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	8:00- 8:15	Kulcinski	Opening Statement and Program Overview
PL-I-1	8:15-8:45	Schmitt	Large Energy Development Projects: Lessons Learned from Space and Politics
PL-I-2	8:45-9:10	Davies	US MFE National Picture
PL-I-3	9:10-9:35	Keane	Status of the US Inertial Confinement Fusion Program
PL-I-4	9:35-10:00	Seki	Overview of Recent Japanese Activities in Fusion Technology

O-I-1.1	10:30-10:48	Kellman	Advanced Control Techniques and High Performance Discharges on DIII-D
O-I-1.2	10:48-11:06	Gasparotto	W7-X Progress
O-I-1.3	11:06-11:24	Fonck	Recent progress of Low Aspect Ratio Machines
O-I-1.4	11:24-11:42	Kaye	Progress in Technology at JET
O-I-1.5	11:42-12:00	Simmons	Recent Progress in NCSX Design and Fabrication

O-I-2.1	10:30-10:48	Sethian	The Path to Develop Laser Fusion Energy
O-I-2.2	10:48-11:06	Jones	KrF Laser Drivers for Initial Fusion Energy
O-I-2.3	11:06-11:24	Bibeau	Diode-Pumped Solid-State Laser Driver for Inertial Fusion Energy
O-I-2.4	11:24-11:42	Dragojlovic	Effects of Chamber Geometry and Gas Properties on Hydrodynamic Evolution of IFE Chambers
O-I-2.5	11:42-12:00	Blanchard	Development of a Dry Wall Concept for Laser IFE Chamber

O-I-3.1	10:30-10:48	Sheffield	Future World Energy Demand and Supply: China and India and the Potential Role of Fusion Energy
O-I-3.2	10:48-11:06	Petti	Status of Safety and Environmental Activities in the US Fusion Program
O-I-3.3	11:06-11:24	El-Guebaly	Evolution of Clearance Standards and Implications for Radwaste Management of Fusion Power Plants
O-I-3.4	11:24-11:4	Taylor	Key Issues for the Safety and Licensing of Fusion
O-I-3.5	11:42-12:00	D'haeseleer	Fusion Power; a Strategic Choice for the Future Energy Provision. Why is so Much Time Wasted for Decision Making?

P-I-1	Shestakov	In-pile Assemblies for Testing of Li2TiO3 Lithium Ceramic Blanket
P-I-2	Tazhibayeva	KTM Experimental Complex Project Status
P-I-3	Nygren	Thermal Modeling of the Sandia Flinabe (LiF-BeF2-NaF) Melt Experiment
P-I-4	Maebara	Power-balance control by Slug Tuner for the 175MHz RFQ linac in IFMIF project
P-I-5	McDonald	Measurement of the Melting Point Temperature of Several Lithium-Sodium-Beryllium Fluoride Salt (FLiNaBe) Mixtures
P-I-6	Ranjan	Investigation of hydrodynamic instabilities in shock-accelerated flows for ICF
P-I-7	Debonnel	Visual Tsunami: A versatile, user-friendly radiation hydrodynamics design code
P-I-8	Debonnel	Validation of the Tsunami code through the Condensation Debris Experiment
P-I-9	Debonnel	Practical ablation models for IFE chamber design

P-I-10	Petzoldt	Target Injection Tracking and Position Prediction Update
P-I-11	Vermillion	Fabrication of a Full Density Polyvinylphenol Overcoat for IFE Targets
P-I-12	Frey	Rep-Rated Target Injection for Inertial Fusion Energy
P-I-13	Olson	Target Physics Scaling for Z-Pinch Inertial Fusion Energy
P-I-14	Rose	Large-Area Electron Beam Diode and Gas Cell Design for a KrF Laser IFE System
P-I-15	Wu	Electron Injection for Space - Charge Contron in HIBF
P-I-16	Calderoni	Experimental study of voltage breakdown over flibe liquid surfaces for IFE applications
P-I-17	Hahn	Characterization of Arc Generated Plasma Interactions with a Liquid Metal Medium
P-I-18	Bardet	Liquid Vortex Shielding for Fusion Energy Applications
P-I-19	Christensen	Thermal Loading of a Direct-Drive Target in Rarefied Gas
P-I-20	Christensen	Modeling DT Vaporization and Melting in a Direct-Drive Target

