Abdou, Mohamed - Fusion Science and Technology Center, University of California at Los Angeles

• Fusion Engineering and Design 83 (2008) 771783 Contents lists available at ScienceDirect
• Fusion Engineering and Design 82 (2007) 22332238 Application of discrete element method to study mechanical
• EXPERIMENTAL & NUMERICAL STUDY OF CERAMIC BREEDER PEBBLE BED THERMAL DEFORMATION BEHAVIOR
• Fusion Engineering and Design 42 (1998) 299305 Integral experiment of induced radioactivity in D-T fusion
• Journal of Fusion Energy, VoL 4, Nos. 2/3, 1985 Panel Discussion
• Experimental study of turbulent supercritical open channel water flow as applied to the CLiFF concept
• Fusion Engineeringand Design 17 (1991)313-319 313 North-Holland
• Thermofluids and Thermomechanics Tasks and Facilities
• Fusion Engineering and Design 45 (1999) 145167 Exploring novel high power density concepts for attractive
• Nuclear Engineering and Design 126 (1991) 137-145 137 North-Holland
• Fusion Engineering and Design 42 (1998) 281288 The use of MNCP for neutronics calculations within large
• A current density conservative scheme for incompressible MHD flows at a low magnetic Reynolds number.
• Fusion Engineering and Design 81 (2006) 433441 An overview of US ITER test blanket module program
• THEORETICAL STUDY OF MIXED CONVECTION IN POLOIDAL FLOWS OF DCLL BLANKET N. Vetcha, S. Smolentsev and M. Abdou
• NUMERICAL MODELING FOR MULTIPHASE INCOMPRESSIBLE FLOW WITH PHASE CHANGE
• ASSESSMENT OF FIRST WALL AND BLANKET OPTIONS WITH THE USE OF LIQUID BREEDER C.P.C. Wong, S. Malang,1 M. Sawan,2 S. Smolentsev,3 S. Majumdar,4 B. Merrill,5 D.K. Sze,6 N. Morley,3
• ELSEVIER Fusion Engineering and Design 27 (1995) 111-153 Engineering
• CHAMBER TECHNOLOGY FY 02 / 03 / 04
• Detailed Information on Proposal for US-Monbusho Collaoration
• M.M. AbdouAbdou TBWGTBWG--13 Meeting13 Meeting
• Fusion Engineering and Design 81 (2006) 659664 Solid breeder test blanket module design and analysis
• MAGNETOHYDRODYNAMICS Vol. 42 (2006), No. 23, pp. 199206 VORTICITY GENERATION IN LOCALIZED
• Fusion Engineering and Design 13 (1991) 363-380 363 North-Holland
• MaterialSELSEVIER Journal of Nuclear Materials 210(1994)143-160 Modeling of tritium transport in ceramic breeder single crystal
• Fusion Engineering and Design 17 (1991) 73-78 73 North-Holland
• TRITIUM ANALYSIS OF A WATER-COOLED SOLID BREEDER BLANKET FOR ITER*
• Recent Advances in Chamber Science and Technology
• Journal of Fusion Energy, Vol. 21, No. 2, June 2002 ( 2003) 0164-0313/02/06000061/0 2003 Plenum Publishing Corporation
• Fusion Engineering and Design 5960 (2000) 567576 Novel liquid blanket configurations and their hydrodynamic
• Fusion Engineering and Design 81 (2006) 14651470 Influence of 2D and 3D convectiondiffusion flow on tritium
• Fusion Engineering and Design 81 (2006) 15431548 Exploring liquid metal plasma facing component (PFC)
• Nuclear Engineering and Design 63 (1981) 199-231 North-Hoiland Publishing Company
• A VARIABLE-DENSITY PROJECTION METHOD FOR INTERFACIAL FLOWS
• Fusion Engineering and Design 81 (2006) 11311144 Physics and technology conditions for attaining tritium
• ELSEVIER Nuclear Engineering and Design 146 (1994) 349-362 Engineed.ng
