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					                                                            ISFNT-9 Program (Tentative)
                                                                                                        First                                    Abstract
 Session      Topic      PID                                     Title                                                 Affiliation     Country              min
                                                                                                       Autohr                                      ID
Opening Ceremony
                       OC-A1 Chair of International Steering Committee (ISC)                                                                                10
                       OC-A2 General Chair of ISFNT-9                                                                                                       10
   Opening Ceremony    OC-A3 Mayor of Dalian                                                                                                                10
                       OC-A4 President of Dalian University of Technology                                                                                   10
                       OC-A5 Representative of Most                                                                                                         10
Keynote
                                                                                                     Holtkamp /
                   6   KN1-A1 Overview of the Status of the ITER Project                                                  ITER          ITER     06-035     45
                                                                                                     Janeschitz
   KN1
                                Advances in Inertial Confinement Fusion at The National Ignition
               11      KN1-A2                                                                         Ed Moses            LLNL          USA      11-002     45
                                Facility (NIF)

                              Fusion Nuclear Science and Technology Issues and Development and the                                               To be
                   6   KN2-A1                                                                      Mohamed Abdou          UCLA          USA                 45
   KN2                        Role of DT Plasma Based Facilities FNF/CTF                                                                         added
                       KN2-A2 Overview of Chinese Fusion Program                                    X. Peng & Luo     CN ITER DA        China    08-047     35

                                Recent Progress on Fusion Nuclear Technologies in Japan in            Hideyuki
   KN3             6   KN3-A1                                                                                             JAEA          Japan    06-036     45
                                Implementation of the ITER Program and the BA Activities               Takatsu

   KN4             6   KN4-A1 R&D Challenges on the Road Towards Fusion DEMO                          J. Pamela          EFDA            EU      06-041     45


                              Tritium Breeder Blankets Design and Technologies in Europe:
   KN5             2   KN5-A1 Development Status for ITER Test Blanket Modules, Test &              Yves Poitevin          F4E           EU      02-097     45
                              Qualification Strategy and Roadmap Towards DEMO


                                Status and Strategy of Fusion Energy Development Towards DEMO in
   KN6             6   KN6-A1                                                                        Yuanxi Wan      USTC& ASIPP        China    06-038     45
                                China
Plenary

                   2   PL1-A1 TBM Program Implementation in ITER                                   Valery Chuyanov        ITER          ITER     02-098     35
   PL1
                       PL1-A2 ITER Plasma-Facing Components                                         Mario Merola          ITER          ITER     01-068     35
                   1
                       PL1-A3 Status of the JET ITER-like Wall Project                               V. Philipps     Euratom/UKAEA       EU      01-069     35

                                                                                                      Richard
                       PL2-A1 Renew: A Framework for Fusion Research                                                  Univ. of Texas    USA      06-040     35
                                                                                                      Hazeltine
   PL2             6



                                                                                   1
   PL2        6                Code and Standards and Regulation Issues for ITER Design and                  Vladimir
                        PL2-A2                                                                                                    ITER          ITER    06-039   35
                               Construction                                                                  Barabash
                        PL2-A3 LiPb Blankets for TBM and DEMO                                             Satoshi Konishi    Kyoto University   Japan   06-037   35

                               Ferritic Steels in Breeding Blankets: Road map from Qualification and
                        PL3-A1 Validation of Technology for TBM Towards New Developments and              Eberhard Diegele         F4E           EU     04-064   35
                               Improved Knowledge for DEMO
   PL3        4                  Progress in the Development of Reduced Activation Ferritic-Martensitic
                        PL3-A2                                                                              Baldev Raj           IGCAR          India   04-065   35
                                 Steels and Fabrication Technologies in India

                        PL3-A3 The R&D of Reduced Activation Ferritc/Martensitic Steels in Japan          Tanigawa / Shiba       JAEA           Japan   04-067   35


