- April 23-24, 2009/ARR 1 Proposed Effort Over the Next 1-2 Years on
- September 24-25, 2003 HAPL meeting, UW, Madison 1 Armor Configuration & Thermal Analysis
- Oct 5, 2007/ARR Compact Stellarator Fusion Power Plant Study
- Fusion Engineering and Design 85 (2010) 23122322 Contents lists available at ScienceDirect
- March 21-22, 2006 HAPL meeting, ORNL Status of Chamber and Blanket Effort
- The main function of the divertor is minimizing the helium and impurity content in the plasma as well as exhausting part of the plasma thermal power.
- May 31-June 1, 2001 A. R. Raffray, et al., Assessment of Dry Chamber Walls as Preliminary Step in Defining Key Processes for Chamber Clearing Code 1
- August 17, 2000 ARIES: Fusion Power Core and Power Cycle Engineering/ARR 1
- IEEE/NPSS Symposium on Fusion Engineering 2005 (SOFE) Gas-cooled divertor design approach for ARIES-CS
- February 5-6, 2004 HAPL meeting, G.Tech. 1
- May 28-29, 2008/ARR Thermal Effect of Off-Normal Energy
- ITER HEAT REMOVAL SYSTEM SYSTEM & PROCESS CONTROL DESIGN
- December 12-13, 2007/ARR Power Core Engineering: Design Updates
- Accepted Manuscript Making Tungsten Work
- jou.rm.alnf ELSEVIER Journal of Nuclear Materials 241-243 (1997) 255-259
- June 17-21, 2007 SOFE07, Albuquerque 1 Conceptual Study of Integrated Chamber Core
- ELSEVIER Journal of Nuclear Materials 244 (1997) 85-100 RACLETTE: a model for evaluating the thermal response of plasma
- November 15, 2000 A. R. Raffray, and the ARIES Team., ARIES-ST and ARIES-AT Blanket Designs, APEX Meeting
- Please cite this article in press as: A.R. Raffray, et al., Optimizing the overall configuration of a He-cooled W-alloy divertor for a power plant, Fusion Eng. Des. (2009), doi:10.1016/j.fusengdes.2008.12.069
- November 2002 15th TOFE, Washington, D.C. 1 Thermal Behavior and Operating
- Fusion Engineering and Design 85 (2010) 93108 Contents lists available at ScienceDirect
- DESIGN OPTIMIZATION OF HIGH-PERFORMANCE HELIUM-COOLED DIVERTOR PLATE CONCEPT
- LASER IFE DIRECT DRIVE CHAMBER CONCEPTS WITH MAGNETIC INTERVENTION A. R. Raffray1
- INTEGRATION OF THE MODULAR DUAL COOLANT PB-17LI BLANKET CONCEPT IN THE ARIES-CS POWER PLANT
- A SELF-COOLED LIQUID BREEDER BLANKET FOR A LASER IFE POWER PLANT WITH MAGNETIC INTERVENTION
- Pre-print of Manuscript Accepted for Publication in Fusion Engineering & Design, 2007
- Fusion Engineering and Design 82 (2007) 265290 Transient thermo-mechanical behavior of a direct-drive target
- FUSION-3792; No.of Pages15 Fusion Engineering and Design xxx (2006) xxxxxx
- Fusion Engineering and Design xxx (2006) xxxxxx Overview of fusion nuclear technology in the US
- Threats, design limits and design windows for laser IFE dry wall chambers
- Modeling DT Vaporization and Melting in a Direct Drive Target B. R. Christensen1
- Advanced high performance solid wall blanket concepts C.P.C. Wong a,
- Progress in blanket designs using SiCf/SiC composites L. Giancarli a,
- Range of blanket concepts from near term solutions to advanced concepts
- Breeding blanket concepts for fusion and materials requirements
- Fusion Engineering and Design 3940 (1998) 585591 ITER first wall/shield blanket
- Journal of Nuclear Materials 1'73(1990) 185-213 North-Holland