• The influence of a magnetic field on turbulent heat transfer of a high Prandtl number fluid
• Fusion Engineering and Design 81 (2006) 549553 Numerical analysis of MHD flow and heat transfer in a
• MFE Chamber Overview Mohamed Abdou
• EXPERIMENTAL MEASUREMENTS OF THE INTERFACE THERMAL CONDUCTANCE OF A LITHIUM METATITANATE PEBBLE BED
• OutboardInboard OutboardInboard
• Material System Thermomechanics Interactions (cont'd) International Collaboration: Role / Impact / Recognition
• Brief Overview of APEX Mohamed Abdou
• APEX Status and Future Directions Introductory Remarks
• )XQGDPHQWDO 7KHUPRIOXLG ([SHULPHQWV 0RGHOLQJ Subtask 3-1 of the US-Monbusho Collaboration Proposal
• Fusion Engineering and Design 81 (2006) 461467 An overview of dual coolant Pb17Li breeder first wall and blanket
• APEX Reference Document FY 2000 Technical Plan
• Journal of Materials Processing Technology 181 (2007) 206212 Experimental measurements of the effective thermal conductivity
• Fusion Engineering and Design 83 (2008) 18071812 Contents lists available at ScienceDirect
• Journal of Fusion Energy, Vol. 19, No. 1, March 2000 ( 2001) Review of the Fusion Materials Research Program
• Magnetic Toroidal Facility (MTOR) has
• Fusion Engineering and Design 83 (2008) 17881791 Contents lists available at ScienceDirect
• Fusion Engineering and Design 3940 (1998) 859864 Tritium processing system for the ITER Li/V Blanket
• Fusion Engineering and Design 18(1991)203-208 203 North-Holland
• INTERNATIONAL JOURNAL FOR NUMERICAL METHODS IN ENGINEERING Int. J. Numer. Meth. Engng 2007; 72:14901512
• Fusion Engineering and Design 18 (1991) 397-405 397 North-Holland
• MODEL FOR DETERMINING THE EFFECTIVE THERMAL CONDUCTIVITY OF PARTICLE BEDS WITH HIGH SOLID-TO-GAS THERMAL
• MAGNETOHYDRODYNAMICS Vol. 42 (2006), No. 2-3, pp. 225236 CURRENT APPROACHES TO MODELING
• EFFECTIVE THERMAL CONDUCTIVITY OF LITHIUM CERAMIC PEBBLE BEDS FOR FUSION BLANKETS: A REVIEW
• Fusion Engineering and Design 81 (2006) 3343 Overview of fusion nuclear technology in the US
• Fusion Engineering and Design 81 (2006) 607612 Experimental study of the interaction of ceramic breeder pebble
• Fusion Technology Working Group Presented by
• 401NUCLEAR ENGINEERING AND TECHNOLOGY, VOL.37 NO.5 OCTOBER 2005 OVERVIEW OF FUSION BLANKET R&D IN THE US OVER
• Fusion Engineering and Design 81 (2006) 15211526 Application of the level set method for multi-phase flow
• Journal of Fusion Energy, Vol. 18, No. 4, 1999 Report of the FEAC Inertial Fusion Energy Review Panel
• THERMAL ANALYSIS OF A SOLID BREEDER TBM UNDER ITER OPERATIONAL CONDITIONS A. Abou-Sena, A. Ying, M. Youssef, M. Abdou
• Numerical simulation of ceramic breeder pebble bed thermal creep behavior
• ELSEVIER Journal of Nuclear Materials 212-215 (1994)885-890 Effect of external pressure on particle bed effective
• Fusion Engineering and Design 17 (1991) 165-170 165 North-Holland
• Brief Remarks on Status and Progress
• Fundamental Thermofluid Experiments & Modeling Subtask 3-1 of the DOE-Monbusho Collaboration Proposal
• Fusion Engineering and Design 54 (2001) 181247 On the exploration of innovative concepts for fusion