                                                                                                                                                        To be
              2         PL4-A1 Technological R&D Activities and Progress of China TBM Program             Chuanhong Pan           CNS           China            35
                                                                                                                                                        added
   PL4        6         PL4-A2 Overview of Fusion Nuclear Technology Activities at SWIP                      Yong Liu            SWIP           China   06-042   35
                               Progress in Technology and Experiment of Superconducting Tokamaks
              8         PL4-A3                                                                             Baonian Wan           ASIPP          China   08-042   35
                               in ASIPP
Oral
                               The CAD-based 4D Neutronics Simulation and Analysis for
                        IO1-A1                                                                               Y.C. Wu             ASIPP          China   06-043   30
                               Fusion/Fusion-Fission Systems
                               Nuclear Design and Optimisation Analyses of the Helium Cooled
                        SO1-A2                                                                             Ulrich Fischer         FZK            EU     02-042   20
                               Lithium Lead Blanket for a Power Demonstration Reactor
                               Novel Tools for Estimation of Activation Dose in ITER: Comparison,
                        SO1-A3                                                                              Raul Pampin      Euratom/UKAEA       EU     06-010   20
                               Applications and Nuclear Data Development
              6
  OR1A
         (Neutronics)            3-D Assessment of Nuclear Heating, Dose Rate, and Structural Damage        Mahmoud Z
                        SO1-A4                                                                                                   UCLA           USA     06-016   20
                                 in the Generic ITER Diagnostics Upper Port Plugs and Adjacent TF Coils      Youssef

                                 Acceleration Techniques for the Direct Use of CAD-Based Geometry in
                        SO1-A5                                                                            Paul P.H. Wilson        UW            USA     08-030   20
                                 Fusion Neutronics Analysis
                                 Neutronics Optimization of Water-cooled Energy Production Blanket for
                        SO1-A6                                                                             Jieqiong Jiang        ASIPP          China   06-028   20
                                 Fusion-Fission Hybrid Reactor


                                                                                                          Masato Akiba /
                        IO1-B1 Overview of the TBM R&D Activities in Japan                                                       JAEA           Japan   02-101   30
                                                                                                          Mikio Enoeda
                        IO1-B2 Progress of Solid Breeder TBM in SWIP                                      Kaiming Feng           SWIP           China   02-102   30
             2
  OR1B                  IO1-B3 R&D Activities of Helium Cooled Solid Breeder Blankets in Korea            Seungyon Cho           NFRI           Korea   02-096   30
          (TBM-1)
                        SO1-B4 Design and Analysis of DFLL-TBMs for EAST and ITER                           Songlin Liu          ASIPP          China   02-043   20
                                                                                                           Clement P.C.
                        SO1-B5 An Overview of the US DCLL ITER TBM Program                                                         GA           USA     02-028   20
                                                                                                              Wong




                                                                                    2
                     IO2-A1 Mission and Design of a Fusion Development Facility                     Vincent Chan              GA               USA     06-046   30
           6         IO2-A2 Progress of IFERC Project in the Broader Approach Activities           Masanori Araki            JAEA              Japan   06-047   30
OR2A
       (Reactor-1)                                                                                 Jean-Jacques
                     SO2-A3 Configuration Control of the ITER Tokamak Baseline                                         ITER Organization       ITER    06-013   20
                                                                                                      Cordier

                     IO2-B1 Progress on the ITER Divertor R&D in JADA                                 S. Suzuki              JAEA              Japan   01-070   30
           1         IO2-B2 DEMO Divertor Development                                                 R.Nygren               SNL               USA     01-071   30
OR2B
       (Divertor)           Advanced Electrochemical Processing of Tungsten Components for He-
                     SO2-B3                                                                        Wolfgang Krauss            FZK               EU     01-002   20
                            Cooled Divertor Application

                     IO3-A1 Review of Stellarator Design Issues Towards MFE DEMO                     Akio Sagara             NIFS              Japan   06-045   30
                            Fusion Development Path – A Roll-Back Approach Based on                   Farrokh
           6         IO3-A2                                                                                                  UCSD              USA     06-048   30
OR3A                        Conceptual Fusion Power Plant Studies                                    Najmabadi
       (Reacor-2)
                              Findings of the US Research Needs Workshop on the Topic of Fusion
                     SO3-A3                                                                         Wayne Meier              LLNL              USA     06-022   20
                              Power

