ARIES-ACT power plants
ARIES Pathways Study
ARIES-CS Compact stellarator power plant
ARIES-IFE Assessment of integrated IFE chambers
ARIES-AT Advanced technology, advanced tokamak power plant (2000)
Fusion neutron source study (2000)
ARIES-ST Spherical torus power plant (1999)
ARIES-RS Reversed-shear tokamak power plant (1996)
Starlite Goals and technical requirements for power plants and Demo
(1995)
Reports of ARIES Utility Advisory Committee (1993-1995)
SPPS Stellarator power plant (1994)
Pulsar Pulsed-tokamak power plant (1993)
ARIES-II and ARIES-IV Second-stability tokamak power plant (1992)
ARIES-III D-3He-fueled tokamak power plant
(1991)
ARIES-I First-stability tokamak power plant (1990)
TITAN Reversed-field pinch power plant (1988)
Special Topics
ARIES-ACT
Final Report:
The ARIES Advanced and Conservative Tokamak Power Plant Study
ARIES-ACT1 System Configuration, Assembly, and Maintenance
Design and Analysis of the ARIES-ACT1 Fusion Power Core
Physics Basis for An Advanced Physics and Advanced Technology
Tokamak Power Plant Configuration: ARIES-ACT1
Neutronics Characteristics and Shielding System for ARIES-ACT1 Power Plant
Plasma Heat-Flux Dispersal for ACT1 Divertor Configurations
Experimental Evaluation of the Thermal Hydraulics of Helium-Cooled Divertors
Thermomechanical Analysis for An All-Tungsten ARIES Divertor
ARIES-ACT1 Safety Design and Analysis
Activation and Environmental Aspects of ARIES-ACT1 Power Plant
ARIES-ACT2 DCLL Power Core Design and Engineering
Physics Basis for a Conservative Physics and Conservative Technology
Tokamak Power Plant: ARIES-ACT2
20th ANS Topical Meeting on the Technology of Fusion
Energy (TOFE 20), 27-30 August 2012, Nashville, TN
"Re-Examination of Visions for Tokamak Power Plants: ARIES-ACT Study"
"ARIES-ACT1 Power Core Engineering"
"Fracture in All-Tungsten Divertors for ARIES"
"The Evaluation of the Heat Loading from Steady, Transient, and
Off-Normal Conditions in ARIES Power Plants"
"Design Challenges and Activation Concerns for ARIES Vacuum Vessel"
"Overall Power Core Configuration and System Integration for
the ARIES-ACT Fusion Power Plant"
"MELCOR accident analysis for ARIES-ACT"
"State-of-the-Art 3-D Assessment of Elements Degrading TBR of ARIES ACT-SiC
Blanket"
"Vacuum Vessel Analysis and Design for the ARIES-ACT Fusion Power
Plant"
"An Experimental Study of the Effects of Thermal Conductivity
Ratio in Helium-Cooled Divertor Modules"
"Verification of Thermal Performance Predictions of Prototypical Multi-Jet
Impingement Helium-Cooled Divertor Module"
"Optimization of Pin-Fin Arrays for Helium-Cooled Finger-Type
Divertors"
19th ANS Topical Meeting on the Technology of Fusion
Energy (TOFE 19), 7-11 November 2010, Las Vegas, NV
"W-Based Alloys for Advanced Divertor Designs:
Options and Environmental Impact of State-of-the-Art Alloys"
"Experimental investigation of fin enhancement for gas-cooled divertor concepts"
"Optimization of the ARIES T-tube divertor concept"
"High Performance Divertor Target Concept for a Power Plant:
a Combination of Plate and Finger Concepts"
"Experimental and numerical investigation of thermal performance
of gas-cooled jet-impingement finger-type divertor concept"
"Experimental studies of the thermal performance of
gas-cooled plate-type divertors"
"Elastic-plastic analysis of transition joints for high
performance divertor target plate"
"Development of the lead lithium (DCLL) blanket concept
"Novel Solution for the Problem of Neutron Streaming Through
Inboard Assembly Gaps of ARIES Tokamak Power Plants"
"Innovative First Wall Concept Providing Additional Armor
at High Heat Flux Regions"
"Ratchetting Models for Fusion Component Design"
"Development of a Visualization Tool for the ARIES Systems Code"
"Activation and Radiation Damage Characteristics of W-Based
Divertor of ARIES Power Plants"
"Rigorous Evaluation of Biological Dose for Fusion Systems
and Comparison with Approximate Contact Dose Approach"
"Challenges of Fusion Power Plant Licensing: Differences
and Commonalities with Existing Systems"
Other Articles:
"Comparison of possible flow distribution systems for
PbLi self-cooled blankets with respect to MHD, fabrication and maintenance"
"Flow distribution systems for liquid metal cooled blankets"
"Alternative Design Options for a Dual-Cooled Liquid Metal Blanket for ARIES-ACT2 "
"ARIES Cost Account Documentation"
"Dynamically similar studies of the thermal performance of
helium-cooled finger-type divertors with and without fins"
"Three-Dimensional Evaluation of Tritium Breeding Ratio,
Nuclear Heating Distribution,
and Neutron Wall Loading Profile for ARIES-ACT LiPb/SiC Design"
"State-of-the-Art 3-D Assessment of Elements Degrading the TBR of the ARIES DCLL Blanket"
"Recent Improvements of the Helium-Cooled W-based Divertor for Fusion Power Plants"
"Development, Visualization, and Application of the ARIES Systems Code"
"Recent US Activities on Advanced He-Cooled W-Alloy
Divertor Concepts for Fusion Power Plants"
"Methodology for Scaling Fusion Power Plant Availability"
"An advanced computational algorithm for systems analysis of tokamak power plants"
"High Heat Flux Components - Readiness to Proceed from
Near Term Fusion Systems to Power Plants"
ARIES-Pathways
18th ANS Topical Meeting on the Technology of Fusion
Energy (TOFE 18), September 28 - October 2, 2008, San Francisco, CA
"Experimental and numerical investigation of prototypical
multi-jet impingement (HEMJ) helium-cooled divertor modules"
"Experimental and numerical investigation of the thermal
performance of the gas-cooled divertor plate concept"
"Thermal performance of a prototypical gas-cooled T-tube
divertor module with single-sided heating"
"The Back-End of Fusion Materials Cycle:
Recycling and Clearance, Avoiding Disposal"
"An advanced computational approach to system modeling of tokamak power plants"
"An Evaluation of Fusion Energy R&D Gaps using Technology Readiness Levels"
"Design Optimization of High-Performance Helium-Cooled Divertor Plate Concept"
Other Articles:
"Summary of the ARIES Town Meeting: Edge Plasma Physics and Plasma
Material Interactions in the Fusion Power Plant Regime"
"Transient Thermal and Stress Response of A Helium-Cooled Tungsten
Plate-Type Divertor"
"Three-Dimensional Source Models for Toroidal Fusion Energy Systems"
"Toward the Ultimate Goal of Tritium Self-Sufficiency:
Technical Issues and Requirements Imposed on ARIES Advanced Fusion Power Plants"
"Goals, Challenges, and Successes of Managing Fusion Active Materials"
"An Integrated Approach to the Back-end of the Fusion Materials Cycle"
"Recent Developments in Environmental Aspects of
D-3He Fueled Fusion Devices"
"The Feasibility of Recycling and Clearance of Active Materials from a
Fusion Power Plant"
"Nuclear Challenges and Progress in Designing Stellarator Power Plants"
"Recent Accomplishments and Future Directions in US Fusion
Safety & Environmental Program"
"Clearance Considerations for Slightly-Irradiated
Components of Fusion Power Plants"
"Evaluation of Disposal, Recycling, and Clearance
Scenarios for Managing ARIES Radwaste after Plant Decommissioning"
"Environmental Aspects of Recent Trend in Managing Fusion Radwaste:
Recycling and Clearance, Avoiding Disposal."
ARIES-CS
Final Report:
The final report was published as a special issue of
Fusion Science and Technology 54 (3), 2008.