- Fusion Engineering and Design 6 (1988) 3-64 North-Holland, Amsterdam
- (Pre-print of paper to be published in the 4th IFSA Proceedings)
- Dry Chamber Wall Thermo-Mechanical Behavior and Lifetime under IFE Cyclic Energy Deposition
- PROGRESS OF ITER FIRST WALL DESIGN R. Mitteau(*), R. Raffray(*), P. Chappuis(*), M. Merola(*), D. Loesser(**) on behalf of the
- Power Handling in ITER: Divertor and Blanket Design and R&D M. Merola 1), D. Loesser 2), R. Raffray 1) on behalf of the ITER Organization, ITER
- Transient Thermal and Stress Response of A Helium-Cooled Tungsten Plate-Type Divertor
- Helium Jet-Cooled Tungsten Divertor Concept J.S. O'Della
- Neutronics Analysis of a Molten Salt Blanket for the HAPL Laser Fusion Power Plant with Magnetic
- Conceptual Study of Integrated Chamber Core for Laser Fusion with Magnetic Intervention
- Modular Dual Coolant Pb-17Li Blanket Design For ARIES-CS Compact Stellarator Power Plant
- Statusof the EngineeringDesign of the ITER Divertor S . Chiocchio, A. Antipenkov, G. Federici, C. Ibbott, H. Heidl, R. Jakeman, G.Janeschitz, E. Martin,
- In-Situ Repair Concepts for the ITER First Wall Components R. Materaa, S. Chiocchioa, G. Federicia, K. Iokia, R. Raffraya, A. Cardellaa, A. Lodatoa, F. Saint-Antoninb, G.
- EXPERIMENTALSTUDY OF THE EFFECTIVETHERMAL CONDUCTIVITYOFA PACKED BED AS A TEMPERATURECONTROL MECHANISMFOR ITER CERAMICBREEDERBLANKETDESIGNS *
- May21-26, 2006/ARR Accommodation of Prompt
- May 22-27, 2005 ISFNT-7, Tokyo, Japan Major Integration Issues in Evolving the
- September 14-16, 2004/ARR ATTRACTIVE DESIGN
- MODELING DT VAPORIZATION AND MELTING IN A DIRECT
- THERMAL LOADING OF A DIRECT DRIVE TARGET IN
- November 20, 2002 A. R. Raffray, et al., Thin Liquid Wall Behavior under IFE Cyclic Operation 1 Thin Liquid Wall Behavior under IFE Cyclic Operation
- May 27, 2002 A. R. Raffray, et al., IFE Chamber Walls: Requirements, Design Options, and Synergy with MFE Plasma Facing Components 1 IFE Chamber Walls: Requirements, Design Options,
- October 16-19, 2000 A. R. Raffray, et al., ARIES-AT Blanket and Divertor, ANS Top. Meet. On TOFE 2000 1
- ARR/18th SOFE Presentation, Albuquerque, NM, October 1999 SiC/SiC Composite for an
- March 3-4, 2008/ARR Power Management Technical Working Group
- September 6-7, 2007/ARR Power Management Technical Working Group
- April 3-4, 2007/ARR Engineering Input to System Code and
- Oct 5, 2006/ARR ARIES-CS Power Core Engineering
- June 14-15, 2006/ARR ARIES-CS Power Core Engineering
- April 27-28, 2006/ARR Finalizing ARIES-CS Power Core
- April 27-28, 2006/ARR Support and Possible In-Situ Alignment of
- November 17-18, 2005/ARR Status of Engineering Effort on ARIES-CS
- February 24-25, 2005/ARR ARIES-CS Power Core Engineering
- November 4-5, 2004/ARR ARIES-CS Power Core Options for
- June 16, 2004/ARR Thermal-Hydraulic Study of ARIES-CS
- March 8-9, 2004/ARR Some of the Major Considerations in
- December 3-4, 2003/ARR Maintenance Studies for 3-Field
- January 8-10, 2003/ARR Plan for Engineering Study of ARIES-CS
- October 2, 2002/ARR 1. Liquid Wall Ablation
- March 8, 2001 A. R. Raffray, et al., Assessment of Carbon and Tungsten Dry Chamber Walls under IFE Energy Depositions
- ARR/ARIES meeting, UCSD, Dec 1-3/99 Status of ARIES-AT Blanket and First Wall