                            MHD Thermofluid Issues of Liquid Metal Blankets: Phenomena and
                     IO3-B1                                                                         S. Smolenstev            UCLA              USA     02-100   30
                            Advances
          2                 Direct Simulations of 3D MHD Flows in a Sudden Expansion Using a                         Graduate University of
OR3B                 IO3-B2                                                                          Ming-Jiu Ni                               China   08-044   30
       (MHD-1)              Consistent and Conservative Scheme                                                               CAS
                            Simulations of MHD thermocapillary and thermoelectric convection in
                     SO3-B3                                                                         Neil B. Morley           UCLA              USA     01-053   20
                            molten metal layers

                            Status of R&D on Fusion Materials in Institute of Nuclear Materials,
                     IO4-A1                                                                        Chang-Chun Ge             USTB              China   04-063   30
                            USTB
            4        IO4-A2 Fabrication of Small TBMs for EAST and ITER                            Qunying Huang             ASIPP             China   04-066   30
       (Structual           Assessment of Defects in EUROFER 97 First Wall/Blanket Structures
                     SO4-A3                                                                          Jarir Aktaa           FZK, IMR             EU     04-036   20
        Material)           Taking into Account Its Viscoplastic Behavior
OR4A
                     SO4-A4 Impact of Materials Innovation on Advanced Blanket Design              Akihiko Kimura       Kyoto University       Japan   02-009   20

                                                                                                      Magali
           9         SO4-A5 ITER Hot Cell Facility Current Status and Main Issues                                      ITER Organization       ITER    09-003   20
                                                                                                    Benchikhoune


                     IO4-B1 Must We Use Ferritic Steel in TBM?                                        JF Salavy               CEA               EU     02-099   30
                            Preparation of Interfaces in ITER for Integrating the Test Blanket
                     SO4-B2                                                                          L. Giancarli      ITER Organization       ITER    02-030   20
                            Systems
                            The Ancillary Systems of the European Test Blanket Modules:
                     SO4-B3                                                                         Italo Ricapito            F4E               EU     02-029   20
           2                Configuration and Integration in ITER
OR4B
        (TBM-2)             Three-Dimensional Nuclear Analysis for the US Dual Coolant Lithium      Mohamed E.
                     SO4-B4                                                                                          University of Wisconsin   USA     02-022   20
                            Lead ITER Test Blanket Module                                             Sawan




                                                                                3
           2
OR4B
        (TBM-2)

                                                                                                           Paritosh       Institute for Plasma
                     SO4-B5 Current Status of Engineering Design and Analysis of Indian LLCB TBM                                                  India    02-027   20
                                                                                                          Chaudhuri             Research
                     SO4-B6 Design, Analysis and Technology Blanket’s Shield Blocks of ITER                D. Mitin              RDIPE           Russian   02-047   20

                     IO4-C1 Mockup Testing Facilities and Qualification Tests for EU ITER TBM             A. Aiello              ENEA              EU      08-046   30
                            Neutronics Experiments on TBM - HCPB and HCLL Mock-ups in
                     IO4-C2                                                                            Paola Batistoni          ENEA               EU      08-045   30
                            Preparation of Nuclear Measurements in ITER TBMs
            8
                     IO4-C3 Status and Prospect of the JT-60SA Project                                 Shinichi Ishida           JAEA            Japan     08-001   30
OR4C
                            Recent Developments in Fusion Vacuum Flow Modelling for ITER and
                     IO4-C4                                                                             Christian Day            FZK               EU      08-043   30
                            Beyond
                            Impact of Various Plasma Instabilities on Reliability and Performance of
            1        SO4-C5                                                                             A. Hassanein       Purdue University      USA      01-019   20
                            Tokamak Fusion Devices

                            The Recent Efforts on Industrialization of SiC/SiC for Fusion                                 Muroran Institute of
                     IO5-A1                                                                              A. Kohyama                              Japan     04-047   30
                            Application                                                                                      Technology
            4
                            Progress in the Development of Insulator Coating for Liquid Lithium
OR5A   (Functional   IO5-A2                                                                             Takeo Muroga             NIFS            Japan     04-068   30
                            Blankets
        Material)
                            Development of Advanced Processes for Al-based Anti-corrosion and T
                     SO5-A3                                                                             Juergen Konys            FZK               EU      02-001   20
                            Permeation Barriers


           12        IO5-B1 Design of the LIFE Engine                                                   J.F. Latkowski           LLNL             USA      12-014   30