See Journal articles below:
The ARIES-CS Compact Stellarator Fusion Power Plant
Physics Design for ARIES-CS
Systems Studies and Optimization of the ARIES-CS Power Plant
Engineering Design and Analysis of the ARIES-CS Power Plant
Designing ARIES-CS Compact Radial Build and Nuclear System:
Neutronics, Shielding, and Activation
Divertor Configuration and Heat Load Studies for the ARIES-CS Fusion Power Plant
ARIES-CS Maintenance System Definition and Analysis
Lester M. Waganer, Richard J. Peipert, Jr., Xueren R. Wang, Siegfried Malang, ARIES Team
ARIES-CS Magnet Conductor and Structure Evaluation
Safety Assessment of the ARIES Compact Stellarator Design
Thermal-Hydraulic Studies in Support of the ARIES-CS T-Tube Divertor Design
ARIES-CS Coil Structure Advanced Fabrication Approach
16th ANS Topical Meeting on the Technology of Fusion
Energy (TOFE 16), September 14-16 2004, Madison, Wisconsin
"Exploration of Compact Stellarators as Power Plants: Initial Results from
ARIES-CS Study,"
"Reactors with Stellarator Stability and Tokamak Transport,"
"Optimization of Stellarator Reactor Parameters,"
"Attractive Design Approaches for a Compact Stellarator Power,"
"Ceramic Breeder Blanket for ARIES-CS,"
"Benefits of Radial Build Minimization and Requirements Imposed on ARIES
Compact Stellarator Design,"
"Initial Activation Assessment for ARIES Compact power Plant,"
"Design Constraints for Liquid-Protected Divertors,"
"Maintenance Approaches for ARIES-CS Power Plant,"
"Three Dimensional Modeling of Complex Fusion Devices Using CAD-MCNPX Interface"
17th ANS Topical Meeting on the Technology of Fusion
Energy (TOFE 17), 13-15 November 2006, Albuquerque, NM
"Configuration Design and Maintenance Approach for the
ARIES-CS Stellarator Power Plant"
"High Performance Superconducting Options for ARIES Compact Stellarator"
"Integration of the Modular Dual Coolant Pb-17Li Blanket Concept in the
ARIES-CS Power Plant"
"ARIES-CS Loss of Coolant and Loss of Flow Accident Analyses"
18th ANS Topical Meeting on the Technology of Fusion
Energy (TOFE 18), September 28 - October 2, 2008, San Francisco, CA
"Three Dimensional Analysis of Radiation Streaming Through ARIES-CS
He-access Pipes"
Other Articles:
"Ideal MHD spectrum calculations for the ARIES-CS configuration"
"Engineering Challenges in Designing an Attractive
Compact Stellarator Power Plant"
"Overview of ARIES-CS In-vessel Components:
Integration of Nuclear, Economics, and Safety Constraints in Compact Stellarator"
"Modular Dual Coolant Pb-17Li Blanket Design for ARIES-CS
Compact Stellarator Power Plant"
ARIES-IFE
Final Report
Final report is published as a special issue of
Fusion Science & Technology 46 (2004)
Journal Articles:
"Operational Windows for Dry-Wall and Wetted-Wall IFE Chambers,"
"Dry-Wall Survival Under IFE Conditions,"
"Thermo Fluid Dynamics and Chamber Aerosol Behavior for the Thin Liquid Wall
Under IFE Cyclic Conditions,"
"An Investigation of the Fluid Dynamics Aspects of Thin Liquid Protection
Schemes for Inertial Fusion Energy Reactor Chambers,"
"Impact of Beam Transport Method on Chamber and Driver Design for Heavy Ion
Inertial Fusion Energy,"
"Design Requirements and Options for Final Focusing Superconducting Magnets
of Heavy-ion Drovers,"
"Feasibility of Target Material Recycling as Waste Management Alternative,"
16th ANS Topical Meeting on the Technology of Fusion
Energy (TOFE 16), September 14-16 2004, Madison, Wisconsin
"ARIES-IFE Assessment of Operational Windows for IFE Power Plants,"
"An Overview of Georgia Tech Studies on the Fluid Dynamics Aspects of Liquid
Protection Schemes for Fusion Reactors,"
"Impact of Boundary-Layer Cutting and Flow Conditioning on Free-Surface
Behavior in Turbulent Liquid Sheets,"
"Flow Conditioning Design in Thick-Liquid Protection,"
"Views on Neutronics and Activation Issues Facing Liquid-Protected IFE Chambers,"
"Recycling issues facing target and RTL materials of inertial fusion designs,"
2nd IAEA Technical Meeting on Physics and Technology of IFE Targets and Chambers, San Diego CA, 7-12 April 2002
Fluid Dynamic Aspects of the Porous Wetted Wall Protection
Scheme for IFE Reactors,
Experimental Studies of High-Speed Liquid Films
on Downward-Facing Surfaces for IFE Wet Wall Concepts,
6th Int. Symp. on Fusion Nuclear Technology,
San Diego CA, 7-12 April 2002
Target Activation and Radiological Response of ARIES-IFE Dry Wall
Chamber,
Int. Symp. on Inertial Fusion Science and Applications, IFSA-2001, Kyoto,
Japan, Sept. 11-14, 2001
"Assessment of Chamber Concepts for Inertial Fusion Energy Power Plants --
The ARIES-IFE Study,"
"Dry Chamber Wall Thermo-mechanical Behavior and Lifetime under IFE Cyclic
Energy Deposition,"
"Damage Threats and Response of Final Optics for Laser-Fusion Power Plants,"
"Thermal Control Techniques for Improved DT Layering of Indirect Drive IFE
Targets,"
21st Symposium on Fusion Technology, Madrid Spain,
September 2000
"Advances in Inertial Confinement Fusion for Energy Production,"
14th ANS Topical Meeting on Technology of Fusion Energy, October 15-19, 2000,
Park City Utah
"ARIES Inertial Fusion Chamber Assessment,"
"An Engineering Test Facility for Heavy Ion Fusion - Options and Scaling,"
"Design of an Inertial Fusion Energy Target Tracking and Position Prediction
System,"
"Preliminary Safety Assessment for an IFE Target Fabrication Facility,"
"Concepts for Fabrication of Targets for a Heavy Ion Driven
Inertial Fusion Energy Plant,"
13th International Symposium on Heavy Ion Inertial Fusion, San Diego CA, March
13-17, 2000
"Selection of IFE target materials from a safety and environmental
perspective," (preprint)
Reports
"Multipole Magnets Using Monolithic High Temperature
Superconductor Materials: I. Quadrupoles,"
"Activation of Target Coatings/Hohlraums and Influence
on Waste Management of IFE Chambers,"
Top of the page.
ARIES-AT
Final Report:
Final report has been published as a speical issue of
Fusion Eng. & Des. (2006).
Journal Articles (Final Report):
"Overview of the ARIES-AT Advanced Tokamak, Advanced Technology Power Plant
Study,"
F. Najmabadi et al.,
"Physics Basis for an Advanced Tokamak Power Plant,"
"Plasma Profile and Shape Optimization for the Advanced Tokamak
Power Platt, ARIES-AT"
"Advanced power core system for the ARIES-AT power plant,"
"ARIES-AT Nuclear Analysis and Shield Design,"
"ARIES-ST Safety Design and Analysis,"
"ARIES-AT Magnet Systems ,"
"ARIES-AT Maintenance System Definitions and Analysis,"
Journal Articles (Other):
"Design and Material Issues for High Performance
SiCf/SiC-Based Power Cores,"
"Options for the Use of High Temperature Superconductor in Tokamak Fusion
Reactor Designs,"
18th IAEA International Conference on Fusion Energy, Sorrento,
Italy, Oct. 2000
A-94. "ARIES-AT: An Advanced Tokamak, Advanced Technology Fusion Power
Plant,"
14th ANS Topical Meeting on Technology of Fusion Energy, Oct. 2000,
Park City Utah
"Impact of Advanced Technologies on Fusion Power Plant Characteristics --
The ARIES-AT Study,"
"ARIES-AT Blanket and Divertor,"
"An Assessment of the Brayton Cycle for High Performance Power
Plant,"
"Systems Context of the ARIES-AT Conceptual Fusion Power Plant,"
"Comparing Maintenance Approaches for Tokamak Fusion Power Plants,"
"Safety and Environmental Results for the ARIES-AT Design,"
"Nuclear Performance Assessment for ARIES-AT Power Plant,"
"Clearance Issues for Advanced Fusion Power Plants,"
"Activation, Decay Heat, and Waste Disposal Analyses for ARIES-AT Power
Plant,"
"Loss of Coolant and Loss of Flow Accident Analyses for ARIES-AT Power
Plant,"
"Flibe Assessments,"
21st Symposium on Fusion Technology, September 2000, Madrid Spain
"High Performance Blanket for ARIES-AT Power Plant,"
18th IEEE Symposium on Fusion Engineering, Oct. 24-28, 1999, Albuquerque, NM
"SiC/SiC Composite for an Advanced Fusion Power Plant Blanket"
"Options for the Use of High Temperature Superconductor in Tokamak Fusion
Reactor Designs,"
5th International Symposium on Fusion Nuclear
Technology, Rome, Italy, Sep. 1999
"Nuclear Issues and Analysis for ARIES Spherical and Advanced
Tokamaks,"
Top of the page.
ARIES-ST
ARIES Neutron Source Study
ARIES-RS
STARLITE
SPPS
PULSAR
ARIES-4
ARIES-3
ARIES-1
TITAN
Speical Topics
Final Report:
Final report will be published as a speical issue of
Fusion Eng. & Des. (2003).
(Click here for
Reprints)
Journal Articles:
"Blanket System Selection for the ARIES-ST,"
D. K. Zse, Mark Tillack, and Laila El-Guebaly
Fusion Engineering and Design 48 371-378 (2000).
17th IAEA International Conference on Fusion Energy, Yokohama, Japan, 1998.
"The ARIES-ST Study: Assessment of the Spherical Tokamak Concept as Fusion
Power Plants,"
F. Najmabadi, S. Jardin, M. Tillack, R. Miller, T. K. Mau, R. Stambaugh,
D. Steiner, L. Waganer, and the ARIES Team
Proc. of 17th
IAEA International Conference on Fusion Energy, (Yokohama, Japan,
Sept. 1998).