- ARR/ARIES meeting, UCSD, Dec 1-3/99 Divertor Options for ARIES-AT
- Dec 12-13, 2006 HAPL meeting, PPPL Advanced Chamber Concept with Magnetic Intervention
- Aug. 8-9, 2006 HAPL meeting, GA Open Discussion on Advanced Armor
- November 8-9, 2005 1 "Engineering Analysis" of He Retention &
- November 8-9, 2005 Blanket Design for Large Chamber
- June 20-21, 2005 HAPL Program Workshop, LLNL 1
- March 3-4, 2005 HAPL meeting, NRL 1
- ARR_1, HAPL, March 3-4, 2005 (a) Effect of Cusp Field on Ion Energy
- October 27-28, 2004 HAPL meeting, PPPL 1
- February 5-6, 2004 HAPL meeting, G.Tech. 1
- April 9-10, 2003 HAPL Program Meeting, SNL, Albuquerque, N.M. 1 Lowering Target Initial Temperature to
- December 5-6, 2002 HAPL Program Workshop, NRL, Washington, D.C. 1 Enhancing Target Survival
- January 25, 2008/ARR 1 Heat and Mass Transfer in Fusion Energy
- Nov 5-9, 2006 IAEA meeting, Vienna, Austria Target and Chamber Technologies for Direct-Drive
- July 14, 2006/ARR ARIES-CS Compact Stellarator Power
- September 23, 2004/ARR ARIES-CS Power Core: Initial Scoping
- June 22-25, 2004/ARR ARIES-CS Overview and Engineering
- R&D PLAN FOR ADDRESSING THE THERMOMECHANICAL BEHAVIOR OF
- July 4, 2001 A. R. Raffray, et al., ARIES-AT Blanket and Divertor Design, SNECMA, Bordeaux, France 1
- Fusion Engineering and Design 84 (2009) 21452157 Contents lists available at ScienceDirect
- Progress in the ITER Blanket Design F. Elio, K. Ioki, L. Bruno, A. Cardella, Y. Gohar, M. Hechler,
- January 23, 2006/ARR Status of Engineering Effort on ARIES-CS
- February 5-6, 2004 HAPL meeting, G.Tech. 1
- Fusion Engineering and Design 55 (2001) 5595 Design and material issues for high performance
- Fusion Engineering and Design 3940 (1998) 377384 Design of the ITER EDA plasma facing components
- ELSEVIER Fusion Engineering and Design 28 (1995) 240-251 Engineering
- SiC/SiC Composite for an Advanced Fusion Power Plant Blanket A. R. Raffray', L. El-Guebaly', D. K. Sze3,M. Billone3, I. Sviatoslavsky', E. Mogahed', F. Najmabadi',
- Effect of Runaway Electrons and VDE's on ITER First Wall A. R. Raffray1, M. Akiba2, A. Cardella1, K. Ezato2, G. Federici1, K. Ioki1, R. Parker1, and L. Topilski3
- NEUTRONICS ANALYSIS OF A SELF-COOLED BLANKET FOR A LASER FUSION PLANT WITH MAGNETIC DIVERSION
- Exploratory Divertor Heat Load Studies for Compact Stellarator Reactors
- March 3-4, 2005 HAPL meeting, NRL 1
- An overview of the development of the first wall and other principal components of a laser fusion power plant
- LASER FUSION CHAMBER DESIGN James P. Blanchard1
- THERMAL BEHAVIOR AND OPERATING REQUIREMENTS OF IFE DIRECT-DRIVE TARGET A.R. Raffray
- Nov 13-15, 2006/ARR Engineering Design and Analysis of the
- Abstract. We have defined the characteristics of a target injection and tracking facility to validate the science and tech-
- October 24, 2001 1. Remaining Action Items on Dry Chamber Wall
- NUMERICAL AND EXPERIMENTAL ANALYSIS OF A FLUIDIZED BED FOR IFE TARGET LAYERING Kurt J. Boehm1
- Fusion Engineering and Design 43 (1998) 7592 The ITER port limiter design
- July 11, 2003 HAPL e-meeting. 1 Armor Design & Modeling Progress
- September 24-25, 2003 HAPL Program Meeting, UW, Madison 1