P-I-21	Muroga	Neutronics Investigation into Lithium/Vanadium Test Blanket Modules
P-I-22	Yamauchi	Estimation of Radioactivities in the IFMIF Liquid Lithium Loop due to the Erosion and Corrosion of Target Back-wall
P-I-23	Sato	Neutronics experiments using small partial mockup of the ITER test blanket module with solid breeder
P-I-24	Tanaka	Tritium Self-Sufficiency and Neutron Shielding Performance of Liquid Li Self-Cooled Helical Reactor
P-I-25	El-Guebaly	Views on Neutronics and Activation Issues Facing Thick Liquid-Protected IFE Chambers
P-I-26	Youssef	Activation Analysis for Two Molten Salt Dual-Coolant Blanket Concepts for the US Demo Reactor
P-I-27	Youssef	On the Strategy and Requirements for Neutronics Testing in ITER
P-I-28	Wang	Three-Dimensional Modeling of Complex Fusion Devices Using CAD-MCNP Interface

P-I-29	Gohar	Blanket Design and Optimization Demonstrations of the First Wall/Blanket/Shield Design and Optimization System
P-I-30	Sviatoslavsky	A Self-Cooled Lithium Blanket Concept for the HAPL Conceptual Laser IFE Power Plant
P-I-31	Wang	Maintenance Approaches for ARIES-CS Power Core
P-I-32	Rochau	Manufacturing Concepts for an IFE Power Plant Using Z-Pinch Technology
P-I-33	Viola	National Compact Stellarator Experiment (NCSX) Vacuum Vessel Manufacture
P-I-34	Takeno	Experiments to Improve Power Conversion Paramters in a TWDEC Simulator
P-I-35	Yasaka	Experimental Simulation on Particle Discrimination for Direct Energy Conversion
P-I-36	Zhao	Optimized Helium-Brayton Power Conversion for Fusion Energy Systems

P-I-37	Tsuchiya	Radiation Induced Conductivity of Proton Conductive Ceramics
P-I-38	Wakai	Effect of Initial Heat Treatment on DBTT of F82H Steel Irradiated by Neutrons
P-I-39	Nagasaka	Tungsten Coating on Low Activation Vanadium Alloy by Plasma Spray Process
P-I-40	Maday	Hydrogen Embrittlement Susceptibility of Conventional and Reduced Activation 9Cr Steels
P-I-41	Ogiwara	Synergistic Influence of Displacement Damage and Helium/dpa on Microstructural Evolution and Radiation-Induced Hardening of Reduced Activation Ferritic/Martensitic Steel
P-I-42	Sawada	Corrosion Behavior of Insulator Coatings for Fusion Reactor Lithium Blankets
P-I-43	Ozawa	Cavity Swelling Behavior in SiC/SiC under Charged Particle Irradiation
P-I-44	Sharafat	An Innovative Solid Breeder Material for Fusion Applications
P-I-45	Hashimoto	Helium Retention of Ion-irradiated and annealed Tungsten Foils
P-I-46	Sharafat	Elasto-plastic Dislocation-based Constitutive Modeling within Full Scale 3-D Thermo-mechanical FEM Analysis of an ITER-TBM