                              Fusion Reactor Design Study with a Self-consistent System Analysis
OR5B                 IO5-B2                                                                            Bong Guen Hong           KAERI            Korea     06-009   30
                              Code
            6
                              Fifty Years of Magnetic Fusion Research (1958-2008): Brief Historical                         University of
                     SO5-B3                                                                            Laila El-Guebaly                           USA      06-006   20
                              Overview and Future Trends                                                                  Wisconsin-Madison

                              Operating Experiences from Existing Fusion Facilities in View of ITER
                     IO6-A1                                                                              Tonio Pinna            ENEA               EU      07-028   30
                              Safety and Reliability
                              Experimental and Numerical Investigations on Hydrogen and Dust
                     SO6-A2                                                                              A.Denkevits             FZK               EU      07-029   30
                              Explosion Risk in ITER
OR6A        7
                     SO6-A3 Steam Oxidation Measurements of Beryllium Dust and Pebbles                   J.P. Sharpe              INL             USA      04-014   20

                                                                                                       José R. García- Technical University of
                     SO6-A4 Development of a IRSN Code for Dust Mobilization Problems in ITER                                                      EU      07-022   20
                                                                                                          Cascales           Cartagena

                     IO6-B1 Material Testing and MHD Research in DRAGON LiPb Loops                      Zhiqiang Zhu             ASIPP           China     02-103   30
                              Direct Numerical Simulation of Unstable Stratified Turbulent Flow                           Tokyo University of
           2         SO6-B2                                                                            Shin-ichi Satake                          Japan     08-003   20
OR6B                          Under a Magnetic Field                                                                           Science
        (MHD-2)




                                                                                 4
                2
  OR6B
             (MHD-2)
                                Primary Experimental Results of an MHD Flow in the Duct with Flow
                       SO6-B3                                                                                  Zengyu Xu            SWIP            China     02-011   20
                                Channel Insert (FCI)


                       IO6-C1 IFMIF, a Major Facility for the Fusion Programme – Status of EVEDA                P. Garin            JAEA            Japan     04-054   30

                                                                                                               Takehiko
                       IO6-C2 High-Flux Test Module Design for IFMIF-EVEDA                                                     Kyushu University    Japan     04-069   30
                                                                                                               Yokomine
  OR6C             4
                                Boundary Condition Definitions and Conceptual Design of IFMIF Target
                       SO6-C3                                                                                   Kuo Tian             FZK             EU       04-021   20
                                and Test Cell
                                Irradiation Facilities Available in Institute of Reactor Materials Used in      Leonid
                       SO6-C4                                                                                                        IRM            Russia    04-039   20
                                Support of Fusion Reactors Development                                         Sinelnikov

                              Progress on an Integrated Multi-physics Simulation Predictive Capability
                       IO7-A1                                                                                  Alice Ying           UCLA             USA      01-072   30
                              for Plasma Chamber Nuclear Components
  OR7A             1
                              Initial Results from the Lithium Tokamak eXperiment (LTX) and the
                       IO7-A2                                                                                  R. Majeski           PPPL             USA      01-073   30
                              Impact of Lithium Wall Coatings on NSTX Discharges


                   8   IO7-B1 Status of Korea ITER Procurement Activities                                     Ki Jung Jung          NFRI            Korea     08-048   30

  OR7B                 IO7-B2 ITER Vacuum Vessel Design and Construction                                      Kimihiro Ioki   ITER Organization     ITER      05-010   30
                   5                                                                                           Vladimir
                       SO7-B3 Impact Interaction Between Blanket and Vacuum Vessel of ITER                                         NIKIET           Russian   05-009   20
                                                                                                               Kolganov


                                Design and R&D Activities in EU in Support of ITER Water Detritiation
                       IO8-A1                                                                                 Ion Cristescu          FZK             EU       03-020   30
                                and Cryogenic Distillation Systems as in Kind Contribution
  OR8A             3
                       SO8-A2 On the Fuel Balance of a DT Reactor                                            Tetsuo Tanabe     Kyushu University    Japan     03-046   20
                              Experimental Design of Tritium Extraction Loop from Lead Lithium
                       SO8-A3                                                                                Sadhana Mohan       HWD/ BARC           India    03-006   20
                              Eutectic