• Moving Beyond Prediction to Control Free Surface, Turbulence, and Magnetohydrodynamics
• Recent Advances in Chamber Science and Technology
• U.S. PLANS AND STRATEGY FOR ITER BLANKET TESTING , M. Sawan4
• Fusion Engineering and Design 72 (2004) 12 This special issue is devoted to articles summarizing
• Application of the ``Ke'' model to open channel flows in a magnetic field
• Fusion Engineering and Design 3940 (1998) 651657 Analysis of thermomechanical interactions and properties of
• Thermal and mechanical properties of ceramic blanket particle bed materials: Numerical derivation
• Fusion Engineering and Design 42 (1998) 555561 Scaling criteria for IFE liquid wall protection scheme simulation
• U.S. PARTICIPATION IN THE ITER TEST BLANKET MODULE (TBM) PROGRAM
• TOWARD AN INTEGRATED SIMULATION PREDICTIVE CAPABILITY FOR FUSION PLASMA CHAMBER SYSTEMS
• MEASUREMENTS OF SPECIFIC ELECTRICAL CONTACT RESISTANCE BETWEEN SIC AND LEAD-LITHIUM EUTECTIC ALLOY
• MAGNETOHYDRODYNAMICS Vol. 45 (2009), No. 2, pp. 233238 EXPERIMENTAL STUDY OF MHD FLOWS IN A
• Available online at www.sciencedirect.com Fusion Engineering and Design 83 (2008) 557572
• DEVELOPMENT OF PIV TECHNIQUE UNDER MAGNETIC FIELDS AND MEASUREMENT OF TURBULENT PIPE FLOW OF FLIBE SIMULANT FLUID
• Fusion Engineering and Design 82 (2007) 22172225 Integrated thermo-fluid analysis towards helium flow
• VALIDATION CASE RESULTS FOR 2D AND 3D MHD SIMULATIONS Ming-Jiu Ni1, 3
• A current density conservative scheme for incompressible MHD flows at a low magnetic Reynolds number.
• Accepted Manuscript Numerical Characterization of Thermo-mechanical Performance of Breeder
• Fusion Engineering and Design 81 (2006) 393405 Breeding Blanket Modules testing in ITER
• Fusion Engineering and Design 81 (2006) 601606 Study of heat transfer enhancement/suppression for molten
• Fusion Engineering and Design 81 (2006) 14511458 Numerical study of MHD effect on liquid metal free
• J. Fluid Mech. (2006), vol. 553, pp. 227252. c 2006 Cambridge University Press doi:10.1017/S0022112006008810 Printed in the United Kingdom
• Vorticity generation in creeping flow past a magnetic obstacle Centro de Investigacin en Energa, UNAM, Apartado Postal 34, Temixco, Morelos 62580, Mexico
• MHD EFFECTS ON HEAT TRANSFER IN A MOLTEN SALT BLANKET Sergey Smolentsev, Reza Miraghaie, Mohamed Abdou
• EXPERIMENTAL ANALYSIS OF SOAKER HOSE CONCEPT FOR FIRST WALL/DIVERTOR APPLICATION
• Engineering Scaling Requirements for Solid Breeder Blanket Testing A. Ying, S. Sharafat, M. Youssef, J. An, R. Hunt, P. Rainsberry, M. Abdou
• Open-surface MHD flow over a curved wall in the 3-D thin-shear-layer approximation
• Fusion Engineering and Design 73 (2005) 8393 Code development for analysis of MHD pressure drop reduction
• Nuclear Instruments and Methods in Physics Research A 544 (2005) 111116 Vapor condensation study for HIF liquid chambers
• Fusion Engineering and Design 72 (2004) 6381 Thermofluid modeling and experiments for free surface
• Impact of material system thermomechanics and thermofluid performance on He-cooled ceramic
• EXPERIMENTAL INVESTIGATION AND ANALYSIS OF THE EFFECTIVE THERMAL PROPERTIES OF BERYLLIUM PACKED BEDS