P-I-47	Senkowicz	Upper Critical Field Improvement in MgB2 by Mechanical Alloying
P-I-48	Hashizume	Jointing Performance in HTc SC Tape for remountable magnet system
P-I-49	Bromberg	Advanced Options for Modular Stellarator Magnets
P-I-50	Jewell	Sn content and alloying effects in ITER Nb3Sn strand
P-I-51	Titus	Seismic Analysis of the National Compact Stellarator (NCSX)
P-I-52	Freudenberg	Non-linear Analysis of the Modular Coil Windings for the National Compact Stellarator Experiment
P-I-53	Myatt	Electromagnetic Linear Structural Analysis of the National Compact Stellarator Experiment (NCSX) Modular Coil System
P-I-54	Kozub	Testing of NCSX Composite Coil Material Properties
P-I-55	Titus	Structural Analysis of the JET TAE Antenna
P-I-56	Williamson	Wire Debris Modeling of the Z-Accelerator
P-I-57	Dahlgren	Structural Analysis of the NCSX Vacuum Vessel
P-I-58	Doshi	Design Requirement, Qualification Tests and Integration of a Thin Solid Lubricant Film of MoS2 for Cold Mass Support Structure of the Steady State Superconducting Tokamak SST-1

O-I-4.1	3:30-3:50	Najmabadi	ARIES-IFE Assessment of Operational Windows for IFE Power Plants
O-I-4.2	3:50-4:10	Cook	European Fusion Power Plant Studies
O-I-4.3	4:10-4:30	Wilson	Synergies between the Generation IV and Advanced Fusion Power Plants
O-I-4.4	4:30-4:50	Meade	FIRE, A Test Bed for ARIES-RS/AT Advanced Physics and Plasma Technology
O-I-4.5	4:50-5:10	Rochau	Progress Toward Development of an IFE Power Plant Using Z-Pinch Technology
O-I-4.6	5:10-5:30	Dolan	Helical Fusion Power Plant Economics Studies

O-I-5.1	3:30-3:50	Chuyanov	Interface of Blanket Testing and ITER design
O-I-5.2	3:50-4:10	Abdou	Blanket Testing Issues and Requirements
O-I-5.3	4:10-4:30	Boccaccini	European Test strategy for Test blanket modules to be tested in ITER
O-I-5.4	4:30-4:50	Enoeda	Plans and Strategy for ITER Blanket Testing in Japan
O-I-5.5	4:50-5:10	Morley	Thermofluid Magnetohydrodynamic Issues for Liquid Breeders
O-I-5.6	5:10-5:30	Ying	Engineering Scaling Requirements for Solid Breeder Blanket Testing

O-I-6.1	3:30-3:50	Schultz	Fusion Production of Hydrogen; How Fusion Energy Can Fuel the Hydrogen Economy
O-I-6.2	3:50-4:10	Konishi	Potential Fusion Market for Hydrogen Production Under Environmental Constraints
O-I-6.3	4:10-4:30	Stacey	Tokamak Neutron Source Based Spent Nuclear Fuel Transmutation Reactors
O-I-6.4	4:30-4:50	Yoshikawa	Research and Development of Landmine Detection System by a Compact Fusion Neutron Source
O-I-6.5	4:50-5:10	Miley	RF Ion Source-Driven IEC Design and Operation
O-I-6.6	5:10-5:30	Santarius	Overview of University of Wisconsin Inertial-Electrostatic Confinement Fusion Research

PL-II-1	8:00-8:30	Dean	Historical Perspective on the United States Fusion Program
PL-II-2	8:30-9:00	Iotti	The Role of Industry in Fusion Development
PL-II-3	9:00-9:30	Wuest	The National Ignition Facility: Laser Performance and First Experiments
PL-II-4	9:30-10:00	Andreani	European Technological Effort in Preparation for ITER Construction

O-II-1.1	10:30-10:48	Najmabadi	Exploration of Compact Stellarators as Power Plants: Initial Results from ARIES-CS Study
O-II-1.2	10:48-11:06	Garabedian	Reactors with Stellarator Stability and Tokamak Transport
O-II-1.3	11:06-11:24	Lyon	Optimization of Stellarator Reactor Parameters
O-II-1.4	11:24-11:42	Raffray	Attractive Design Approaches for a Compact Stellarator Power Plant
O-II-1.5	11:42-12:00	El-Guebaly	Benefits of Radial Build Minimization and Requirements Imposed on ARIES-CS Stellarator Design

