RECENT RESULTS FROM USA MAGNETIC FUSION POWER PLANTS Farrokh Najmabadi University of California, San Diego, La Jolla, CA, United States of America German.

Slides:



Advertisements
Similar presentations
Comments on Progress Toward and Opportunities for Attractive Magnetic Fusion Power Plants Farrokh Najmabadi FPA workshop Jan 23-25, 1999 Marina Del Rey,
Advertisements

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.
Fusion Power Plants: Visions and Development Pathway Farrokh Najmabadi UC San Diego 15 th ICENES May 15 – 19, 2011 San Francisco, CA You can download a.
October 16-19, 2000 A. R. Raffray, et al., ARIES-AT Blanket and Divertor, ANS Top. Meet. On TOFE ARIES-AT Blanket and Divertor A. R. Raffray 1,
ARIES-AT: An Advanced Tokamak, Advanced Technology Fusion Power Plant Farrokh Najmabadi University of California, San Diego, La Jolla, CA, United States.
Overview of the ARIES Program Farrokh Najmabadi University of California San Diego Presentation to: ARIES Program Peer Review August 18, 2000 UC San Diego.
January 8-10, 2003/ARR 1 Plan for Engineering Study of ARIES-CS Presented by A. R. Raffray University of California, San Diego ARIES Meeting UCSD San.
Impact of Advanced Technologies on Fusion Power Plant Characteristics: The ARIES-AT Study Farrokh Najmabadi University of California, San Diego, La Jolla,
Overview of NSO and Advanced Design Studies Farrokh Najmabadi OFES Budget Meeting April 4-6, 2000 OFES Headquarters, Germantown Electronic copy:
ARIES-AT: Evolution of Vision for Advanced Tokamak Power Plants Farrokh Najmabadi University of California, San Diego, La Jolla, CA, United States of America.
Perspectives on Fusion Electric Power Plants Farrokh Najmabadi University of California, San Diego, La Jolla, CA FPA Annual Meeting December 13, 2004 Washington,
Physics Analysis for Equilibrium, Stability, and Divertors ARIES Power Plant Studies Charles Kessel, PPPL DOE Peer Review, UCSD August 17, 2000.
National Fusion Power Plant Studies Program Achievements and Recent Results Prepared for Bill Dove OFES Headquarters June, 1999.
Overview of the ARIES Fusion Power Plant Studies Farrokh Najmabadi IAEA Technical Committee Meeting on Fusion Power Plant Studies March 24-28, 1998 Culham,
National Fusion Power Plant Studies Program Achievements and Recent Results Farrokh Najmabadi University of California, San Diego FESAC Meeting March 4-5,
Towards Attractive Fusion Power Plants Farrokh Najmabadi University of California San Diego Presented at Korean National Fusion Research Center Daejon,
June 14-15, 2007/ARR 1 Trade-Off Studies and Engineering Input to System Code Presented by A. René Raffray University of California, San Diego With contribution.
March 16-17, 2000ARIES-AT Blanket Design and Power Conversion, US/Japan Workshop/ARR ARIES-AT Blanket Design and Power Conversion The ARIES Team Presented.
Optimization of Spherical Torus as Power Plants -- The ARIES-ST Study Farrokh Najmabadi and the ARIES Team University of California, San Diego ISFNT-5.
Characteristics of an Economically Attractive Fusion Power Plant Farrokh Najmabadi University of California San Diego Fusion: Energy Source for the Future?
August 17, 2000 ARIES: Fusion Power Core and Power Cycle Engineering/ARR 1 ARIES: Fusion Power Core and Power Cycle Engineering The ARIES Team Presented.
ARIES-AT: An Advanced Tokamak, Advanced Technology Fusion Power Plant Presented by Farrokh Najmabadi University of California, San Diego, La Jolla, CA,
Contributions of Burning Plasma Physics Experiment to Fusion Energy Goals Farrokh Najmabadi Dept. of Electrical & Computer Eng. And Center for Energy Research.
The ARIES Compact Stellarator Study: Introduction & Overview Farrokh Najmabadi and the ARIES Team UC San Diego ARIES-CS Review Meeting October 5, 2006.
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.
Overview of the ARIES Program Farrokh Najmabadi University of California San Diego Presentation to: ARIES Program Peer Review August 18, 2000 UC San Diego.
Impact of Liquid Wall on Fusion Systems Farrokh Najmabadi University of California, San Diego NRC Fusion Science Assessment Committee November 17, 1999.
Status of Advanced Design Studies and Overview of ARIES-AT Study Farrokh Najmabadi US/Japan Workshop on Fusion Power Plant Studies & Advanced Technologies.
Characteristics of Commercial Fusion Power Plants Results from ARIES-AT Study Farrokh Najmabadi Fusion Power Associates Annual Meeting & Symposium July.
Optimization of a Steady-State Tokamak-Based Power Plant Farrokh Najmabadi University of California, San Diego, La Jolla, CA IEA Workshop 59 “Shape and.
Prospect for Attractive Fusion Power (Focus on tokamaks) Farrokh Najmabadi University of California San Diego Mini-Conference on Nuclear Renaissance 48th.
Overview of ARIES Compact Stellarator Study Farrokh Najmabadi and the ARIES Team UC San Diego US/Japan Workshop on Power Plant Studies & Related Advanced.
Environmental, Safety, and Economics Studies of Magnetic Fusion, Including Power Plant Design Studies Robert W. Conn Farrokh Najmabadi University of California.