• 3D MHD free surface fluid flow simulation based on magnetic-field induction equations
• MATERIALS ENGINEERING KEYWORDS: beryllium, stainless
• Modeling and analysis of time-dependent tritium transport in lithium oxide
• Fusion Engineering and Design 42 (1998) 155172 Assessment of dose rate profiles and accessibility inside the
• Fusion Engineering and Design 42 (1998) 267273 Benchmark experiment on bulk shield of SS316/water with
• Fusion Engineering and Design 3940 (1998) 759764 Mechanical behavior and design database of packed beds for
• Fusion Engineering and Design 42 (1998) 289297 Nuclear heating measurements for SS-316, copper, graphite,
• Fusion Engineering and Design 42 (1998) 319327 Validation of induced radioactivity calculations for candidate
• Journal of Fusion Energy, Vol. 16, No. 4, 1997 Report from the Planning Workshop for the Fusion Energy
• ELSEVIER Journal of Nuclear Materials 212-215 (1994)1003-1009 An assessment of models for tritium release from ceramic
• ELSEXIER Journal of Nuclear Materials 212-215 (1994) 961-965 Modeling of tritium release from beryllium in fusion
• Journal of Fusion Energy, VoL 11, Nos. 3/4, 1992 Report of Panel 1: The Appropriate Scope and Mission of
• Fusion Engineering and Design 18 (1991) 387-395 387 North-Holland
• Fusion Engineering and Design 18 (1991) 275-280 275 North-Holland
• Fusion Engineering and Design 18 (1991) 265-274 265 North-Holland
• CONFERENCES AND SYMPOSIA FUSION REACTOR DESIGN IV
• SPECIAL TOPIC INTERNATIONAL TOKAMAK REACTOR -
• Overview of US Liquid Metal Blanket R&D ActivitiesR&D Activities
• Scientific and Engineering Challenges and New Strategy for Development of gy p
• Perspective on Fusion Energy Presentation at TWAS-ARO Meeting Bibliotheca Alexandria
• Material Issues for the US ITER-TBM Program Part I: US Strategy and Outline of Suggested Material EffortPart I: US Strategy and Outline of Suggested Material Effort
• APPENDIXAPPENDIX Mohamed Abdou
• OutboardInboard OutboardInboard
• Interfacial Transport Test section length = 4 m
• Chamber Technology Goals Used in APEX to Calibrate New Ideas and Measure Progress
• Fusion Science and Technology Research Program (VLT Programs)
• Overview of APEX Mohamed Abdou
• Introductory Remarks and Key Technical and Management Questions
• APEX Overview: Part I Opportunities and Challenges in Free-
• Plasma Chamber and APEX Budget Plans for FY 2000 (and FY 2001)
• Fusion Engineering and Design 23 (1993)251-297 251 North-Holland
• 1Gyeongbokgung Challenges and Development Pathways for
• This article appeared in a journal published by Elsevier. The attached copy is furnished to the author for internal non-commercial research
• The International Standing Committee for FNST All Participants to ISFNT-9
• FliHy experimental facilities for studying open channel turbulent flows and heat transfer
• Fusion Engineering ScienceFusion Engineering Science Subgroup ASubgroup A Subgroup BSubgroup B
• SPECIAL TOPIC INTERNATIONAL TOKAMAK REACTOR -PHASE I
• TRITIUM SYSTEMS KEYWORDS: tritium fuel cycle, re-
• MAGNETOHYDRODYNAMIC AND THERMAL ISSUES OF THE SiCf0SiC FLOW CHANNEL INSERT
• Keynote Presentation at ISFNT-9, Dalian, China, October 12, 2009 Mohamed Abdou