O-II-2.1	10:30-10:48	Goodin	Demonstrating a Target Supply for Inertial Fusion Energy
O-II-2.2	10:48-11:06	Norimatsu	Development of target fabrication and injection for Laser Fusion in Japan
O-II-2.3	11:06-11:24	Moses	High Energy Density Simulations for IFE Reactor Design
O-II-2.4	11:24-11:42	Callahan	Target Designs for Heavy Ion Inertial Fusion Energy
O-II-2.5	11:42-12:00	Streit	Fabrication of Overcoated Divinylbenzene (DVB) Shells

O-II-3.1	10:30-10:48	Hosogane	Recent Technological Progress for Advanced Tokamak Research in JT-60U and JFT-2M
O-II-3.2	10:48-11:06	Lucon	An Integrated Approach to Fusion Material Research at SCK-CEN
O-II-3.3	11:06-11:24	Cadwallader	Comparison of Tritium Component Failure Rate Data
O-II-3.4	11:24-11:42	Burruss	Development in Remote Collaboration and Distributed Computing
O-II-3.5	11:42-12:00	Putvinskaya	Information Technology Systems for Fusion Industry and ITER project

P-II-1	Machkour	Magnetic method To characterize the Current Densities in a Breaker Arc
P-II-2	Scoville	Automatic Fault-Checking System on the DIII-D Tokamak
P-II-3	Oliva	Four Barrel Pellet Injector Upgrade on the Madison Symmetric Torus (MST)
P-II-4	Kowbel	Hybrid AL/SiC composite optics for IFE applications
P-II-5	Cengher	EBW coupling using a twin waveguide launcher on the MST reversed field pinch
P-II-6	Matsuura	Effect of Nuclear Elastic Scattering on Neutral Beam Injection Heating in Thermonuclear Plasmas
P-II-7	Deranian	Integrated Plasma Control in Next-Generation Devices Using DIII-D Modeling and Simulation Approaches
P-II-8	Akino	Long pulse operation of NBI system for JT-60U
P-II-9	Walker	Nonlinear Methods for Current Limit Constraint Satisfaction in Tokamak Plasma Shape Control
P-II-10	Welander	Nonrigid, Linear Plasma Response Model Based on Perturbed Equilibria for Axisymmetric Tokamak Control Design
P-II-11	Ebara	Numerical Study on behavior of hydrogen ice pellet in drift tube
P-II-12	Mau	Alpha Particle Loss and Heat Load Assessment for Compact Stellarator Reactors
P-II-13	Kamberov	Correlations of ELM frequency with pedestal plasma parameters

P-II-14	Cheng	Performance Characteristics of Actinide-Burning Fusion Power Plants
P-II-15	Cipiti	The Production of 13N using Beam-Target D-3He Fusion
P-II-16	Takamatsu	Improvement of an Inertial Electrostatic Confinement Fusion Device
P-II-17	Osawa	Optimal Position of Ion Source for High Performance of IEC
P-II-18	Osawa	Numerical Study on Hollow Cathode Discharge of IEC Fusion
P-II-19	Ueno	Measurement of Ion Energy Distributions in a Cylindrical Inertial Electrostatic Confinement Fusion (C-IECF) Device
P-II-20	Yoshinaga	Fast Neutral Generation by Charge Exchange Reaction and its Effect on Nuclear Burning in Inertial Electrostatic Confinement Fusion Systems
P-II-21	Noborio	One Dimensional Simulation of an Inertial Electrostatic Confinement Fusion at Low Gas Pressure Operation
P-II-22	Yamamoto	Influence of the Electrode Spacing on the Performance Characteristics of Inertial Electrostatic Confinement Fusion in Low Pressure Operation
P-II-23	Yamauchi	Pulsed Operation of a Compact Fusion Neutron Source Using a High-Voltage Pulse Generator Developed for Landmine Detection
P-II-24	Radel	Implantation of D+ and He+ in Candidate Fusion First Wall Materials
P-II-25	Radel	Optimizing Neutron Production Rates from D-D Fusion in an Inertial Electrostatic Confinement Device
P-II-26	Murali	D-3He Proton Energy Distribution from an IEC Device
P-II-27	Piefer	Design of an Ion Source for Low Pressure IEC Operation
P-II-28	Nebel	An Electrostatic Confinement Experiment to Explore the Periodically Oscillating Plasma Sphere