- January 1, 2002/ARR 1. "Overlap" Design Regions for IFE Dry Wall
- CONFIGURATION DESIGN AND MAINTENANCE APPROACH FOR THE ARIES-CS STELLARATOR POWER PLANT
- Numerical Analysis of using a Fluidized Bed as a Prototypic Mass Production Device for IFE Target Layering
- Journal of Nuclear Materials 141-143 (1986) 10-18 North-Holland, Amsterdam
- April 22, 2002/ARR 1. Concluding Sacrificial Liquid Film Activities
- December 6, 2000 A. R. Raffray, et al., Assessment of Dry Wall Material Configuration
- December 3-4, 2003/ARR,1 ARIES-CS Engineering Approach
- From One-of-a-Kind to 500,000 Per Day: The Challenge of Mass-Produced IFE Targets*
- June 14-15, 2005/ARR Status of ARIES-CS Power Core
- April 10, 2002 A. R. Raffray, et al., Dynamic Chamber Armor Behavior in IFE and MFE 1 Dynamic Chamber Armor Behavior in IFE and MFE
- ELSEVIER Fusion Engineering and Design 27 (1995) 240-246 Engineering
- October 27-28, 2004 HAPL meeting, PPPL Overview of the Components of an IFE Chamber
- Fusion Engineering and Design 45 (1999) 377407 Critical heat flux analysis and R&D for the design of the
- September 16, 2004/ARR ARIES-CS Power Core Options
- October 27-28, 2004 HAPL meeting, PPPL 1
- Breeding Blanket Concepts for Fusion and Materials Requirements
- November 8-9, 2005 1 Considerations for Small Chambers
- July 1, 2002/ARR Scoping Study of FLiBe Evaporation and
- September 24-25, 2003 HAPL Program Meeting, UW, Madison 1
- October 15-19, 2000 R. Schleicher, A. R. Raffray, and C. P. Wong, An Assessment of the Brayton Cycle..., TOFE 2000 An Assessment of the Brayton Cycle for High
- Journal of Nuclear Materials 187(1992) 1-31 North-Holland
- June19-21, 2000 Finalizing the ARIES-AT Blanket and Divertor Designs, ARIES Project Meeting/ARR ARIES-AT Blanket and Divertor Design
- Abstract. Tailored porous media is a proposed method of achieving higher heat transfer coefficients while seeking to
- ARR/ARIES meeting, UW, May 3-4/99 Advanced ARIES-RS Using SiC/SiC as Structural
- ELSEVIER Journal of Nuclear Materials 244 (1997) 101-130 RACLETTE: a model for evaluating the thermal response of
- Nov 13-14, 2001 A. R. Raffray, et al., Progress Report on Chamber Clearing Code Effort 1 Progress Report on Chamber Clearing Code
- IFSA, Kyoto, Japan, September 2001 1 Dry Chamber Wall Thermo-Mechanical Behavior
- IFE chamber dry wall materials response to pulsed X-rays and ions at power-plant level fluences
- June7-8, 2001 A. R. Raffray, et al., Completion of Assessment of Dry Chamber Wall Option Without Protective Gas,
- Thermal Loading of a Direct Drive Target in Rarefied Gas B. R. Christensen1
- Fusion Engineering and Design 46 (1999) 159175 Engineering design of the ITER blanket and relevant
- Eects of plasma disruption events on ITER rst wall materials A. Cardella a,*, H. Goreno a
- Initial Maintenance Assessment for ARIES-CS Power Plant X. R. Wang, S. Malang
- AN ASSESSMENT OF THE BRAYTON CYCLE FOR HIGH PERFORMANCE POWER PLANTS R. Schleicher A. R. Raffray C. P. Wong
- November 13-15, 2006 17th TOFE, Albuquerque 1
- April 23-24, 2009/ARR 1 Debriefing/New Results of ReNeW Themes
- September 4-5, 2008/ARR TRL Assessment of Fusion Power Plant
- 214 Journal of Nuclear Materials 173 (1990) 214-22X North-Holland
- OPTIMIZING THE OVERALL CONFIGURATION OF A HE-