• Fusion Engineering and Design 42 (1998) 537548 Chamber technology concepts for inertial fusion energy--three
• Fusion Engineering and Design 4950 (2000) 605611 Numerical and experimental prediction of the
• EXPERIMENTAL AND COMPUTATIONAL SIMULATION OF FREE JET CHARACTERISTICS UNDER TRANSVERSE FIELD GRADIENTS
• Fusion Engineering and Design 17 (1991) 131-137 131 North-Holland
• materialsELSEVIER Journal of Nuclear Materials 233-237 (1996) 847-851 Experimental evaluation of the interface heat conductance between
• Fusion Engineering and Design 42 (1998) 235245 Verification of ITER shielding capability and FENDL data
• Fusion Engineering and Design 83 (2008) 10821086 Contents lists available at ScienceDirect
• Summary of FNST Survey : Thoughts of the Community on progress, concerns, and next steps in FNST
• Journal of Fusion Energy, Vol. 13, Nos. 2/3, 1994 Fusion Energy Advisory Committee (FEAC): Panel 7 Report
• Liquid Wall Science in other Scientific Pursuits and Applications
• Fusion Engineering and Design 5152 (2000) 8591 Analysis of tritium kinetics of SIBELIUS beryllium
• Fusion Engineering and Design 42 (1998) 307318 Experimental measurement of nuclear heating in a
• Characterization of the effect of Froude number on surface waves and heat transfer in inclined turbulent
• Fusion Engineering and Design 83 (2008) 13351339 Contents lists available at ScienceDirect
• MODELING FOR FREE SURFACE FLOW WITH PHASE CHANGE XIAOYONG LUO, MINGJIU NI, ALICE YING, M. ABDOU
• Liquid Walls Innovative Concepts for First Walls and Blankets
• ELSEVIER Journal of Nuclear Materials 212-215 (1994) 993-997 Analysis of BEATRIX-II tritium release results using MISTRAL
• MAGNETOHYDRODYNAMICS Vol. 46 (2010), No. 1, pp. 99111 NUMERICAL AND EXPERIMENTAL STUDIES
• Fusion Engineering and Design 72 (2004) 334 Progress on the modeling of liquid metal, free surface,
• Engineering ELSEVIER Fusion Engineering and Design 29 (1995) 3-17
• Nuclear Instruments and Methods in Physics Research A 544 (2005) 337341 Three-dimensional modeling of slab liquid jets used
• IAEA-CN-60/F-16 REQUIREMENTS AND DESIGN ENVELOPE
• Test blanket modules in ITER: An overview on proposed designs and required DEMO-relevant materials
• A novel diagnostic for time-resolved spectroscopic argon and lithium density measurements
• Fusion Engineering and Design 81 (2006) 15351541 Validation strategies of HIMAG in interfacial flow
• Journal of Fusion Energy, Vol. 15, Nos. 3/4, 1996 Report of the FESAC Inertial Fusion Energy Review Panel
• Fusion Engineering and Design 72 (2004) 3562 Exploratory studies of flowing liquid metal divertor options for
• Understanding mechanisms of flow instability leads to improved control of
• Fusion Engineering and Design 4950 (2000) 719725 Heat deposition, damage, and tritium breeding
• NUCLEAR ANALYSIS OF A TOKAMAK EXPERIMENTAL POWER REACTOR
• A STUDY OF LIQUID METAL FILM FLOW, UNDER FUSION RELEVANT MAGNETIC FIELDS M. Narula, A. Ying and M.A. Abdou
• Remarks on Liquid Wall Research Mohamed Abdou
• Effect of initial turbulence intensity and velocity profile on liquid jets for IFE beamline protection
• 3D Micromechanical modeling of packed beds Zi Lu, Mohamed Abdou *, Alice Ying