P-II-29	El-Guebaly	Initial Activation Assessment for ARIES Compact Stellarator Power Plant
P-II-30	Cadwallader	Compressed Gas Safety for Experimental Fusion Facilities
P-II-31	Savercool	Activities of the US-Japan Safety Monitor Joint Working Group
P-II-32	Cadwallader	The Worker Exposure Failure Modes and Effects Analysis

P-II-33	Shin	Design Constraints for Liquid-Protected Divertors
P-II-34	Hirooka	Particle Control by Lithium-Gettered Moving-Surface PFCs in Steady State Magnetic Fusion Devices
P-II-35	Karditsas	Optimization of the HETS He-cooled divertor concept:Thermal-fluid and structural analysis
P-II-36	Morikawa	Experimental Analysis of Soaker Hose Concept for First Wall/Diverter Application
P-II-37	Latkowski	Pulsed X-Ray Exposures and Modeling for Tungsten as an IFE First Wall Material
P-II-38	Whyte	DIONISOS: A new experiment on the dynamics of plasma-surface interactions
P-II-39	Stubbers	The Flowing Liquid-Metal Retention Experiment (FLIRE) Results
P-II-40	Durbin	Impact of Boundary-Layer Cutting on Free-Surface Behavior in Turbulent Liquid Sheets
P-II-41	Durbin	Flow Conditioning Design in Thick Liquid Protection
P-II-42	Debonnel	Visual Tsunami modeling of ballistic and assisted-pinch heavy-ion target chambers

P-II-43	Novak	Experimental and Numerical Investigation of Mist Cooling for the Electra Hibachi
P-II-44	Yin	Prediction of Pressure Drop in the ITER Divertor Cooling Channels
P-II-45	Pampin-Garcia	Heat transfer issues in finite element analysis of PPCS model bounding accidents
P-II-46	Chiba	Experimental Research on Heat Transfer Enhancement for High Prandtl-Number Fluid
P-II-47	Mignot	Initial Study of Supercritical Fluid Blowdown
P-II-48	Okumura	Evaluation of flow structure in packed-bed tube by visualization experiment
P-II-49	Togashi	Heat Transfer Enhancement Technique with Copper Fiber Porous Media
P-II-50	Modesto-Beato	Thermal Analysis of the Z-Pinch Power Plant Concept
P-II-51	Luo	Modeling Development for Free Surface Flow with Phase Change
P-II-52	An	Experimental & Numerical Study of Ceramic Breeder Pebble Bed Thermal Deformation Behavior
P-II-53	Abou-Sena	Effects of Pulsed Operation Conditions on Effective Thermo-physical Properties of Ceramic Breeder Pebble Beds
P-II-54	Dritselis	Magnetohydrodynamic Turbulent Channel Flow with Transverse Square Cylinders
P-II-55	Smolentsev	MHD Effects on Heat Transfer in a Molten Salt Blanket
P-II-56	Narula	Study of Liquid Metal Film Flow Characteristics under Fusion Relevant Magnetic Fields

O-II-4.1	3:30-3:50	Antaya	The ITER CS Magnet System
O-II-4.2	3:50-4:10	Ulrickson	Proposed US Participation in Fabrication of the First Wall and Shield for ITER
O-II-4.3	4:10-4:30	Rasmussen	ITER Ion Cyclotron Heating and Fueling Systems
O-II-4.4	4:30-4:50	Vernon	ITER ECH System and US ECH Program for ITER
O-II-4.5	4:50-5:10	Petti	Future US ITER Safety Studies
O-II-4.6	5:10-5:30	Paffett	ITER Plasma Exhaust Processing System