18th IEEE Symposium on Fusion Engineering, Oct. 24-28, 1999, Albuquerque, NM
"Innovative, Ultra-Low Cost Fabrication Methods,"
L. M. Waganer,
"The Toroidal Field Coil Design for ARIES-ST,"
W. Reiersen, F. Dahlgren, H-M. Fan, C. Neumeyer, and I. Zatz,
"Configuration and Maintenance of the ARIES-ST Power Plant,"
X. R. Wang, M. S. Tillack, F. Najmabadi,
S. Malang and the ARIES Team
"Physics Basis for the ARIES-ST Power Plant,"
T. K. Mau, S. C. Jardin, C. E. Kessel, J. E. Menard and the ARIES Team,
"Design-Point Finalization for the ARIES-ST Power Plant,"
R. L. Miller and the ARIES Team,
5th International Symposium on Fusion Nuclear
Technology, Septempber 19-24, 1999, Rome
"ARIES-ST Breeding Blanket Design and Analysis,"
M. S. Tillack, X. R. Wang, J. Pulsifer, S. Malang, D. K. Sze, and the ARIES
Team
Proc. of 5th International Symposium on Fusion Nuclear
Technology,ISFNT-5, Sept. 19-24, 1999, Rome
Fusion Engineering and Design, 49-50 689-695 (2000).
"ARIES-ST Plasma-Facing Component Design and Analysis,"
M. S. Tillack, X. R. Wang, J. Pulsifer, I. Sviatoslavsky, and the ARIES
Team
Proc. of 5th International Symposium on Fusion Nuclear
Technology,ISFNT-5, Sept. 19-24, 1999, Rome
Fusion Engineering and Design, 49-50 363-369 (2000).
"Nuclear Issues and Analysis for ARIES Spherical and Advanced
Tokamaks,"
L. A. El-Guebaly and the ARIES Team
Proc. of 5th International Symposium on Fusion Nuclear
Technology,ISFNT-5, Sept. 19-24, 1999, Rome
Fusion Engineering and Design, 51-52 325-330 (2000).
13th ANS Topical Meeting on the Technology of Fusion Energy, June 7-11, 1998,
Nashville, TN
"Need for Inboard Shield to Protect the Center Post of ST Power
Plants,"
L.A. El-Guebaly, H.Y. Khater and the ARIES Team
"Three-Dimensional Neutronics Study for ARIES-ST Power Plant,"
L.A. El-Guebaly and the ARIES Team
"Loss of Coolant Accident (LOCA) Analysis of the ARIES-ST Design,"
E.A. Mogahed and the ARIES Team
"Overview of the Spherical Tokamak Power Plant Study: ARIES-ST,"
(Electronic copy is not avilable)
R. L. Miller and the ARIES Team
"The ARIES-ST Blanket Design,"
(Electronic copy is not avilable)
D. K. Sze, M. S. Tillack, L. El-Guebaly and S. Malang
17th IEEE Symposium on Fusion Engineering, Oct. 6-9, 1997, San Diego, CA
"The ARIES Spherical Tokamak Power Plant Study,"
(Electronic copy is not avilable)
F. Najmabadi
"High-Performance PbLi Blanket,"
M. S. Tillack, S. Malang and the ARIES Team
"Plasma Physics Basis and Operations of the ARIES-ST Tokamak Power Plant,"
T. K. Mau, S. C. Jardin, J. Menard, R. L. Miller, R. D. Stambaugh
"A Comparative Assessment of Centerpost Design Options for
ARIES-ST,"
W. Reiersen, F. Dahlgren, P. Heitzenroeder, P. Bonanos, C. Neumeyer,
D. Steiner, L. Bromberg
"Design-Point Determination for the Commercial Spherical Tokamak,
ARIES-ST,"
(Electronic copy is not avilable)
R. L. Miller and the ARIES Team
"Configuration and Maintenance Options for Low Aspect Ratio Tokamaks,"
X. R. Wang, F. Najmabadi, M. S. Tillack
"Superconducting Bus Bar for Spherical Torus Reactors,"
(Electronic copy is not avilable)
L. Bromberg, M. Sidorov
12th Top. Conf. on Radio Frequency Power in Plasmas, Savannah, GA (1997)
"RF Curent Drive Modeling for Spherical Torus Plasmas,"
(Electronic copy is not avilable)
T.K. Mau and S.C. Chiu
Final Report:
Final report was published as a speical issue of
Fusion Eng. & Des. 38 (1997).
See Journal articles below:
Journal Articles:
"Overview of the ARIES-RS Reversed-Shear Tokamak Power Plant Study,"
F. Najmabadi and the ARIES Team,
Fusion Eng. & Des. 38 (1997) 3-25.
(tex)
"Physics Basis for a Reversed-Shear Tokamak Power Plant,"
S. C. Jardin, C. E. Kessel, C. G. Bathke, D. A. Ehst,
T. K. Mau, F. Najmabadi, and T. W. Petrie, and the ARIES Team
Fusion Eng. & Des. 38 (1997) 27-57.
"Systems Analysis in Support of the Selection of the ARIES-RS Design Point,"
C. G. Bathke and the ARIES Team
Fusion Eng. & Des. 38 (1997) 59-86.
"Configuration and Engineering Design of the ARIES-RS Tokamak Power Plant,"
M. S. Tillack, S. Malang, L. Waganer, X. R. Wang, D. K. Sze, L. El-Guebaly,
C. P. C. Wong, J. A. Crowell, T. K. Mau, L. Bromberg, and the
ARIES Team
Fusion Eng. & Des. 38 (1997) 87-113.
"ARIES-RS Divertor System Selection and Analysis,"
C. P. C. Wong, E. Chin, T. W. Petrie, E. E. Reis, M. S. Tillack, X. Wang,
I. Sviatoslavsky, S. Malang, D. K. Sze, and the ARIES Team
Fusion Eng. & Des. 38 (1997) 115-137.
"Overview of ARIES-RS Neutronics and Radiation Shielding: Key Issues and
Main Conclusions,"
L. El-Guebaly, and the ARIES Team
Fusion Eng. & Des. 38 (1997) 139-158.
"ARIES-RS Magnet Systems,"
L. Bromberg, P. Titus, J. Schultz, M. Sidorov, S. Pourrahimi, and the
ARIES Team
Fusion Eng. & Des. 38 (1997) 159-88.
"ARIES-RS Safety Design and Analysis,"
D. Steiner, L. El-Guebaly, S. Herring, H. Khater, E. Mogahed,
R. Thayer, M. S. Tillack, and the ARIES Team
Fusion Eng. & Des. 38 (1997) 189-218.
4th International Symposium on Fusion Nuclear
Technology (ISFNT-4), April 1997, Tokyo, Japan
"Prospects and Issues for Commercial Fusion Power Systems,"
R. W. Conn, F. Najmabadi, M. S. Tillack and the ARIES Team,
Proc. 4th International Symposium on
Fusion Nuclear Technology (ISFNT-4) (Tokyo, Japan, April 1997),
Fusion Engineering & Design, 41, 337-347 (1998).
"Overview of ARIES-RS Tokamak Fusion Power Plant,"
F. Najmabadi and the ARIES Team,
Proc. 4th International Symposium on
Fusion Nuclear Technology (ISFNT-4) (Tokyo, Japan, April 1997),
Fusion Engineering & Design, 41, 365-370 (1998).
"Engineering Design of the ARIES-RS Power Plant,"
M. S. Tillack and the ARIES Team,
Proc. 4th International Symposium on
Fusion Nuclear Technology (ISFNT-4) (Tokyo, Japan, April 1997),
Fusion Engineering & Design, 41, 491-499 (1998).
"The ARIES-RS Power Core--Recent Development in Li/V Designs,"
D. K. Sze, M. C. Billone, T. Q. Hua, M. S. Tillack, F. Najmabadi, et al.,
Proc. 4th International Symposium on
Fusion Nuclear Technology (ISFNT-4) (Tokyo, Japan, April 1997),
Fusion Engineering & Design, 41, 371-376 (1998).
"ARIES-RS Maintenance Approach for High Availability,"
S. Malang, F. Najmabadi, L. M. Waganer, and M. S. Tillack,
Proc. 4th International Symposium on
Fusion Nuclear Technology (ISFNT-4) (Tokyo, Japan, April 1997),
Fusion Engineering & Design, 41, 377-383 (1998).
"Combination of a Self-Cooled Liquid Metal Breeder Blanket with a Gas
Turbine Power Conversion System,"
S. Malang, H.Schnauder, and M. S. Tillack,
Proc. 4th International Symposium on
Fusion Nuclear Technology (ISFNT-4) (Tokyo, Japan, April 1997),
Fusion Engineering & Design, 41, 561-567 (1998).
"Economic Goals and Requirements for Competitive Fusion Energy"
R. L. Miller,
Proc. 4th International Symposium on
Fusion Nuclear Technology (ISFNT-4) (Tokyo, Japan, April 1997),
Fusion Engineering & Design, 41, 393-400 (1998).
17th IEEE Symposium on Fusion Engineering, Oct. 6-9, 1997, San Diego, CA.