                       IO8-B1 Construction of the Plasma-Wall Experiment Magnum-PSI                             J. Rapp        FOM, Nieuwegein       EU       01-035   20
                              Performances of Helium, Neon and Argon Glow Discharges for
  OR8B             1   SO8-B2                                                                                Tomoaki Hino     Hokkaido University   Japan     01-003   20
                              Reduction of Fuel Hydrogen Retention
                       SO8-B3 Plasma Facing Components of EAST Tokamak                                         Y.T. Song            ASIPP           China     01-007   20
Closing Ceremony
                       CC-A1 Chair of International Steering Committee (ISC)                                                                                           10
                       CC-A2 Presentation of Miya-Abdou Award for FNT                                                                                                  10
    Closing Ceremony
                       CC-A3 General Chair of ISFNT-9                                                                                                                  10
                       CC-A4 Mayor of Dalian                                                                                                                           10




                                                                                       5
Topics:
     1    First Wall Technology and High Heat Flux Components
     2    Blanket Technology
     3    Fuel Cycle and Tritium Processing
     4    Material Engineering for FNT
     5    Vacuum Vessel
     6    Nuclear System Design and Reactor Studies
     7    Safety Issues and Waste Management
     8    Models and Experiments for FNT
     9    Remote Handling and Maintenance
    10    Burning Plasma Control and Operation
    11    Inertial Confinement Fusion Studies and Technologies
    12    FNT Contributions to other Fields of Science and Technology




                                                                        6
                                                                   Monday Schedule (Tentative)
                                                                                                               First                                      Abstract
 Time    Session       Topic        PID                                 Title                                                     Affiliation   Country              min
                                                                                                              Autohr                                        ID
Room A
  8:30                            OC-A1    Chair of International Steering Committee (ISC)                                                                           10
  8:40                            OC-A2    General Chair of ISFNT-9                                                                                                  10
  8:50   Opening Ceremony         OC-A3    Mayor of Dalian                                                                                                           10
  9:00                            OC-A4    President of Dalian University of Technology                                                                              10
  9:10                            OC-A5    Representative of Most                                                                                                    10
  9:20 Break                                                                                                                                                         10

  9:30                   6        KN1-A1 Overview of the Status of the ITER Project                     Holtkamp / Janeschitz       ITER         ITER     06-035     45
           KN1
                                           Advances in Inertial Confinement Fusion at The National
 10:15                  11        KN1-A2                                                                     Ed Moses               LLNL         USA      11-002     45
                                           Ignition Facility (NIF)
 11:00   Break                                                                                                                                                       20
                                         Fusion Nuclear Science and Technology Issues and
                                                                                                                                                           To be
 11:20                   6        KN2-A1 Development and the Role of DT Plasma Based Facilities           Mohamed Abdou             UCLA         USA                 45
           KN2                                                                                                                                             added
                                         FNF/CTF
 12:05                   8        KN2-A2 Overview of Chinese Fusion Program                                X. Peng & Luo         CN ITER DA      China    08-047     35
 12:40   Lunch Time                                                                                                                                                  80
                                         The CAD-based 4D Neutronics Simulation and Analysis for
 14:00                            IO1-A1                                                                      Y.C. Wu               ASIPP        China     06-043    30
                                         Fusion/Fusion-Fission Systems
                                         Nuclear Design and Optimisation Analyses of the Helium
 14:30                            SO1-A2 Cooled Lithium Lead Blanket for a Power Demonstration             Ulrich Fischer            FZK          EU      02-042     20
                                         Reactor
                                           Novel Tools for Estimation of Activation Dose in ITER:
 14:50                            SO1-A3                                                                    Raul Pampin         Euratom/UKAEA     EU       06-010    20
                        6                  Comparison, Applications and Nuclear Data Development
          OR1A
                   (Neutronics)          3-D Assessment of Nuclear Heating, Dose Rate, and Structural
 15:10                            SO1-A4 Damage in the Generic ITER Diagnostics Upper Port Plugs and    Mahmoud Z Youssef           UCLA         USA      06-016     20
                                         Adjacent TF Coils
                                           Acceleration Techniques for the Direct Use of CAD-Based
 15:30                            SO1-A5                                                                  Paul P.H. Wilson           UW          USA      08-030     20
                                           Geometry in Fusion Neutronics Analysis
                                           Neutronics Optimization of Water-cooled Energy Production
 15:50                            SO1-A6                                                                   Jieqiong Jiang           ASIPP        China     06-028    20
                                           Blanket for Fusion-Fission Hybrid Reactor
 16:10 Break                                                                                                                                                         20
Room B
                                                                                                           Masato Akiba /
 14:00                            IO1-B1 Overview of the TBM R&D Activities in Japan                                                JAEA         Japan    02-101     30
                                                                                                           Mikio Enoeda


