Prospect for Attractive Fusion Power (Focus on tokamaks) Farrokh Najmabadi University of California San Diego Mini-Conference on Nuclear Renaissance 48th.

Slides:



Advertisements
Similar presentations
Role of Fission and Fusion Energy in a Carbon-Constrained World Farrokh Najmabadi Prof. of Electrical Engineering Director of Center for Energy Research.
Advertisements

Comments on Progress Toward and Opportunities for Attractive Magnetic Fusion Power Plants Farrokh Najmabadi FPA workshop Jan 23-25, 1999 Marina Del Rey,
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,
Overview of the ARIES “Pathways” Program Farrokh Najmabadi UC San Diego 8 th International Symposium on Fusion Nuclear Technology Heidelberg, Germany 01–
ARIES-AT: An Advanced Tokamak, Advanced Technology Fusion Power Plant Farrokh Najmabadi University of California, San Diego, La Jolla, CA, United States.
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:
Summary and Closing Remarks Farrokh Najmabadi University of California San Diego Presentation to: ARIES Program Peer Review August 18, 2000 UC San Diego.
ARIES-AT: Evolution of Vision for Advanced Tokamak Power Plants Farrokh Najmabadi University of California, San Diego, La Jolla, CA, United States of America.
Fusion Development Path: A Roll-Back Approach Based on Conceptual Power Plant Studies Farrokh Najmabadi UC San Diego Fusion Power Associates Annual Meeting.
Perspectives on Fusion Electric Power Plants Farrokh Najmabadi University of California, San Diego, La Jolla, CA FPA Annual Meeting December 13, 2004 Washington,
National Fusion Power Plant Studies Program Achievements and Recent Results Prepared for Bill Dove OFES Headquarters June, 1999.
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.
RECENT RESULTS FROM USA MAGNETIC FUSION POWER PLANTS Farrokh Najmabadi University of California, San Diego, La Jolla, CA, United States of America German.
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.
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.
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:
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.
Thoughts on Fusion Nuclear Technology Development and the Role of ITER TBM Farrokh Najmabadi Prof. of Electrical Engineering Director of Center for Energy.
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)
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,
Role of Fusion Energy in the 21st Century
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.
Progress in ARIES-ACT Study Farrokh Najmabadi UC San Diego Japan/US Workshop on Power Plant Studies and Related Advanced Technologies 8-9 March 2012 US.
Fusion: Bringing star power to earth Farrokh Najmabadi Prof. of Electrical Engineering Director of Center for Energy Research UC San Diego NES Grand Challenges.
Overview of the ARIES “Pathways” Program Farrokh Najmabadi UC San Diego US-Japan Workshop on Power Plants Study and Related Advanced Technologies with.
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.
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 “Pathways” Program Farrokh Najmabadi University of California San Diego ARIES brainstorming meeting UC San Diego April 3-4, 2007 Electronic copy:
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.
PERSISTENT SURVEILLANCE FOR PIPELINE PROTECTION AND THREAT INTERDICTION ARIES Pathways Study Kick-off Meeting Ken Schultz 3 April 2007 Determining the.
Assessment of Fusion Development Path: Initial Results of the ARIES “Pathways” Program Farrokh Najmabadi UC San Diego ANS 18 th Topical Meeting on the.
Advanced Design Activities in US Farrokh Najmabadi University of California, San Diego Japan/US Workshop on Fusion Power Plants & Related Technologies.
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
Improvements to power flow modeling in the ARIES system code
The European Power Plant Conceptual Study Overview
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
Advanced Design Activities in US
Presentation transcript:

Prospect for Attractive Fusion Power (Focus on tokamaks) Farrokh Najmabadi University of California San Diego Mini-Conference on Nuclear Renaissance 48th annual meeting of APS DDP October 31, 2006 Electronic copy: ARIES Web Site:

1)Do we have an attractive vision for the final product?

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

 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.

Reduced COE mainly due to advanced technology Approaching COE insensitive of power density Advanced Tokamak lead to attractive power plants 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)

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

 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

 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

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) 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!

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 Advanced Technologies is the main lever in reducing fusion power plant costs

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

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

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)

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

2) How to we get from ITER to an attractive final product

ITER Integration of fusion plasma with fusion technologies A 1 st of the kind Power Plant! “Fusion Power: Research and Development Requirements.” Division of Controlled Thermonuclear Research (AEC).

In the ITER area, we need to develop a 5,000 ft view

A holistic optimization approach should drive the development path. Traditional Approach: Ask each scientific area (i.e., plasma, blanket, …)  What are the remaining major R&D areas?  Which of the remaining major R&D areas can be explored in existing devices or simulation facilities (e.g., fission reactors)? What other major facilities are needed? Traditional Approach: Ask each scientific area (i.e., plasma, blanket, …)  What are the remaining major R&D areas?  Which of the remaining major R&D areas can be explored in existing devices or simulation facilities (e.g., fission reactors)? What other major facilities are needed? Holistic Approach: Fusion energy development should be guided by the requirements for an attractive fusion energy source  What are the remaining major R&D areas? What it the impact of this R&D on the attractiveness of the final product.  Which of the remaining major R&D areas can be explored in existing devices or simulation facilities (i.e., fission reactors)? What other major facilities are needed? Should we attempt to replicate power plant conditions in a scaled device or Optimize facility performance relative to scaled objectives Holistic Approach: Fusion energy development should be guided by the requirements for an attractive fusion energy source  What are the remaining major R&D areas? What it the impact of this R&D on the attractiveness of the final product.  Which of the remaining major R&D areas can be explored in existing devices or simulation facilities (i.e., fission reactors)? What other major facilities are needed? Should we attempt to replicate power plant conditions in a scaled device or Optimize facility performance relative to scaled objectives

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

Existing facilities fail to address essential features of a fusion energy source

ITER is a major step forward but there is a long road ahead. Present Experiments

Power plant features and not individual parameters should drive the development path  Absolute parameters  Dimensionless parameters

There is a need to examine fusion development scenarios in detail  We need to start planning for facilities and R&D needed between ITER and a power plant.  Metrics will be needed for cost/benefit/risk tradeoffs  An integrated, “holistic” approach, based on the requirements for an attractive fusion energy source, provides a path to an optimized development scenario and R&D prioritization.  Developing power-plant fusion technologies is the pace- setting element in developing fusion.  Fusion and advanced fission systems have similar R&D issues, we can leverage substantially on advanced fission effort (but we need to be at the table).  We need to start planning for facilities and R&D needed between ITER and a power plant.  Metrics will be needed for cost/benefit/risk tradeoffs  An integrated, “holistic” approach, based on the requirements for an attractive fusion energy source, provides a path to an optimized development scenario and R&D prioritization.  Developing power-plant fusion technologies is the pace- setting element in developing fusion.  Fusion and advanced fission systems have similar R&D issues, we can leverage substantially on advanced fission effort (but we need to be at the table).