• EXPERIMENTAL INVESTIGATION OF TURBULENT HEAT TRANSFER OF HIGH PRANDTL NUMBER FLUID FLOW UNDER STRONG MAGNETIC FIELD
• TEMPORAL SECOND-ORDER ACCURACY OF SIMPLE-TYPE METHODS FOR INCOMPRESSIBLE
• For Distribution at the Fusion Summer Study Snowmass Colorado, July 1999 Merits & Issues for Liquid Wall Concepts
• Fusion Engineering and Design 85 (2010) 11291132 Contents lists available at ScienceDirect
• Fusion Engineering and Design 85 (2010) 16811688 Contents lists available at ScienceDirect
• Fusion Engineering and Design 85 (2010) 12961300 Contents lists available at ScienceDirect
• Fusion Engineering and Design 85 (2010) 17111715 Contents lists available at ScienceDirect
• Fusion Engineering and Design 85 (2010) 18241828 Contents lists available at ScienceDirect
• Fusion Engineering and Design 85 (2010) 10071011 Contents lists available at ScienceDirect
• Fusion Engineering and Design 85 (2010) 14881491 Contents lists available at ScienceDirect
• CONP-811040--200 D E M 008509
• Journal of Nuclear Materials103& 104(1981)41-50 North-HollandPublishingCompany
• STARFIRE -INITIAL CONCEPTUAL DESIGN OFA COMMERCIAL TOKAMAK POWER PLANT C.C. Baker, M.A. Abdou, D.DeFreece, C.Trachsel,
• The Prometheus IFE Reactor Cavity" M. S. Tillack, Pi.Ghoniem, A. R. Raffray, M. A. Abdon, and the Prometheus Team
• JournalofNuclear Materials 85 & 86(1979)57-64 0 North-HollandPublishingCompany
• Distribution Category: Magnetic Fuaion Energy
• MEASUREMENT AND CALCULATION OF DOSES IN AND AROUND NORTH-WEST LABYRINTH IN TFTR TEST CELlL SHIELDING FOR D-T OPERATION
• IAEA-CN-33/G 1-2 MAJOR DESIGN FEATURES OF THE
• IAEA-CN-33/G 3-3 ENGINEERING DESIGN OF A
• Distribution Category: Magnetic Fusion Energy
• Nuclear Analysis of the First Wall/Blanket/Shielld of Inertial Fusion Energy Reactors
• UCRL-JC-117018 Utility of the U.S.NationalI nition Facilityfor
• INTERNATIONAL ATOMIC ENERGY AGENCY THIRD TECHNICAL COMMITTEE MEETING AND WORKSHOP
• IAEA-CN-38/E-1 STARFIRE -A CONCEPTUAL DESIGN
• Paper presented at Che Ninth Symposium on Engineering Problems of Pus ion Research, Chicago, Illinois, October 26-29, 1981; also for
• DESIGN AND ANALYSIS OFTHE PROMETHEUS WETIED WALL IFEREACTOR CAVITY * M. S.Tillack, M. Z. Youssef, M. A. Abdou, A. R. Raffray, J. Eggleston, A. El-Azab,
• COIIF-840 4137--1 TRITIUM BREEDING MATERIALS D E 8 4 010521
• Research and Development Assessments for Prometheus eavy Ion and Laser Driven Inertial Fusion Energy Reactor Designs
• Fusion Engineering and Design 5152 (2000) 10951101 Progress and critical issues for IFE blanket and
• AN ASSESSMENT OF THE BASE BLANKETFOR ITER A. R. Raffray, M. A, Abdou, and A. Ying, Mechanical, Aerospace and Nuclear
• IFE Chamber Technology Testing Program In NIF and Chamber Development Test Plan Mohamed A. Abdou
• COMPUTATIONS OF NUCLEAR RESPONSE FUNCTIONS WITH MACK-IV M. A. Abdou and Y. Gohar
• ITER BLANKET AND SHIELD STUDIES FOR HIGH ASPECT RATIO DESIGN OPTION* Y .Gohar, H. Attaya, M. Billone,C. Johnson,J. Kopasz, S.Majumdar, R. Mattas, and D.L. Smith
• IAEA-CN-60/F-16 REQUIREMENTS AND DESIGN ENVELOPE
• Journal of Nuclear Materials 72 (1978) 147-167 0 North-Holland Publishing Company