The Future Prospects of Fusion Power Plants Farrokh Najmabadi University of California San Diego MIT IAP January 10, 2006 Electronic copy:
Overview of the ARIES-CS Compact Stellarator Power Plant Study Farrokh Najmabadi and the ARIES Team UC San Diego Japan-US Workshop on Fusion Power Plants.
Overview of the ARIES-ST Study Farrokh Najmabadi University of California, San Diego Japan/US Workshop on Fusion Power Plants & Related Technologies with.
Physics Issues and Trade-offs in Magnetic Fusion Power Plants Farrokh Najmabadi University of California, San Diego, La Jolla, CA APS April 2002 Meeting.
Magnetic Fusion Power Plants Farrokh Najmabadi MFE-IFE Workshop Sept 14-16, 1998 Princeton Plasma Physics Laboratory.
Advanced Design Activities Farrokh Najmabadi Virtual Laboratory for Technology Meeting Dec. 10, 1998 VLT PAC Meeting, UCSD.
Highlights of ARIES-AT Study Farrokh Najmabadi For the ARIES Team VLT Conference call July 12, 2000 ARIES Web Site:
June19-21, 2000Finalizing the ARIES-AT Blanket and Divertor Designs, ARIES Project Meeting/ARR ARIES-AT Blanket and Divertor Design (The Final Stretch)
A design for the DCLL inboard blanket S. Smolentsev, M. Abdou, M. Dagher - UCLA S. Malang – Consultant, Germany 2d EU-US DCLL Workshop University of California,
Requirements and Designs for IFE and MFE First Wall and Blankets Farrokh Najmabadi UC San Diego 2nd Japan/US Workshop on Laser-driven Inertial Fusion Energy.
Role of ITER in Fusion Development Farrokh Najmabadi University of California, San Diego, La Jolla, CA FPA Annual Meeting September 27-28, 2006 Washington,
Contributions of Advanced Design Activities to Fusion Research Farrokh Najmabadi University of California San Diego Presentation to: VLT PAC Meeting February.
Prospects for Attractive Fusion Power Plants Farrokh Najmabadi University of California San Diego 18 th KAIF/KNS Workshop Seoul, Korea April 21, 2006 Electronic.
March 20-21, 2000ARIES-AT Blanket and Divertor Design, ARIES Project Meeting/ARR Status ARIES-AT Blanket and Divertor Design The ARIES Team Presented.
The Energy Challenge – Fusion Energy Farrokh Najmabadi Prof. of Electrical Engineering Director of Center for Energy Research UC San Diego November 21,
Magnetic Fusion Power Plants -- Tritium Systems and Requirements Farrokh Najmabadi, Director, Center for Energy Research University of California, San.
Magnetic Fusion Power Plants Farrokh Najmabadi, Director, Center for Energy Research Prof. of Electrical & Computer Engineering University of California,
Re-Examination of Visions for Tokamak Power Plants – The ARIES-ACT Study Farrokh Najmabadi Professor of Electrical & Computer Engineering Director, Center.
Fusion: Bringing star power to earth Farrokh Najmabadi Prof. of Electrical Engineering Director of Center for Energy Research UC San Diego NES Grand Challenges.
Page 1 of 11 An approach for the analysis of R&D needs and facilities for fusion energy ARIES “Next Step” Planning Meeting 3 April 2007 M. S. Tillack ?
October 27-28, 2004 HAPL meeting, PPPL 1 Thermal-Hydraulic Analysis of Ceramic Breeder Blanket and Plan for Future Effort A. René Raffray UCSD With contributions.
Magnetic Fusion Power Plants Farrokh Najmabadi, Director, Center for Energy Research Prof. of Electrical & Computer Engineering University of California,
Managed by UT-Battelle for the Department of Energy Stan Milora, ORNL Director Virtual Laboratory for Technology 20 th ANS Topical Meeting on the Technology.
San Diego Workshop, 11 September 2003 Results of the European Power Plant Conceptual Study Presented by Ian Cook on behalf of David Maisonnier (Project.
ARIES-AT Physics Overview presented by S.C. Jardin with input from C. Kessel, T. K. Mau, R. Miller, and the ARIES team US/Japan Workshop on Fusion Power.
Page 1 of 11 Progress developing an evaluation methodology for fusion R&D ARIES Project Meeting March 4, 2008 M. S. Tillack.
Compact Stellarator Approach to DEMO J.F. Lyon for the US stellarator community FESAC Subcommittee Aug. 7, 2007.
Characteristics of Transmutation Reactor Based on LAR Tokamak Neutron Source B.G. Hong Chonbuk National University.
PERSISTENT SURVEILLANCE FOR PIPELINE PROTECTION AND THREAT INTERDICTION ARIES Pathways Study Kick-off Meeting Ken Schultz 3 April 2007 Determining the.
Towards An Attractive Fusion Power Plant Farrokh Najmabadi Forum on Next Step Device April 27, May 1, 1998 U. Wisconsin, Madison, Wisconsin.
SOFE Mini-Course Fusion Power Plants Farrokh Najmabadi Prof. of Electrical Engineering Director of Center for Energy Research UC San Diego June 5, 2009.
EVOLUTION OF VISIONS FOR TOKAMAK FUSION POWER PLANTS
Fusion power: Visions and the Development Path in the ITER Era
Trade-Off Studies and Engineering Input to System Code
Farrokh Najmabadi University of California, San Diego,
Historical Perspectives and Pathways to an Attractive Power Plant
Farrokh Najmabadi Professor of Electrical & Computer Engineering
Presentation transcript:

RECENT RESULTS FROM USA MAGNETIC FUSION POWER PLANTS Farrokh Najmabadi University of California, San Diego, La Jolla, CA, United States of America German Nuclear Society Annual Meeting on Nuclear Technology May 2004, Düsseldorf, You can download a copy of this presentation from ARIES Web Site:

The ARIES Team Has Examined Several Magnetic Fusion Concept as Power Plants in the Past 15 Years 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 IFE chambers (2003) ARIES-CS Compact Stellarator Study (Current Research)

Analysis of Conceptual Fusion Power Plants Identifies Key R&D Issues and Provides a Vision for Fusion Research Scientific & Technical Achievements Periodic Input from Energy Industry Goals and Requirements 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

Analysis of Conceptual Fusion Power Plants Identifies Key R&D Issues and Provides a Vision for Fusion Research 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 Conceptual Design of Magnetic Fusion Power Systems Are Developed Based on a Reasonable Extrapolation of Physics & Technology  Plasma regimes of operation are optimized based on latest experimental achievements and theoretical predictions.  Engineering system is based on “evolution” of present-day technologies, i.e., they should be available at least in small samples now. Only learning-curve cost credits are assumed in costing the system components. Conceptual Design of Magnetic Fusion Power Systems Are Developed Based on a Reasonable Extrapolation of Physics & Technology  Plasma regimes of operation are optimized based on latest experimental achievements and theoretical predictions.  Engineering system is based on “evolution” of present-day technologies, i.e., they should be available at least in small samples now. Only learning-curve cost credits are assumed in costing the system components.

