Closed, on-site fuel cycle High fuel availability Capable of partial load operation Available in a range of unit sizes Fusion physics & technology Low-activation material

5 Framework: Assessment Based on Attractiveness & Feasibility Periodic Input from Energy Industry Goals and Requirements Scientific & Technical Achievements Evaluation Based on Customer Attributes Attractiveness Characterization of Critical Issues Feasibility Projections and Design Options Balanced Assessment of Attractiveness & Feasibility No: Redesign R&D Needs and Development Plan Yes

6  Our vision of a fusion system in 1980s was a large pulsed device. Non-inductive current drive is inefficient.  Some important achievements in 1980s: Experimental demonstration of bootstrap current; Development of ideal MHD codes that agreed with experimental results.  Development of steady-state power plant concepts (ARIES-I and SSTR) based on the trade-off of bootstrap current fraction and plasma  ARIES-I:  N = 2.9,  =2%, P cd =230 MW  Our vision of a fusion system in 1980s was a large pulsed device. Non-inductive current drive is inefficient.  Some important achievements in 1980s: Experimental demonstration of bootstrap current; Development of ideal MHD codes that agreed with experimental results.  Development of steady-state power plant concepts (ARIES-I and SSTR) based on the trade-off of bootstrap current fraction and plasma  ARIES-I:  N = 2.9,  =2%, P cd =230 MW A dramatic change occurred in 1990: Introduction of Advanced Tokamak Last decade: Reverse Shear Regime  Excellent match between bootstrap & equilibrium current profile at high   Requires wall stabilization (Resistive-wall modes).  Internal transport barrier.

7 Framework: Assessment Based on Attractiveness & Feasibility Periodic Input from Energy Industry Goals and Requirements Scientific & Technical Achievements Evaluation Based on Customer Attributes Attractiveness Characterization of Critical Issues Feasibility Projections and Design Options Balanced Assessment of Attractiveness & Feasibility No: Redesign R&D Needs and Development Plan Yes

8 Increase Power Density Directions for Improvement What we pay for,V FPC r  Power density, 1/V p r >  r ~  r <  Improvement “saturates” at ~5 MW/m 2 peak wall loading (for a 1GWe plant). A steady-state, first stability device with Nb 3 Sn technology has a power density about 1/3 of this goal. Big Win Little Gain Decrease Recirculating Power Fraction Improvement “saturates” about Q ~ 40. A steady-state, first stability device with Nb 3 Sn Tech. has a recirculating fraction about 1/2 of this goal. High-Field Magnets ARIES-I with 19 T at the coil (cryogenic). Advanced SSTR-2 with 21 T at the coil (HTS). High bootstrap, High  2 nd Stability: ARIES-II/IV Reverse-shear: ARIES-RS, ARIES-AT, A-SSRT2

9 Reduced COE mainly due to advanced technology Approaching COE insensitive of power density Evolution of ARIES Designs 1 st Stability, Nb 3 Sn Tech. ARIES-I’ Major radius (m)8.0   ) 2% (2.9) Peak field (T)16 Avg. Wall Load (MW/m 2 )1.5 Current-driver power (MW)237 Recirculating Power Fraction0.29 Thermal efficiency0.46 Cost of Electricity (c/kWh)10 Reverse Shear Option High-Field Option ARIES-I 6.75 2% (3.0) 19 2.5 202 0.28 0.49 8.2 ARIES-RS 5.5 5% (4.8) 16 4 81 0.17 0.46 7.5 ARIES-AT 5.2 9.2% (5.4) 11.5 3.3 36 0.14 0.59 5

10 ARIES-I Introduced SiC Composites as A High- Performance Structural Material for Fusion  Excellent safety & environmental characteristics (very low activation and very low afterheat).  High performance due to high strength at high temperatures (>1000 o C).  Large world-wide program in SiC:  New SiC composite fibers with proper stoichiometry and small O content.  New manufacturing techniques based on polymer infiltration or CVI result in much improved performance and cheaper components.  Recent results show composite thermal conductivity (under irradiation) close to 15 W/mK which was used for ARIES-I.