O-II-5.1	3:30-3:50	Enoeda	Development of Solid Breeder Blanket at JAERI
O-II-5.2	3:50-4:10	Fischer	EU Blanket Design Activities and Neutronics Support Efforts
O-II-5.3	4:10-4:30	Wong	Assessment of Liquid Breeder First Wall and blanket Options for the DEMODesign
O-II-5.4	4:30-4:50	Sawan	Neutronics Assessment of Molten Salt Breeding Blanket Design Options
O-II-5.5	4:50-5:10	Sagara	Innovative Liquid Blanket Design Activities in Japan
O-II-5.6	5:10-5:30	Raffray	Ceramic Breeder Blanket for ARIES-CS

O-II-6.1	3:30-3:50	Olson	Development Path for Z Pinch IFE
O-II-6.2	3:50-4:10	Meier	Update on Progress and Challenges in the Development of Heavy Ion Fusion
O-II-6.3	4:10-4:30	Wurden	Overview of Magneto-Inertial Fusion
O-II-6.4	4:30-4:50	Mima	Present Status of Fast Ignition Research and Prospects of FIREX Project
O-II-6.5	4:50-5:10	Yu	The Modular Approach to Heavy-Ion Fusion
O-II-6.6	5:10-5:30	Peterson	Dynamics of Liquid-Protected Fusion Chambers

O-III-1.1	8:00-8:20	Zinkle	Overview of the US Fusion Materials Sciences Program
O-III-1.2	8:20-8:40	Diegele	European Fusion Materials Research Program - Recent Results and Future Strategy
O-III-1.3	8:40-9:00	Kohyama	Recent Accomplishments and Future Prospects of Materials R & D in Japan
O-III-1.4	9:00-9:20	Larbalestier	New Superconductors for Fusion Magnets
O-III-1.5	9:20-9:40	Konys	Status of Tritium Permeation Barrier Development in the EU
O-III-1.6	9:40-10:00	Pint	Recent Progress Addressing Compatibility Issues Relevant to Fusion Environments

O-III-2.1	8:00-8:20	Brooks	Overview of ALPS Program
O-III-2.2	8:20-8:40	Linke	EU Developments of High Heat-flux Components
O-III-2.3	8:40-9:00	Hassanein	Plasma/Liquid-Metal Interactions during Tokamak Operation
O-III-2.4	9:00-9:20	Snead	IFE First Wall Survival: Development and Testing of a Refractory Armored Ferritic
O-III-2.5	9:20-9:40	Mirnov	The Use of Ga and Li as Limiter Materials in T-3M and T-11M Tokamaks
O-III-2.6	9:40-10:00	Renk	Laser Inertial Fusion Dry-Wall Materials Exposure to X-rays and Ions

O-III-3.1	8:00-8:20	Peng	Emgineering and Physics Assessments of Spherical Torus Component Test Facility
O-III-3.2	8:20-8:40	Abdel-Khalik	An Overview of the Fluid Dynamics Aspects of Liquid Protection Schemes for Fusion Systems
O-III-3.3	8:40-9:00	Sugimoto	Recent Progress of Design & Development of IFMIF Activities
O-III-3.4	9:00-9:20	Morley	Progress on Liquid Metal MHD Free Surface Flow Modeling and Experiments
O-III-3.5	9:20-9:40	Anderson	Protection of IFE First Wall Surfaces from Impulsive Loading by Multiple Liquid Layers
O-III-3.6	9:40-10:00	Rodriguez	Z-Pinch Power Plant Shock Mitigation Experiments and Analysis

PL-III-1	10:30-11:00	Barabaschi	ITER Status
PL-III-2	11:00-11:30	Sauthoff	US ITER Project Activities
PL-III-3	11:30-12:00	Baker	Relation of US VLT Program to ITER
-	12:00-12:10	Kulcinski	Wrap-up