Analysis of Conceptual Fusion Power Plants Identifies Key R&D Issues and Provides a Vision for Fusion Research 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

Customer Requirements

Public Acceptance:  No public evacuation plan is required: total dose < 1 rem at site boundary;  Generated waste can be returned to environment or recycled in less than a few hundred years (not geological time-scale);  No disturbance of public’s day-to-day activities;  No exposure of workers to a higher risk than other power plants; Public Acceptance:  No public evacuation plan is required: total dose < 1 rem at site boundary;  Generated waste can be returned to environment or recycled in less than a few hundred years (not geological time-scale);  No disturbance of public’s day-to-day activities;  No exposure of workers to a higher risk than other power plants; Top-Level Requirements for Fusion Power Plants Was Developed in Consultation with US Industry  Economic Competitiveness: Above requirements must be achieved simultaneously and consistent with a competitive life-cycle cost of electricity. Reliable Power Source:  Closed tritium fuel cycle on site;  Ability to operate at partial load conditions (50% of full power);  Ability to maintain power core (avilability > 80%);  Ability to operate reliably with < 0.1 major unscheduled shut-down per year. Reliable Power Source:  Closed tritium fuel cycle on site;  Ability to operate at partial load conditions (50% of full power);  Ability to maintain power core (avilability > 80%);  Ability to operate reliably with < 0.1 major unscheduled shut-down per year.

Top-Level Requirements Translate into Directions for System Optimization Top –Level Requirements for Commercial Fusion Power  Have an economically competitive life-cycle cost of electricity: Low recirculating power; High power density; High thermal conversion efficiency; Less-expensive systems.  Gain Public acceptance by having excellent safety and environmental characteristics: Use low-activation and low toxicity materials and care in design.  Have operational reliability and high availability: Ease of maintenance, design margins, and extensive R&D.

Fusion Plasma

Portfolio of MFE Configurations Externally ControlledSelf Organized Example: Stellarator Confinement field generated by mainly external coils Toroidal field >> Poloidal field Large aspect ratio More stable, better confinement Example: Field-reversed Configuration Confinement field generated mainly by currents in the plasma Poloidal field >> Toroidal field Small aspect ratio Simpler geometry

Important Parameters of a Fusion Plasma  Fusion power density, P f ~  2 B T 4 and    (I/aB) High magnetic field Higher performance plasma (   )  Recirculating power is dominated by the power to drive and maintain plasma current. Maximize self-driven bootstrap current  Confinement is not a major issue for a power plant size plasma. Important Parameters of a Fusion Plasma  Fusion power density, P f ~  2 B T 4 and    (I/aB) High magnetic field Higher performance plasma (   )  Recirculating power is dominated by the power to drive and maintain plasma current. Maximize self-driven bootstrap current  Confinement is not a major issue for a power plant size plasma. Optimization involves trade-off among various parameters  Trade-off between bootstrap current fraction and   Advanced Tokamak Regime  Trade-off between vertical stability and plasma shape  Trade-off between plasma edge condition and plasma facing components capabilities,  …

Approaching COE insensitive of current drive 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 % (3.0) ARIES-RS 5.5 5% (4.8) ARIES-AT % (5.4)

Detailed Physics Modeling Has Been Performed for ARIES-AT High accuracy equilibria; Large ideal MHD database over profiles, shape and aspect ratio; RWM stable with wall/rotation or wall/feedback control; NTM stable with LHCD; Bootstrap current consistency using advanced bootstrap models; External current drive; Vertically stable and controllable with modest power (reactive); Rough kinetic profile consistency with RS /ITB experiments, as well GLF23 transport code; Modest core radiation with radiative SOL/divertor; Accessible fueling; No ripple losses; 0-D consistent startup;

Fusion Technologies

ARIES-AT Fusion Core

The ARIES-RS Utilizes An Efficient Superconducting Magnet Design TF Coil Design 4 grades of superconductor using Nb 3 Sn and NbTi; Structural Plates with grooves for winding only the conductor. TF Structure Caps and straps support loads without inter-coil structure; TF cross section is flattened from constant-tension shape to ease PF design.