                         2
          OR1B
                      (TBM-1)
                                                                                             7
 14:30                          IO1-B2 Progress of Solid Breeder TBM in SWIP                           Kaiming Feng      SWIP    China   02-102   30
                         2               R&D Activities of Helium Cooled Solid Breeder Blankets in
 15:00    OR1B                  IO1-B3                                                                 Seungyon Cho      NFRI    Korea   02-096   30
                      (TBM-1)            Korea
 15:30                          SO1-B4 Design and Analysis of DFLL-TBMs for EAST and ITER               Songlin Liu      ASIPP   China   02-043   20
 15:50                          SO1-B5 An Overview of the US DCLL ITER TBM Program                   Clement P.C. Wong    GA     USA     02-028   20
  16:10 Break                                                                                                                                     20
Poster Room
 16:30   Poster Session 1                                                                                                                         120
 18:30   Break




                                                                                      8
                                                                Tuesday Schedule (Tentative)
                                                                                                             First                                       Abstract
 Time     Session      Topic        PID                               Title                                                   Affiliation      Country              min
                                                                                                            Autohr                                         ID
Room A

                                           Recent Progress on Fusion Nuclear Technologies in Japan in
  8:30     KN3           6        KN3-A1                                                                Hideyuki Takatsu        JAEA            Japan    06-036     45
                                           Implementation of the ITER Program and the BA Activities

  9:15                   2        PL1-A1 TBM Program Implementation in ITER                             Valery Chuyanov          ITER           ITER     02-098     35
  9:50     PL1                    PL1-A2 ITER Plasma-Facing Components                                   Mario Merola            ITER           ITER     01-068     35
                         1
 10:25                            PL1-A3 Status of the JET ITER-like Wall Project                         V. Philipps      Euratom/UKAEA         EU      01-069     35
 11:00   Break                                                                                                                                                      20
 11:20                            IO2-A1 Mission and Design of a Fusion Development Facility             Vincent Chan            GA             USA      06-046     30

                        6                  Progress of IFERC Project in the Broader Approach
 11:50                            IO2-A2                                                                Masanori Araki          JAEA            Japan    06-047     30
          OR2A                             Activities
                    (Reactor-1)
                                                                                                         Jean-Jacques
 12:20                            SO2-A3 Configuration Control of the ITER Tokamak Baseline                                ITER Organization    ITER      06-013    20
                                                                                                            Cordier
 12:40 Lunch Time                                                                                                                                                   80
Room B
 11:20                            IO2-B1 Progress on the ITER Divertor R&D in JADA                         S. Suzuki             JAEA           Japan    01-070     30
 11:50                1           IO2-B2 DEMO Divertor Development                                         R.Nygren              SNL            USA      01-071     30
        OR2B
                  (Divertor)               Advanced Electrochemical Processing of Tungsten
 12:20                            SO2-B3                                                                Wolfgang Krauss          FZK             EU       01-002    20
                                           Components for He-Cooled Divertor Application
 12:40   Lunch Time                                                                                                                                                 80

 14:00   Social Program (Excursion to Dalian Coast for ISFNT9 participants and spouses)                                                                             240
 18:00   Break                                                                                                                                                      60
 19:00   Welcome in Dalian (To be decided)




                                                                                      9
                                                             Wednesday Schedule (Tentative)
                                                                                                               First                                            Abstract
 Time    Session        Topic       PID                                   Title                                                   Affiliation         Country              min
                                                                                                              Autohr                                              ID
Room A


 8:30      KN4            6        KN4-A1 R&D Challenges on the Road Towards Fusion DEMO                     J. Pamela              EFDA                EU      06-041     45


                                                                                                             Richard
 9:15                              PL2-A1 Renew: A Framework for Fusion Research                                                Univ. of Texas         USA      06-040     35
                                                                                                             Hazeltine