11 Continuity of ARIES research has led to the progressive refinement of research ARIES-I: SiC composite with solid breeders Advanced Rankine cycle ARIES-I: SiC composite with solid breeders Advanced Rankine cycle Starlite & ARIES-RS: Li-cooled vanadium Insulating coating Starlite & ARIES-RS: Li-cooled vanadium Insulating coating ARIES-ST: Dual-cooled ferritic steel with SiC inserts Advanced Brayton Cycle at  650 o C ARIES-ST: Dual-cooled ferritic steel with SiC inserts Advanced Brayton Cycle at  650 o C ARIES-AT: LiPb-cooled SiC composite Advanced Brayton cycle with  = 59% ARIES-AT: LiPb-cooled SiC composite Advanced Brayton cycle with  = 59% Many issues with solid breeders; Rankine cycle efficiency saturated at high temperature Max. coolant temperature limited by maximum structure temperature High efficiency with Brayton cycle at high temperature

12 Advanced Brayton Cycle Parameters Based on Present or Near Term Technology Evolved with Expert Input from General Atomics *  Key improvement is the development of cheap, high-efficiency recuperators. Recuperator Intercooler 1Intercooler 2 Compressor 1 Compressor 2 Compressor 3 Heat Rejection HX W net Turbine Blanket Intermediate HX 5' 1 2 2' 3 8 9 4 7' 9' 10 6 T S 1 2 3 4 5 67 8 9 Divertor LiPb Blanket Coolant He Divertor Coolant 11

13  Originally developed for ARIES-ST, further developed by EU (FZK).  Typically, the coolant outlet temperature is limited to the max. operating temperature of structural material (550 o C for ferritic steels).  A coolant outlet temperature of 700 o C is achieved by using a coolant/breeder (LiPb), cooling the structure by He gas, and SiC insulator lining PbLi channel for thermal and electrical insulation.  Originally developed for ARIES-ST, further developed by EU (FZK).  Typically, the coolant outlet temperature is limited to the max. operating temperature of structural material (550 o C for ferritic steels).  A coolant outlet temperature of 700 o C is achieved by using a coolant/breeder (LiPb), cooling the structure by He gas, and SiC insulator lining PbLi channel for thermal and electrical insulation. ARIES-ST Featured a High-Performance Ferritic Steel Blanket

14  Simple, low pressure design with SiC structure and LiPb coolant and breeder. Outboard blanket & first wall ARIES-AT 2 : SiC Composite Blankets  Simple manufacturing technique.  Very low afterheat.  Class C waste by a wide margin.  LiPb-cooled SiC composite divertor is capable of 5 MW/m 2 of heat load.  Innovative design leads to high LiPb outlet temperature (~1,100 o C) while keeping SiC structure temperature below 1,000 o C leading to a high thermal efficiency of ~ 60%.

15 Innovative Design Results in a LiPb Outlet Temperature of 1,100 o C While Keeping SiC Temperature Below 1,000 o C Two-pass PbLi flow, first pass to cool SiC f /SiC box second pass to superheat PbLi Bottom Top PbLi Outlet Temp. = 1100 °C Max. SiC/PbLi Interf. Temp. = 994 °C Max. SiC/SiC Temp. = 996°C PbLi Inlet Temp. = 764 °C

16 The ARIES-AT Utilizes An Efficient Superconducting Magnet Design  On-axis toroidal field:6 T  Peak field at TF coil:11.4 T  TF Structure: Caps and straps support loads without inter-coil structure;  On-axis toroidal field:6 T  Peak field at TF coil:11.4 T  TF Structure: Caps and straps support loads without inter-coil structure; Superconducting Material  Either LTC superconductor (Nb 3 Sn and NbTi) or HTC  Structural Plates with grooves for winding only the conductor. Superconducting Material  Either LTC superconductor (Nb 3 Sn and NbTi) or HTC  Structural Plates with grooves for winding only the conductor.

17 Use of High-Temperature Superconductors Simplifies the Magnet Systems  HTS does offer operational advantages: Higher temperature operation (even 77K), or dry magnets Wide tapes deposited directly on the structure (less chance of energy dissipating events) Reduced magnet protection concerns  HTS does offer operational advantages: Higher temperature operation (even 77K), or dry magnets Wide tapes deposited directly on the structure (less chance of energy dissipating events) Reduced magnet protection concerns Inconel strip YBCO Superconductor Strip Packs (20 layers each) 8.5 430 mm CeO 2 + YSZ insulating coating (on slot & between YBCO layers)  Epitaxial YBCO Inexpensive manufacturing would consist of layering HTS on structural shells with minimal winding!  Epitaxial YBCO Inexpensive manufacturing would consist of layering HTS on structural shells with minimal winding!