Use of High-Temperature Superconductors Simplifies the Magnet Systems Inconel strip YBCO Superconductor Strip Packs (20 layers each) mm CeO 2 + YSZ insulating coating (on slot & between YBCO layers)  HTS does not offer significant superconducting property advantages over low temperature superconductors due to the low field and low overall current density in ARIES-AT  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  and potential significant cost advantages Because of ease of fabrication using advanced manufacturing techniques

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' ' 9' 10 6 T S Divertor LiPb Blanket Coolant He Divertor Coolant 11

ARIES-ST Features a High-Performance Ferritic Steel Blanket Typically, the coolant outlet temperature is limited to the max. operating temperature of structural material (550 o C for ferritic steels). By using a coolant/breeder (LiPb), cooling the structure by He gas, and SiC insulators, a coolant outlet temperature of 700 o C is achieved for ARIES-ST leading to 45% thermal conversion efficiency. OB Blanket thickness 1.35 m OB Shield thickness 0.42 m Overall TBR 1.1

 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%.

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

The divertor is part of the replacement module, and consists of 3 plates, coolant and vacuum manifolds, and the strongback support structure The divertor structures fulfill several essential functions: 1) Mechanical attachment of the plates; 2) Shielding of the magnets; 3) Coolant routing paths for the plates and inboard blanket;

Attractiveness: Evaluation Based on Customer Requirements

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

ARIES-AT is Competitive with Other Future Energy Sources EPRI Electric Supply Roadmap (1/99): Business as usual Impact of $100/ton Carbon Tax. AT 1000 (1 GWe) AT 1500 (1.5 GWe) Estimated range of COE (c/kWh) for 2020* * Data from Snowmass Energy Working Group Summary. Estimates from Energy Information Agency Annual Energy Outlook 1999 (No Carbon tax).

Radioactivity Levels in Fusion Power Plants Are Very Low and Decay Rapidly after Shutdown Low afterheat results in excellent safety characteristics Low specific activity leads to low-level waste that decays away in a few hundreds years. Low afterheat results in excellent safety characteristics Low specific activity leads to low-level waste that decays away in a few hundreds years. ARIES-RS: V Structure, Li Coolant; ARIES-ST: Ferritic Steel Structure, He coolant, LiPb Breeder; Designs with SiC composites will have even lower activation levels. After 100 years, only 10,000 Curies of radioactivity remain in the 585 tonne ARIES-RS fusion core.

Multi-Dimensional Neutronics Analysis was Performed to Calculate TBR, activities, & Heat Generation Profiles  Very low activation and afterheat Lead to excellent safety and environmental characteristics.  All components qualify for Class-C disposal under NRC and Fetter Limits. 90% of components qualify for Class-A waste.  On-line removal of Po and Hg from LiPb coolant greatly improves the safety aspect of the system and is relatively straight forward.

ARIES-AT Also Uses A Full-Sector Maintenance Scheme

Feasibility: Fusion Development Path

The development path to realize fusion as a practical energy source includes:  Demonstration of high performance, steady-state burning plasmas.  Fusion power technologies are a pace setting element of fusion development. Development of fusion power technologies requires: 1)Strong base program including testing of components in non- nuclear environment as well as fission reactors. 2)Material program including an intense neutron source to develop and qualify low-activation material. 3)A Component Test Facility for integration and test of power technologies in fusion environment.  Fusion power technologies are a pace setting element of fusion development. Development of fusion power technologies requires: 1)Strong base program including testing of components in non- nuclear environment as well as fission reactors. 2)Material program including an intense neutron source to develop and qualify low-activation material. 3)A Component Test Facility for integration and test of power technologies in fusion environment.

ITER-Based Development Path Tokamak physics ITER Base Plasma physics ST, stellarator, RFP, other ICCs Major Facilities Base Technologies 14-MeV neutron source Fusion power technologies Plasma support technologies Decision point DEMO Component Test Facility Theory & Simulation ICC ETRDEMO