"The Current Drive and Heating Systems for the ARIES-RS Tokamak Power
Plant,"
T. K. Mau
"ARIES-RS Loss of Coolant Accident (LOCA) Analysis,"
E. A. Mogahed, H. Khater, I. N. Sviatoslavsky, L. El-Guebaly
19th Symposium on Fusion Technology (SOFT-19), Lisbon, Sept. 16-20, 1996
"Engineering Overview of ARIES-RS Tokamak Power Plant,"
M. S. Tillack and the ARIES Team
"Designing a Maintainable Tokamak Power Plant,"
L. M. Waganer, F. R. Cole, and the ARIES Team
Other reports:
"Electromagnetic disruption effects in the ARIES-RS tokamak design,"
J. A. Crowell and J. P. Blanchard
UWFDM-1148, October 2000.
Final Report:
The Starlite Study: Assessment of Options for Tokamak Power Plants
-- Final Report,"
F. Najmabadi, et al., UC San Diego Report UCSD-ENG-005 (1997).
Journal Articles:
"Physics Basis for a Tokamak Fusion Power Plant",
S. C. Jardin, C. G. Bathke, D. A. Ehst, S. M. Kaye, C. E. Kessel, Jr., B. J.
Lee, T. K. Mau, J. Menard, R. Miller, F. Najmabadi,
Fusion Engineering and Design, 48
(2000) 281-298.
16th IAEA International Conference on Fusion Energy,
Montreal, October 7 to 11, 1996.
"Assessment of Tokamak Plasma Operation Modes as Fusion Power
Plants--The Starlite Study,"
F. Najmabadi, et al.,
Proc. of 16th IAEA International Conference on Fusion Energy, (Montreal,
Canada, October, 1996).
12th ANS Topical Meeting on Technology of Fusion Energy, June 1996, Reno NV.
Park City Utah
"Assessment of Engineering Options for Attractive Commercial
and Demonstration Tokamak Fusion Power Plant,"
F. Najmabadi,
12th ANS Topical Meeting on Fusion Engineering, (Reno, NV, June 1996),
Fusion Technology,
30, 1286-1292, 1996.
"A Systems Assessment of the Five Starlite Tokamak Power Plants,"
C. G. Bathke and the ARIES Team,
12th ANS Topical Meeting on Fusion Engineering, (Reno, NV, June 1996),
Fusion Technology,
30, 1996.
(Electronic copy is not avilable).
"Fusion Power Plant Economics,"
R. L. Miller, and the ARIES Team,
12th ANS Topical Meeting on Fusion Engineering, (Reno, NV, June 1996),
Fusion Technology,
30, 1996.
(Electronic copy is not avilable).
"Tradeoffs between Improved Performance and Increased Cost of Advanced
Materials in Commercial Power Plants,"
M. S. Tillack, C. G. Bathke, L. A. El-Guebaly, R. L. Miller, and the ARIES
Team,
12th ANS Topical Meeting on Fusion Engineering, (Reno, NV, June 1996),
Fusion Technology,
30, 1996.
"Blanket Selection for the Starlite Project,"
D. K. Sze, M. S. Tillack, I. N. Sviatoslavsky, L. A. El-Guebaly,
C. P. C. Wong, L. M. Waganer, and the ARIES Team,
12th ANS Topical Meeting on Fusion Engineering, (Reno, NV, June 1996),
Fusion Technology,
30, 1996.
(Electronic copy is not avilable).
"Cost-Effective Shield
Designs for Environmentally Attractive Fusion Power Plants,"
L. A. El-Guebaly, C. G. Bathke, and the ARIES Team,
12th ANS Topical Meeting on Fusion Engineering, (Reno, NV, June 1996),
Fusion Technology,
30, 1996.
(Electronic copy is not avilable).
"Initial Nuclear Assessment for a Low Aspect Ratio Power Plant,"
L. A. El-Guebaly, H. Y. Khater, and the ARIES Team,
12th ANS Topical Meeting on Fusion Engineering, (Reno, NV, June 1996),
Fusion Technology,
30, 1996.
(Electronic copy is not avilable).
"Innovative Out-of-Plane Support
of TF Coils and Implication to Fusion Core Maintenance,"
L. Bromberg, P. Titus, and the ARIES Team,
12th ANS Topical Meeting on Fusion Engineering, (Reno, NV, June 1996),
Fusion Technology,
30, 1996.
(Electronic copy is not avilable).
"Busbar for the Low Aspect Ratio Device,"
L. Bromberg, M. Sidorov, and the ARIES Team,
12th ANS Topical Meeting on Fusion Engineering, (Reno, NV, June 1996),
Fusion Technology,
30, 1996.
(Electronic copy is not avilable).
16th IEEE Symposium on Fusion Engineering, Sept 30.-Oct. 5, 1995, Champaign
IL.
"The Starlite Project: The Mission of the Fusion Demo,"
F. Najmabadi, M. S. Tillack, L. M. Waganer, and the ARIES Team
(For some unknown reason, the paper was not published in the proceedings)
"What Must Demo Do?,"
L. M. Waganer, F. Najmabadi, M. S. Tillack, and the ARIES Team
"A Preliminary Systems Assessment of the Starlite Demo Candidates,"
C. G. Bathke and the ARIES Team
"Engineering Options for the U.S. Fusion Demo,"
M. S. Tillack, M. Billone, L. El-Guebaly, D.K. Sze, L. M. Waganer,
C. Wong and the ARIES Team
"Evaluation of the US Demo-1 Helium-Cooled Blanket Options,"
C. P. C. Wong, B. W. McQuillan, R. W. Schleicher, E. T. Cheng, and the ARIES
Team
"Heat Flux Limits on the Plasma-Facing Components of a Commercial Fusion
Power Plant,"
X. R. Wang, D. K. Sze, M. S. Tillack, and C. P. C. Wong
"Breeding Potential of Candidate Breeders for the U.S. Demo Power Plant,"
L. A. El-Guebaly, et al.
(Electronic copy is not avilable).
"Plasma System Requirements and Performance Data Base for the Starlite/Demo
Fusion Power Plant,"
T. K. Mau, et al.
(Electronic copy is not avilable).
"Starlite Economics: Requirements and Methods,"
R. L. Miller, et al.
(Electronic copy is not avilable).
Reports:
"The Requirements of a Fusion Demonstration Reactor,"
R. W. Conn, F. Najmabadi, et al.
UCLA report UCLA-PPG-1394 (1992).
(Electronic copy is not avilable).
Final Report:
The Stellarator Power Plant Study -- Final Report:
R. L. Miller, F. Najmabadi, et al.,
UC San Diego Report UCSD-ENG-004 (1997).
(Click her for electronic copy)
Journal Articles:
"Status of the U. S. Stellarator Reactor Study,"
J. F. Lyon, K. Gulec, R. L. Miller and L. El-Guebaly,
Fusion Engineering and Design 25 85-103 (1994).
(Electronic copy is not avilable).
16th IEEE Symposium on Fusion Engineering, Sept 30.-Oct. 5, 1995, Champaign
IL.
"Neutronics Analysis for the Stellarator Power Plant Study SPPS,"
L. A. El-Guebaly, et al.
(Electronic copy is not avilable).
"Results of the Activation Analysis of the Stellarator Power Plant Study,"
H. Y. Khater, et al.
(Electronic copy is not avilable).
11th ANS Topical Meeting on the Technology of Fusion Energy, June 19-23, 1994
New Orleans, LA.
"Advanced Stellarator Power Plants,"
R. L. Miller,
American Nuclear Society 11th Topical Meeting on the
Technology of Fusion Energy, New Orleans, LA (June 19-23, 1994),
Fusion Technology 26 (November 1994) 1127
[also LA-UR-94-1956].
(Electronic copy is not avilable).
15th IEEE Symposium on Fusion Engineering, Oct.11-15, 1993, Hyannis, MA.
"Overview of the U. S. Stellarator Reactor Study,"
J. F. Lyon, K. Gulec, R. L. Miller and L. El-Guebaly,
Proceedings 15th IEEE/NPSS Symposium on Fusion Engineering,
Hyannis, MA, 1, 411 (October 11-15, 1993).
(Electronic copy is not avilable).
Reports:
"Evaluation of Torsatrons as Reactors,"
J.F. Lyon, K. Gulec, R.L. Miller, and L. El-Guebaly
Oak Ridge National Laboratory Report ORNL/TM-12670 (1994).
(Electronic copy is not avilable).
Final Report:
The Pulsed-Tokamak Fusion Power Plant-
The Pulsar Study -- Final Report,"
F. Najmabadi, R. W. Conn, et al., UC San Diego Report UCSD-ENG-003.
(Electronic copy is not avilable)
3rd International Symposium on Fusion Nuclear
Technology (ISFNT-3), June 26-July 1 1994, Los Angeles, CA
"Using the Shield for Thermal Energy Storage in PULSAR,"
G. T. Sager, D. K. Sze, C. P. C. Wong, C. G. Bathke, J. P. Blanchard,
C. Brimmer, E. T. Cheng, L. A. El-Guebaly, M. Z. Hasa, F. najmabadi,
S. Sharafat, I. N. Sviatoslavski, L. Waganer,
Proc. 3rd International Symposium on Fusion Nuclear Technology (ISFNT-4)
(Los Angeles, CA, June 26-July 1, 1994),
Fusion Engineering and Design, 29, 43-50 (1995).