18 Modular sector maintenance enables high availability  Full sectors removed horizontally on rails  Transport through maintenance corridors to hot cells  Estimated maintenance time < 4 weeks  Full sectors removed horizontally on rails  Transport through maintenance corridors to hot cells  Estimated maintenance time < 4 weeks ARIES-AT elevation view

19 Framework: Assessment Based on Attractiveness & Feasibility Periodic Input from Energy Industry Goals and Requirements Scientific & Technical Achievements Evaluation Based on Customer Attributes Attractiveness Characterization of Critical Issues Feasibility Projections and Design Options Balanced Assessment of Attractiveness & Feasibility No: Redesign R&D Needs and Development Plan Yes

20 Our Vision of Magnetic Fusion Power Systems Has Improved Dramatically in the Last Decade, and Is Directly Tied to Advances in Fusion Science & Technology Estimated Cost of Electricity (c/kWh)Major radius (m) Approaching COE insensitive of power density High Thermal Efficiency High  is used to lower magnetic field

21 Radioactivity Levels in Fusion Power Plants Are Very Low and Decay Rapidly after Shutdown After 100 years, only 10,000 Curies of radioactivity remain in the 585 tonne ARIES-RS fusion core. After 100 years, only 10,000 Curies of radioactivity remain in the 585 tonne ARIES-RS fusion core.  SiC composites lead to a very low activation and afterheat.  All components of ARIES-AT qualify for Class-C disposal under NRC and Fetter Limits. 90% of components qualify for Class-A waste.  SiC composites lead to a very low activation and afterheat.  All components of ARIES-AT qualify for Class-C disposal under NRC and Fetter Limits. 90% of components qualify for Class-A waste. Ferritic Steel Vanadium

22 Fusion Core Is Segmented to Minimize the Rad-Waste  Only “blanket-1” and divertors are replaced every 5 years Blanket 1 (replaceable) Blanket 2 (lifetime) Shield (lifetime)

23 Generated radioactivity waste is reasonable  1270 m 3 of Waste is generated after 40 full-power year (FPY) of operation (~50 years) Coolant is reused in other power plants 29 m 3 every 4 years (component replacement) 993 m 3 at end of service  Equivalent to ~ 30 m 3 of waste per FPY Effective annual waste can be reduced by increasing plant service life.  1270 m 3 of Waste is generated after 40 full-power year (FPY) of operation (~50 years) Coolant is reused in other power plants 29 m 3 every 4 years (component replacement) 993 m 3 at end of service  Equivalent to ~ 30 m 3 of waste per FPY Effective annual waste can be reduced by increasing plant service life.  90% of waste qualifies for Class A disposal

24 Framework: Assessment Based on Attractiveness & Feasibility Periodic Input from Energy Industry Goals and Requirements Scientific & Technical Achievements Evaluation Based on Customer Attributes Attractiveness Characterization of Critical Issues Feasibility Projections and Design Options Balanced Assessment of Attractiveness & Feasibility No: Redesign R&D Needs and Development Plan Yes

25 Advances in plasma physics has led to a dramatic improvement in our vision of fusion systems  Attractive visions for tokamak exist.  The main question is to what extent the advanced tokamak modes can be achieved in a burning plasma (e.g., ITER): What is the achievable  N (macroscopic stability) Can the necessary pressure profiles realized in the presence of strong  heating (microturbulence & transport)  Attractive visions for tokamak exist.  The main question is to what extent the advanced tokamak modes can be achieved in a burning plasma (e.g., ITER): What is the achievable  N (macroscopic stability) Can the necessary pressure profiles realized in the presence of strong  heating (microturbulence & transport)  Pace of “Technology” research has been considerably slower than progress in plasma physics.  Advanced technologies have a dramatic impact on attractiveness of fusion. Considerable more technology R&D is needed.  Pace of “Technology” research has been considerably slower than progress in plasma physics.  Advanced technologies have a dramatic impact on attractiveness of fusion. Considerable more technology R&D is needed.

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