- October 27-28, 2004 HAPL meeting, PPPL 1
- SOLID BREEDER BLANKET OPTION FOR THE ITER CONCEPTUAL DESIGN* Y. Cohar, H. Attaya, M.C. Billone, P. Finn, S. Majumdar, L.R. Turner
- Assessment of Chamber Concepts for Inertial Fusion Energy Power Plants The ARIES-IFE study
- ARIES-AT BLANKET AND DIVERTOR A. R. Raffray, M.S.Tillack, X. Wang L. El-Guebaly, I. Sviatoslavsky S. Malang
- June 2-3, 2004 HAPL meeting, UCLA 1
- The headers will be insert by the Publisher The headers will be insert by the Publisher
- MERLOT: a model for flow and heat transfer through porous media for high heat flux applications
- September 24-25, 2003 HAPL meeting, UW 1
- September 29, 2008 TOFE08, San Francisco 1 Laser IFE Direct Drive Chamber Concepts with
- This article was originally published in a journal published by Elsevier, and the attached copy is provided by Elsevier for the
- June 14-15, 2007/ARR Trade-Off Studies and Engineering Input to
- September 14-16, 2004/ARR CERAMIC BREEDER BLANKET
- MHD Analysis of Dual Coolant Pb-17Li Blanket for ARIES-CS C. Mistrangelo1
- May 6-7, 2003/ARR ARIES-CS Maintenance Scheme and Blanket
- Impact of Magnetic Diversion on Laser IFE Reactor Design and Performance
- Fusion Engineering and Design 46 (1999) 207220 ITER divertor, design issues and research and development
- IFE THICK LIQUID WALL CHAMBER DYNAMICS: GOVERNING MECHANISMS AND MODELING AND
- May 22-27, 2005 ISFNT-7, Tokyo, Japan Progress Towards Realization of a Laser IFE
- Aug. 8-9, 2006 HAPL meeting, GA Advanced Chamber Concept with Magnetic Intervention
- Fusion Engineering and Design 3940 (1998) 323331 High heat flux thermalhydraulic analysis of ITER divertor and
- September 3-4, 2003/ARR Initial Assessment of Maintenance Scheme for 2-
- Dec 20, 2006/ARR Overview of the Engineering Design and
- September 11, 2000 A. R. Raffray, et al., High Performance Blanket for ARIES-AT Power Plant, SOFT 2000
- Fusion Engineering and Design 85 (2010) 969973 Contents lists available at ScienceDirect
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- Please cite this article in press as: K.J. Boehm, et al., Modeling results for mass production layering in a fluidized bed, Fusion Eng. Des. (2011), doi:10.1016/j.fusengdes.2010.08.004
- A LITHIUM SELF-COOLED BLANKET FOR THE HAPL CONCEPTUAL INERTIAL CONFINEMENT REACTOR
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- ARR/April 8, 2008 Magnetic Intervention Dump Concepts
- June 20-21, 2005 Overview of Chamber/Blanket Work
- Fusion Engineering and Design 10 (1989) 47-55 47 North-Holland, Amsterdam
- Fusion Engineering and Design 46 (1999) 177183 ITER reference breeding blanket design
- IFE CHAMBER TECHNOLOGY STATUS AND FUTURE CHALLENGES W.R. Meier1
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- March 20-21, 2000 ARIES-AT Blanket and Divertor Design, ARIES Project Meeting/ARR Status ARIES-AT Blanket and Divertor
- June 2-3, 2004 HAPL meeting, UCLA 1
- Fusion Engineering and Design 86 (2011) 5165 Contents lists available at ScienceDirect
- A shaped First Wall for ITER R. Mitteau a,,1
- January 13, 2009/ARR International HHFC Workshop on Readiness
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- February 5-6, 2004 HAPL meeting, G.Tech. 1