"Fatigue Life of the Plasma-Facing Components in PULSAR,"
J. A. Crowell, J. P. Blanchard, and The Pulsar Team,
Proc. 3rd International Symposium on Fusion Nuclear Technology (ISFNT-4)
(Los Angeles, CA, June 26-July 1, 1994),
Fusion Engineering and Design, 27, 515-521 (1995).
16th IEEE Symposium on Fusion Engineering, Sept 30.-Oct. 5, 1995, Champaign
IL.
"Activation Analysis of the PULSAR-I Fusion Power Reactor,"
H. Y. Khater, et al.,
(Electronic copy not available).
"Activation Analysis of the PULSAR-II Fusion Power Reactor,"
H. Y. Khater, et al.,
(Electronic copy not available).
Final Report:
"The ARIES-II and ARIES-IV Tokamak Fusion Reactor Study -- The Final
Report,"
UCLA report UCLA-PPG-1461 (1992).
(Electronic copy is not avilable).
14th IAEA International Conference on Plasma Physics and Controlled Nuclear
Fusion Research, Wurzburg, Germany, Sep. 30-Oct. 7, 1992
"Directions for Attractive Tokamak Reactors: The ARIES-II and ARIES-IV
Second-Stability Designs,"
F. Najmabadi, R. W. Conn, and the ARIES Team,
Nuclear Fusion Supplement, 3, 295-420, (1993).
12th ANS Topical Meeting on Fusion Engineering, Reno, NV, June 1996
"The ARIES-II and ARIES-IV Second Stability Reactors,"
F. Najmabadi, R. W. Conn, and the ARIES Team,
Fusion Technology, 21 1721-1728 (1992).
"Neutronics Aspects of ARIES-II and ARIES-IV Fusion Power Reactors,"
L.A. El-Guebaly,
Fusion Technology, 21 2128 (1992).
(Electronic copy is not available).
15th IEEE/NPSS Symposium on Fusion Engineering, Hyannis, MA,
Oct. 11-14, 1993,
"Design Layout and Maintenance of the ARIES-IV Tokamak Fusion Power Plant,"
S. Sharafat, F. Najmabadi, C. P. C. Wong, R. Junge, and I. Sviatoslavsky,
Proc. IEEE 15th Symp. on Fusion Eng.,
Hyannis MA (Oct. 1993), IEEE No. 93CH3348-0, IEEE,
Piscataway, NJ 417-420 (1994).
""Activation and Waste Disposal of the ARIES-II Tokamak Fusion
Power Reactor,"
H. Y. Khater,
Proc. IEEE 15th Symp. on Fusion Eng.,
Hyannis MA (Oct. 1993), IEEE No. 93CH3348-0, IEEE,
Piscataway, NJ 930 (1994).
(Electronic copy is not available).
Final Report:
"The ARIES-III Tokamak Fusion Reactor Study -- The Final Report,"
F. Najmabadi, R. W. Conn, et al.,
UCLA report UCLA-PPG-1384.
(Elecrtonic copy not available).
Journal Articles
"Shielding Aspects of D-3He Fusion Power Reactors,"
L.A. El-Guebaly,
Fusion Technology, 22 124 (1992).
(Elecrtonic copy not available).
Second Wisconsin Symposium on Helium-3 and Fusion Power, July 1993
"Parametric Analysis of the ARIES-III D-3He Tokamak Reactor,"
C. G. Bathke, K. A. Werley, R. L. Miller, R. A. Krakowski,
J. F. Santarius, and the ARIES Team,
Proceedings of the Second Wisconsin Symposium
on Helium-3 and Fusion Power, (July 1993) WCSAR-TR-AR3-9307-3 321.
(Elecrtonic copy not available).
"Engineering Design of ARIES-III,"
D. K. Sze et al. ,
Proceedings of the Second Wisconsin Symposium
on Helium-3 and Fusion Power, (July 1993) WCSAR-TR-AR3-9307-3.
(Elecrtonic copy not available).
14th IEEE/NPSS Symposium on Fusion Engineering, San Diego, CA
Oct. 1991
"The ARIES-III D-He3 Tokamak Reactor Study,"
F. Najmabadi, R. W. Conn, et al.,
Proc. IEEE 14th Symp. on Fusion Eng., San Diego, CA (Oct. 1991),
IEEE No. 91CH3035-3, IEEE, Piscataway, NJ, 213 (1992).
(Electronic copy is not available).
"The ARIES-III D-He3 Tokamak Reactor: Design-Point Determination
and Parametric Studies,"
C. G. Bathke, K. A. Werley, R. L. Miller, R. A. Krakowski, and
J. F. Santarius,
Proc. IEEE 14th Symp. on Fusion Eng., San Diego, CA (Oct. 1991),
IEEE No. 91CH3035-3, IEEE, Piscataway, NJ, 219 (1992).
(Electronic copy is not available).
"An Algorithm for Determining EF Coils from Fixed-Boundary Equilibria
Applied to ARIES-III,"
C. G. Bathke, S. C. Jardin and C. E. Kessel,
Proc. IEEE 14th Symp. on Fusion Eng., San Diego, CA (Oct. 1991),
IEEE No. 91CH3035-3, IEEE, Piscataway, NJ, 1148 (1992).
(Electronic copy is not available).
"Magnet Design for the ARIES-III D-He3 Reactor,"
L. Bromberg, J. H. Schultz, J. E. C. Williams, P. Titus,
F. Najmabadi, S. Sharafat, and the ARIES Team,
Proc. IEEE 14th Symp. on Fusion Eng., San Diego, CA (Oct. 1991),
IEEE No. 91CH3035-3, IEEE, Piscataway, NJ, 313 (1992).
(Electronic copy is not available).
"Nested Shell Superconducting Magnet Design,"
L. Bromberg, J. E. C. Williams and P. Titus,
Proc. IEEE 14th Symp. on Fusion Eng., San Diego, CA (Oct. 1991),
IEEE No. 91CH3035-3, IEEE, Piscataway, NJ, 318 (1992).
(Electronic copy is not available).
"Plasma Startup of the ARIES-III Second-Stability Advanced Fuel Tokamak,"
G. A. Emmert, E. A. Mogahed, C. Kessel, J. Mandrekas, and T. K. Mau,
Proc. IEEE 14th Symp. on Fusion Eng., San Diego, CA (Oct. 1991),
IEEE No. 91CH3035-3, IEEE, Piscataway, NJ, 1031 (1992).
(Electronic copy is not available).
"Thermo-structural Design of the ARIES-III Divertor with Organic Coolant in
Subcooled Flow Boiling,"
M. Z. Hasan, et al.,
Proc. IEEE 14th Symp. on Fusion Eng., San Diego, CA (Oct. 1991),
IEEE No. 91CH3035-3, IEEE, Piscataway, NJ, 346 (1992).
(Electronic copy is not available).
"Safety in the ARIES-III D-He3 Tokamak Reactor Design,"
J. S. Herring and T. J. Dolan,
Proc. IEEE 14th Symp. on Fusion Eng., San Diego, CA (Oct. 1991),
IEEE No. 91CH3035-3, IEEE, Piscataway, NJ, 708 (1992).
(Electronic copy is not available).
"Controlled Central Fueling for ARIES-III by Compact-Toroid Injection,"
S. K. Ho and the ARIES Team,
Proc. IEEE 14th Symp. on Fusion Eng., San Diego, CA (Oct. 1991),
IEEE No. 91CH3035-3, IEEE, Piscataway, NJ, 205 (1992).
(Electronic copy is not available).
"Comparison of Activation of Ceramic and Ferritic Structural
Materials with D-T and D-He3 Fuel Cycles,"
S. K. Ho,
Proc. IEEE 14th Symp. on Fusion Eng., San Diego, CA (Oct. 1991),
IEEE No. 91CH3035-3, IEEE, Piscataway, NJ, 712 (1992).
(Electronic copy is not available).
"The Importance of Using the Mixed Neutron Flux in Activation Analysis of
D-3He Fueled Reactors,"
H. Y. Khater and M. E. Sawan,
Proc. IEEE 14th Symp. on Fusion Eng., San Diego, CA (Oct. 1991),
IEEE No. 91CH3035-3, IEEE, Piscataway, NJ, 613 (1992).
(Electronic copy is not available).
"Current Drive and Profile Control for the ARIES-III Second-Stability
Advanced-Fuel Tokamak Reactor,"
T. K. Mau, J. Mandrekas, D. A. Ehst, J. H. Whealton, and the
ARIES Team,
Proc. IEEE 14th Symp. on Fusion Eng., San Diego, CA (Oct. 1991),
IEEE No. 91CH3035-3, IEEE, Piscataway, NJ, 145 (1992).
(Electronic copy is not available).
"Design Layout and Maintenance of the ARIES-III Tokamak Reactor,"
S. Sharafat, F. Najmabadi, I. Sviatoslavsky, and the ARIES Team,
Proc. IEEE 14th Symp. on Fusion Eng., San Diego, CA (Oct. 1991),
IEEE No. 91CH3035-3, IEEE, Piscataway, NJ, 1039 (1992).
(Electronic copy is not available).
"Thermo-Mechanical Design and Structural Analysis of the First Wall
for ARIES-III D-He3 Power Reactor,"
I. N. Sviatoslavsky, J. P. Blanchard, E. A. Mogahed, and the ARIES Team,
Proc. IEEE 14th Symp. on Fusion Eng., San Diego, CA (Oct. 1991),
IEEE No. 91CH3035-3, IEEE, Piscataway, NJ, 455 (1992).
(Electronic copy is not available).
"ARIES-III Divertor Engineering Design,"
C. P. C. Wong, et al.,
Proc. IEEE 14th Symp. on Fusion Eng., San Diego, CA (Oct. 1991),
IEEE No. 91CH3035-3, IEEE, Piscataway, NJ, 451 (1992).
(Electronic copy is not available).
13th IEEE/NPSS Symposium on Fusion Engineering, Knoxville, TN, Oct. 1989
"Energy Conversion Options for ARIES-III -- A Conceptual D-He3 Tokamak
Reactor,"
J. F. Santarius, et al.
IEEE 13th Symp. on Fusion Eng., Knoxville, TN (Oct. 1989),
IEEE No. 89CH2820-9, IEEE, Piscataway, NJ, 1039-1042 (1990).
(Electronic copy is not available).
"Organic-Cooled First-Wall and Shield Design for the ARIES-III D-He3
Reactor,"
M. E. Sawan, et al.,
IEEE 13th Symp. on Fusion Eng., Knoxville, TN (Oct. 1989),
IEEE No. 89CH2820-9, IEEE, Piscataway, NJ, 1110 (1990).
(Electronic copy is not available).
10th ANS Topical Meeting on Fusion Engineering, Boston, MA, June 7-12, 1992
"Neutronics Analysis for the First Wall and Shield of the D-3He Reactor
ARIES-III,"
M.E. Sawan and L.A. El-Guebaly,
Fusion Technology, 21 2069 (1992).
(Elecrtonic copy not available).
"Activation Analysis for the D-3He Reactor,"
H. Y. Khater and M. E. Sawan,
Fusion Technology, 21 2112 (1992).
(Elecrtonic copy not available).
"Tritium Production, Management, and Its Impact on Safety for a
D-He3 Fusion Reactor,"
D. K. Sze, S. Herring, M. Sawan, and the ARIES Team,
Fusion Technology, 21 994-998 (1992).
(Elecrtonic copy not available).
Final Report
"The ARIES-I Tokamak Fusion Reactor Study -- The Final Report,"
F. Najmabadi, R. W. Conn, et al.,
UCLA report UCLA-PPG-1323.
(Click her for electronic
copy)
13th IAEA Conference on Plasma Physics & Controlled Nuclear
Fusion Research, Washington, DC, Oct. 1990
"ARIES-I: A Steady-State, First-Stability Tokamak Reactor with Enhanced
Safety and Environmental Features,"
R. W. Conn, F. Najmabadi, et al.,
Nuclear Fusion Supplement, 3, 659-670 (1991).
(Elecrtonic copy is not available).
16th Symposium on Fusion Technology, Sep. 1990, London United Kingdom
"The ARIES-I Tokamak Reactor Study,"
F. Najmabadi, R. W. Conn, et al.
Proc. 16th Symp. Fusion Technol. (SOFT),
London, United Kingdom (Sept. 1990), Fusion Technology 90, A. M. Van
Ingen, A. Nijsen-Vis, H. T. Klippel, Eds., North-Holland, Amsterdam, 253
(1991).
(Elecrtonic copy is not available).
2nd International Symposium on Fusion Nuclear Technology, Karlsruhe, Germany,
June 1991
"ARIES-I Fusion Power Core Engineering,"
S. Sharafat, F. Najmabadi, et al.
Proc. 2nd Int. Symp. on Fusion Nuclear
Technology (ISFNT-2), Karlsruhe, Germany (June 1991),
Fusion Eng. and Design, 18 215-222 (1991).
9th ANS Topical Meeting on The Technology of Fusion Energy, Oakbrook, IL,
Oct7-11, 1990
"Neutronics Design Aspects of Reference ARIES-I Fusion Blanket,"
E. T. Cheng and the ARIES Team,
Fusion Technology, 19 984 (1991).
(Elecrtonic copy is not available).
"Design Integration and Maintenance of the ARIES-I Tokamak Reactor,"
S. P. Grotz, F. Najmabadi, L. Bromberg, R. L. Miller, D. K. Sze,
C. P. C. Wong and the ARIES Team,
Fusion Technology, 19 889-894 (1991).
(Elecrtonic copy is not available).
"Thermal Response of the ARIES-I Divertor Plate to Plasma Disruption,"
M. Z. Hasan, T. Kunugi, M. Seki and M. Yokokawa,
Fusion Technology, 19 908-912 (1991).
(Elecrtonic copy is not available).
"Entry-Length Effect on the Thermal-Hydraulic Design of Plasma Facing
Components of Fusion Reactors, Part II: MHD Flow,"
M. Z. Hasan and T. Kunugi,
Fusion Technology, 19 1030-1035 (1991).
(Elecrtonic copy is not available).
"Activation Product Safety in the ARIES-I Reactor Design,"
J. S. Herring, C. Wong, E. T. Cheng, D. K. Sze, S. P. Grotz,
and the ARIES Team,
Fusion Technology, 19 1386-1391 (1991).
(Elecrtonic copy is not available).
"ARIES-I Tokamak Reactor Start-up Simulations, Tradeoffs, and
Engineering Considerations,"
R. A. Krakowski, G. L. Varsamis, T. K. Mau, C. G. Bathke, K. A. Werley,
C. P. C. Wong, and K. R. Schultz,
Fusion Technology, 19 1272-1277 (1991).
(Elecrtonic copy is not available).
"Entry-Length Effect on the Thermal-Hydraulic Design of Plasma Facing
Components of Fusion Reactors, Part I: Non-MHD Flow,"
T. Kunugi and M. Z. Hasan,
Fusion Technology, 19 1024-1029 (1991).
(Elecrtonic copy is not available).
"Current Drive Using Fast Waves and Folded Waveguide Launchers for
the ARIES-I Tokamak Reactor,"
T. K. Mau, D. A. Ehst, D. J. Hoffman, and the ARIES Team,
Fusion Technology, 19 882-888 (1991).
(Elecrtonic copy is not available).
"Options and Optimization for Tokamak Reactors: ARIES,"
R. L. Miller, R. A. Krakowski, and the ARIES Team,
Fusion Technology, 19 802-806 (1991).
(Elecrtonic copy is not available).
"The ARIES-I Tokamak Reactor,"
F. Najmabadi and R. W. Conn,
Fusion Technology, 19 783-790 (1991).
(Elecrtonic copy is not available).
"Divertor Engineering for the ARIES-I Tokamak Reactor,"
S. Sharafat, S. P. Grotz, M. Z. Hasan and T. K. Kunugi,
Fusion Technology, 19 895-900 (1991).
(Elecrtonic copy is not available).
"SiC-Composite First Wall Design for the ARIES-I Reactor,"
S. Sharafat and the ARIES Team,
Fusion Technology, 19 901-907 (1991).
(Elecrtonic copy is not available).
"ARIES-I Tritium System,"
D. K. Sze, S. W. Tam, M. C. Billone, and R. Martin,
Fusion Technology, 19 1674-1679 (1991).
(Elecrtonic copy is not available).
"ARIES-I SiC Composite Low Activation Blanket Design,"
C. P. C. Wong, E. T. Cheng, K. R. Schultz, S.P. Grotz, M. Z. Hasan, F.
Najmabadi, S. Sharafat, T. Kunugi, J. S. Herring, D. K. Sze, and The ARIES
Team,
Fusion Technology, 19 938-943 (1991).
(Elecrtonic copy is not available).
13th IEEE/NPSS Symposium on Fusion Engineering, Knoxville, TN, Oct. 1989
"The ARIES Tokamak Fusion Reactor Study,"
F. Najmabadi and R. W. Conn,
IEEE 13th Symp. on Fusion Eng., Knoxville, TN (Oct. 1989),
IEEE No. 89CH2820-9, IEEE, Piscataway, NJ, 1021 (1990).
(Electronic copy is not available).
"Vertical Stability Requirements for ARIES-I Reactor,"
C. G. Bathke, S. C. Jardin, J. A. Leuer, D. J. Ward, and the
ARIES Team,
IEEE 13th Symp. on Fusion Eng., Knoxville, TN (Oct. 1989),
IEEE No. 89CH2820-9, IEEE, Piscataway, NJ, 909-912 (1990).
(Electronic copy is not available).
"High-Field Magnet Designs for the ARIES-I Reactor,"
L. Bromberg, D. R. Cohn, J. Schultz, J. E. C. Williams, S. P. Grotz,
R. L. Creedon, C. P. C. Wong, and the ARIES Team,
IEEE 13th Symp. on Fusion Eng., Knoxville, TN (Oct. 1989),
IEEE No. 89CH2820-9, IEEE, Piscataway, NJ, 352-356 (1990).
(Electronic copy is not available).
"Neutronics Studies for the ARIES-I Reactor,"
E. T. Cheng and the ARIES Team,
IEEE 13th Symp. on Fusion Eng., Knoxville, TN (Oct. 1989),
IEEE No. 89CH2820-9, IEEE, Piscataway, NJ, 58-61 (1990).
(Electronic copy is not available).
"Thermal Cycle Power Conversion for the ARIES-I Tokamak Reactor,"
M. Z. Hasan and the ARIES Team,
IEEE 13th Symp. on Fusion Eng., Knoxville, TN (Oct. 1989),
IEEE No. 89CH2820-9, IEEE, Piscataway, NJ, 392-395 (1990).
(Electronic copy is not available).
"Safety in the ARIES Tokamak Design Study,"
J. S. Herring, C. P. C. Wong, E. T. Cheng, S. Grotz and the ARIES Team,
IEEE 13th Symp. on Fusion Eng., Knoxville, TN (Oct. 1989),
IEEE No. 89CH2820-9, IEEE, Piscataway, NJ, 329-332 (1990).
(Electronic copy is not available).
"Numerical Simulation of Turbulent Gas-Particle Fluid Flow and Heat
Transfer,"
T. Kunugi, M. Z. Hasan, and the ARIES Team,
IEEE 13th Symp. on Fusion Eng., Knoxville, TN (Oct. 1989),
IEEE No. 89CH2820-9, IEEE, Piscataway, NJ, 882-885 (1990).
(Electronic copy is not available).
"Current Drive Analysis and System Design for the ARIES-I Tokamak
Reactor,"
T. K. Mau, D. A. Ehst, J. Mandrekas, M. J. Shaffer, and the ARIES
Team,
IEEE 13th Symp. on Fusion Eng., Knoxville, TN (Oct. 1989),
IEEE No. 89CH2820-9, IEEE, Piscataway, NJ, 272-275 (1990).
(Electronic copy is not available).
"The ARIES-I High-Field Tokamak Reactor: Design Point Determination and
Parametric Studies,"
R. L. Miller, and the ARIES Team,
IEEE 13th Symp. on Fusion Eng., Knoxville, TN (Oct. 1989),
IEEE No. 89CH2820-9, IEEE, Piscataway, NJ, 1027-1030 (1990).
(Electronic copy is not available).
"MHD Equilibrium and Stability Considerations for High-Aspect-Ratio
ARIES-I Tokamak Reactor,"
Y.-K. M. Peng, D. J. Strickler, J. T. Hogan, J. C. Whitson, C. G. Bathke,
K. Evens, S. C. Jardin, M. Klasky, J. A. Leuer, and the ARIES Team,
IEEE 13th Symp. on Fusion Eng., Knoxville, TN (Oct. 1989),
IEEE No. 89CH2820-9, IEEE, Piscataway, NJ, 1278-1282 (1990).
(Electronic copy is not available).
"SiC Composites as Structural Material for the ARIES-I Reactor,"
S. Sharafat, N. M. Ghoniem, L. Y. Lee, and the ARIES team,
IEEE 13th Symp. on Fusion Eng., Knoxville, TN (Oct. 1989),
IEEE No. 89CH2820-9, IEEE, Piscataway, NJ, 1344-13472 (1990).
(Electronic copy is not available).
"Blanket Design for the ARIES-I Reactor,"
C. P. C. Wong, et al.,
IEEE 13th Symp. on Fusion Eng., Knoxville, TN (Oct. 1989),
IEEE No. 89CH2820-9, IEEE, Piscataway, NJ, 1035-1038 (1990).
(Electronic copy is not available).
Final Report
"The TITAN Reversed Field Pinch Fusion Reactor Study -- The Final Report,"
F. Najmabadi, R. W. Conn, et al.,
UCLA report UCLA-PPG-1200 (1990).
(Click her for electronic copy)
Scoping Phase Report
"The TITAN Reversed Field Pinch Fusion Reactor Study - The
Scoping Phase Report,"
F. Najmabadi, N. M. Ghoniem, R. W. Conn, et al.
UCLA report UCLA-PPG-1100 (1987).
(Click her for electronic copy)
Journal Articles
"Introduction and Synopsis of the TITAN Reversed-Field-Pinch Fusion-Reactor
Study,"
F. Najmabadi, et al.,
Fusion Engineering and Design, 23, 69-80 (1993).
(Elecrtonic copy is not available)
"The TITAN-I Reversed-Field-Pinch Fusion-Power-Core Design,"
F. Najmabadi, et al.,
Fusion Engineering and Design, 23, 81-98 (1993).
(Elecrtonic copy is not available)
"Materials Analysis of the TITAN-I Reversed-Field-Pinch Fusion Power Core,"
S. Sharafat, N. M. Ghoniem, P. I. H. Cooke, R. C. Martin, F. Najmabadi,
K. R. Schultz, C. P. C. Wong, and the TITAN Team,
Fusion Engineering and Design, 23, 99-113 (1993).
(Elecrtonic copy is not available)
"Thermal-Hydraulic andStructural Design of the TITAN-I
Reversed-Field-Pinch Fusion Power Core,"
M. Z. Hasan, N. M. Ghoniem, J. P. Blanchard, and the TITAN Team,
Fusion Engineering and Design, 23, 115-132 (1993).
(Elecrtonic copy is not available)
"Safety Design and Radioactive-Waste-Disposal Analysis for the TITAN-I
Reversed-Field-Pinch Reactor Design,"
C. P. C. Wong, S. P. Grotz, J. P. Blanchard, E. T. Cheng, R. W. Conn,
R. L. Creedon, C. G. Hoot, F. Najmabadi, S. Sharafat, and K. R. Schultz,
Fusion Engineering and Design, 23, 133-156 (1993).
(Elecrtonic copy is not available)
"Integrated-blanket-coil appliations in the TITAN-I reversed-field pinch
reactor,"
W. P. Duggan and D. Steiner,
Fusion Engineering and Design, 23, 157-172 (1993).
(Elecrtonic copy is not available)
"The TITAN-II Reversed-Field-Pinch Fusion-Power-Core Design,"
C. P. C. Wong, S. P. Grotz, F. Najmabadi, J. P. Blanchard, E. T. Cheng,
P. I. H. Cooke, R. L. Creedon, N. M. Ghoniem, et al.,
Fusion Engineering and Design, 23, 173-200 (1993).
(Elecrtonic copy is not available)
"Materials SelectionCriteria and Performance Analysis for the TITAN-II
Reversed-Field-Pinch Fusion-Power-Core Design,"
S. Sharafat, N. M. Ghoniem, P. I. H. Cooke, R. C. Martin, F. Najmabadi,
K. R. Schultz, C. P. C. Wong, and the TITAN Team,
Fusion Engineering and Design, 23, 201-217 (1993).
(Elecrtonic copy is not available)
"Maintenance Procedures and Analysis for the TITAN rEversed-Field-Pinch
Reactor Designs,"
S. P. Grotz, F. Najmabadi, P. I. H. Cooke, R. L. Creedon, C. P. C. Wong,
R. A. Krakowski, and W. P. Duggan,
Fusion Engineering and Design, 23, 219-232 (1993).
(Elecrtonic copy is not available)
"Safety Design and Radioactive Waste Disposal Analysis for the TITAN-II
Reversed-Field-Pinch Reactor Design,"
C. P. C. Wong, E. T. Cheng, S. P. Grotz, S. Sharafat, R. L. Creedon, and
K. R. Schultz,
Fusion Engineering and Design, 23, 233-237 (1993).
(Elecrtonic copy is not available)
"Advances in Fusion Reactor Design - The TITAN Reversed-field-pinch Reactor
Study,"
F. Najmabadi,
J. Fusion Energy, 7, 177-181 (1988).
(Elecrtonic copy is not available)
9th ANS Topical Meeting on The Technology of Fusion Energy, Oakbrook, IL,
Oct7-11, 1990
"Plasma Confinement Requirements for Compact RFP Reactor (TITAN)
Plasmas Operated in a High-Radiation Mode,"
K. A. Werley, C. G. Bathke, R. A. Krakowski, R. L. Miller
and J. N. DiMarco,
Fusion Technology 19 1266 (1991).
12th IAEA Conference on Plasma Physics & Controlled Nuclear
Fusion Research, Nice, France Oct. 1988
"Compact, High-Power-Density Reversed-Field-Pinch Fusion Reactors,"
R. W. Conn, F. Najmabadi, et al.,
Nuclear Fusion Supplement 3, 315-324 (1989).
(Elecrtonic copy is not available)
15th Symposium on Fusion Technology, Sep. 1988, Utrecht, The Netherlands
"Engineering and Physics of High-Power-Density, Compact,
Reversed-Field-Pinch Fusion Reactors: The TITAN Study,"
F. Najmabadi, R. W. Conn, R. A. Krakowski, K. R. Schultz,
D. Steiner and the TITAN Team,
Proc. 15th Symposium on Fusion Technology (SOFT-15), (Utrecht, The
Netherlands, Sept. 1988), Fusion Technology 1988, North
Holland, Amsterdam, 1779-1785 (1989).
(Elecrtonic copy is not available)
1st International Symposium on Fusion Nuclear Technology (ISFNT-1), Tokyo, Japn
April 10-19, 1988.
"Overview of the TITAN-I Fusion-Power Core,"
S. P. Grotz, et al.,
Fusion Engineering and Design, 10, 367-373 (1989).
(Elecrtonic copy is not available)
"Maintenance Procedures for the TITAN-I and TITAN-II Reversed-Field Pinch
Reactors,"
S. P. Grotz, R. L. Creedon, P. I. H. Cooke, W. Duggan, R. Krakowski,
F. Najmabadi, C. P. C. Wong, and the TITAN Research Group,
Fusion Engineering and Design, 10, 481-487 (1989).
(Elecrtonic copy is not available)
"The Safety Design for the TITAN Reversed-Field Pinch Reactor Study,"
C. P. C. Wong, S. P. Grotz, J. P. Blanchard, E. T. Cheng, S. Sharafat,
R. L. Creedon, C. G. Hoot, F. Najmabadi, K. R. Schultz, and the TITAN Research
Group,
Fusion Engineering and Design, 10, 447-453 (1989).
(Elecrtonic copy is not available)
12th IEEE/NPSS Symposium on Fusion Engineering, Monterey, CA, Oct. 1987
"The TITAN Reversed-Field-Pinch Lithium-Vanadium Fusion Power Core Design,"
S. P. Grotz, N. M. Ghoniem, and the TITAN Team,
Proc. 12th IEEE Symposium on Fusion Engineering,
(Monterey, CA, Oct. 1987), IEEE No. 87CH2507-2, Piscataway, NJ, 776-779
(1988).
(Elecrtonic copy is not available)
"Single-Piece Maintenance Procedures for the TITAN Reversed-Field Reactor,"
S. P. Grotz, R. L. Creedon, P. I. H. Cooke, W. P. Duggan,
R. A. Krakowski, F. Najmabadi, and C. P. C. Wong,
Proc. 12th IEEE Symposium on Fusion Engineering,
(Monterey, CA, Oct. 1987), IEEE No. 87CH2507-2, Piscataway, NJ, 930-933
(1988).
(Elecrtonic copy is not available)
"Thermal-Hydraulic Design for the Lithium-Cooled TITAN Reversed-Field
Pinch Reactor,"
M. Z. Hasan, J. P. Blanchard, R. W. Conn, P. I. H. Cooke, N. M. Ghoniem,
S. P. Grotz, F. Najmabadi,
Proc. 12th IEEE Symposium on Fusion Engineering,
(Monterey, CA, Oct. 1987), IEEE No. 87CH2507-2, Piscataway, NJ,
1054-1057 (1988).
(Elecrtonic copy is not available)
"The TITAN Reversed-Field-Pinch Reactor: Design-Point Determination and
Parametric Studies,"
R. L. Miller,
Proc. 12th IEEE Symposium on Fusion Engineering,
(Monterey, CA, Oct. 1987), IEEE No. 87CH2507-2, Piscataway, NJ,
951 (1988).
(Elecrtonic copy is not available)
"The TITAN Reversed-Field-Pinch Fusion Reactor Study,"
F. Najmabadi, R. W. Conn, and the TITAN Team,
Proc. 12th IEEE Symposium on Fusion Engineering,
(Monterey, CA, Oct. 1987), IEEE No. 87CH2507-2, Piscataway, NJ,
503-508 (1988).
(Elecrtonic copy is not available)
"Structure and Insulator Material Choices for the TITAN Reversed-Field Pinch
Reactor,"
S. Sharafat, N. M. Ghoniem, E. Cheng, P. I. H. Cooke, S. P. Grotz,
R. Martin, F. Najmabadi, et al.,
Proc. 12th IEEE Symposium on Fusion Engineering,
(Monterey, CA, Oct. 1987), IEEE No. 87CH2507-2, Piscataway, NJ,
1046-1049 (1988).
(Elecrtonic copy is not available)
"The TITAN-II, Reversed-Field Pinch Aqueous Fusion Power Core Design,"
C. P. C. Wong, et al.,
Proc. 12th IEEE Symposium on Fusion Engineering,
(Monterey, CA, Oct. 1987), IEEE No. 87CH2507-2, Piscataway, NJ,
1287-1291 (1988).
(Elecrtonic copy is not available)
Fusion Energy and Power Plants
"Recent Directions in Plasma Physics and Their impact on Tokamak Magnetic
Fusion Design,"
M. Kikuchi, R. W. Conn, F. Najmabadi, and Y. Seki,
Fusion Eng. and Design 16, 253-270 (1991).
(Elecrtonic copy is not available)
"Economic, Safety and Environmental Prospects of Fusion Reactors,"
R. W. Conn, J. P. Holdren, S. Sharafat, D. Steiner, D. A. Ehst,
W. J. Hogan, R. A. Krakowski, R. L. Miller, F. Najmabadi and
K. R. Schultz,
Nuclear Fusion 30, 1919 (1990).
(Elecrtonic copy is not available)
Alternate Applications of Fusion
"Assessing A New Direction For Fusion,"
Fusion Engineering and Design, 48, 467-472 (2000).
"Can Fusion do Better than Boil Water for Electricity,"
L. M. Waganer and the ARIES Team
Proc. 13th ANS Topical Meeting on Technology of Fusion Energy,
(Nashville, TN, June 1998).
"Assessment of Markets and Customers for Fusion Applications,"
L. M. Waganer,
Proc. 17th IEEE/NPSS Symp. on Fusion Eng., (San Diego, CA, Oct. 1997),
Economics, Costing and System Studies
"Evolution of the Design in the ARIES and PULSAR Projects,"
C. G. Bathke, R. L. Miller, et al.,
Proc. 16th IEEE/NPSS Symp. on Fusion Eng., (Champaign, IL Oct. 1995),
"Lessons Learned from the Tokamak Advanced Reactor Innovation and
Evaluation Study (ARIES),"
R. A. Krakowski, C. G. Bathke, R. L. Miller and K. A. Werley,
Los Alamos National Laboratory document LA-UR-93-4217 (1993).
(Electronic copy is not available).
"A Cost-Based Systems Analysis of Long-Pulsed versus Steady-State
Tokamak Reactors,"
R. A. Krakowski, R. L. Miller and C. G. Bathke,
Proc. 14th IEEE Symp. on Fusion Eng., (San Diego, CA, Oct. 1997),
IEEE No. 91CH3035-3, IEEE, Piscataway, NJ, 1119 (1992).
(Electronic copy is not available).
"Comparison of EURATOM and US Estimates of Fusion Reactor Costs,"
R. L. Miller, W. R. Spears, R. Hancox and R. A. Krakowski,
Proc. 9th ANS Topical Meeting on the Technology of Fusion Energy,
(Oak Brook, IL, Oct. 1990), Fusion Technology
19 813 (1991).
(Electronic copy is not available).
"Lessons Learned from the Tokamak Advanced Reactor Innovation and
Evaluation Study (ARIES),"
R. A. Krakowski, C. G. Bathke, R. L. Miller, and K. A. Werley,
Proc. 11th ANS Topical Meeting on the Technology of Fusion Energy,
(New Orleans, LA, June 1994), Fusion Technology
26 1111 (1991).
(Electronic copy is not available).
General Topics
"Engineering Issues for Dipole-Based Fusion Reactors,"
L. Bromberg et al.,
Proc. 14th ANS Topical Meeting on Technology of Fusion Energy
(Park City, Utah, Oct. 2000).
(Electronic copy is not available)
"Innovative, Ultra-Low Cost Fabrication Methods,"
L. M. Waganer,
Proc. 18th IEEE Symp. Fusion Eng., (Albuquerque, NM, Oct. 1999).
"Particle Dynamic Simulation of Free Surface Granular Flows,"
M. S. Tillack and J. Zhang,
Proc. 5th International Symposium on Fusion Nuclear
Technology - ISFNT-5 (Rome, Italy (Sep. 1999).
(Electronic copy is not available)
"Modular Application of Moving-Belt Plasma-Facing Components
for Particle and Heat Removal from a Steady-State Fusion System,"
Y. Hirooka and M. S. Tillack,
Proc. 13th ANS Topical Meeting on the Technology of Fusion Energy,
(Nashville, TN, June 1998).
"Steady-State Impurity Control, Heat
Removal and Tritium Recovery by Moving-Belt Plasma-Facing Components,"
Y. Hirooka, M. S. Tillack and A. Grossman,
Proc. 18th IEEE Symp. Fusion Eng., (San Diego, CA 1007).
"2-Dimensional Analysis of ICRF Wave Propagation and Absorption on KSTAR
Plasma,"
B.G. Hong, M.H. Ju, T.K. Mau,
Proc. 12th Top. Conf. on Radio Frequency Power in Plasmas, (Savannah,
GA, 1997).
(Electronic copy is not available)
"Cost Effective Shield Designs for Environmentally Attractive Fusion Power
Plants,"
L.A. El-Guebaly and C.G. Bathke,
Fusion Technology, (1996).
"Neutronics Assessment for the ARIES Advanced Reactor Studies,"
L. El-Guebaly,
Fusion Engineering and Design, 28 658-664 (1995).
Need for
Special Burning Module in Fusion Devices to Transmute Fusion
High Level Waste,
L. A. El-Guebaly, UWFDM-1155, June 2002.