           PL2            6                 Code and Standards and Regulation Issues for ITER Design and     Vladimir
 9:50                              PL2-A2                                                                                            ITER              ITER     06-039     35
                                            Construction                                                     Barabash

 10:25                             PL2-A3 LiPb Blankets for TBM and DEMO                                   Satoshi Konishi      Kyoto University       Japan    06-037     35
 11:00   Break                                                                                                                                                             20
 11:20                             IO3-A1 Review of Stellarator Design Issues Towards MFE DEMO              Akio Sagara              NIFS              Japan     06-045    30

                          6               Fusion Development Path – A Roll-Back Approach Based on             Farrokh
 11:50                             IO3-A2                                                                                            UCSD              USA      06-048     30
          OR3A                            Conceptual Fusion Power Plant Studies                              Najmabadi
                      (Reacor-2)
                                            Findings of the US Research Needs Workshop on the Topic of
 12:20                             SO3-A3                                                                   Wayne Meier              LLNL              USA       06-022    20
                                            Fusion Power
 12:40   Lunch Time                                                                                                                                                        80
                                          Status of R&D on Fusion Materials in Institute of Nuclear
 14:00                             IO4-A1                                                                  Chang-Chun Ge            USTB               China    04-063     30
                                          Materials, USTB

 14:30                     4       IO4-A2 Fabrication of Small TBMs for EAST and ITER                      Qunying Huang            ASIPP              China    04-066     30
                      (Structual
                       Material)            Assessment of Defects in EUROFER 97 First Wall/Blanket
 15:00    OR4A                     SO4-A3                                                                    Jarir Aktaa          FZK, IMR              EU      04-036     20
                                            Structures Taking into Account Its Viscoplastic Behavior

 15:20                             SO4-A4 Impact of Materials Innovation on Advanced Blanket Design        Akihiko Kimura      Kyoto University        Japan    02-009     20

                                                                                                             Magali
 15:40                    9        SO4-A5 ITER Hot Cell Facility Current Status and Main Issues                               ITER Organization        ITER     09-003     20
                                                                                                           Benchikhoune
 16:00 Break                                                                                                                                                               20
Room B
                                            MHD Thermofluid Issues of Liquid Metal Blankets: Phenomena
 11:20                             IO3-B1                                                                  S. Smolenstev             UCLA              USA      02-100     30
                                            and Advances
                         2                  Direct Simulations of 3D MHD Flows in a Sudden Expansion                         Graduate University of
 11:50    OR3B                     IO3-B2                                                                   Ming-Jiu Ni                                China    08-044     30
                      (MHD-1)               Using a Consistent and Conservative Scheme                                               CAS
                                            Simulations of MHD thermocapillary and thermoelectric
 12:20                             SO3-B3                                                                  Neil B. Morley           UCLA               USA       01-053    20
                                            convection in molten metal layers




                                                                                      10
 12:40   Lunch Time                                                                                                                                                            80
 14:00                              IO4-B1 Must We Use Ferritic Steel in TBM?                                     JF Salavy                CEA                EU      02-099   30
                                           Preparation of Interfaces in ITER for Integrating the Test Blanket
 14:30                              SO4-B2                                                                       L. Giancarli       ITER Organization        ITER     02-030   20
                                           Systems
                                             The Ancillary Systems of the European Test Blanket Modules:
 14:50                              SO4-B3                                                                      Italo Ricapito             F4E                EU      02-029   20
                         2                   Configuration and Integration in ITER
          OR4B                               Three-Dimensional Nuclear Analysis for the US Dual Coolant         Mohamed E.
 15:10                (TBM-2)       SO4-B4                                                                                        University of Wisconsin    USA      02-022   20
                                             Lithium Lead ITER Test Blanket Module                                Sawan
                                             Current Status of Engineering Design and Analysis of Indian           Paritosh        Institute for Plasma
 15:30                              SO4-B5                                                                                                                   India    02-027   20
                                             LLCB TBM                                                             Chaudhuri              Research

 15:50                              SO4-B6 Design, Analysis and Technology Blanket’s Shield Blocks of ITER         D. Mitin               RDIPE             Russian   02-047   20
 16:10 Break                                                                                                                                                                   20
Room C
                                             Mockup Testing Facilities and Qualification Tests for EU ITER
 14:00                              IO4-C1                                                                        A. Aiello               ENEA                EU      08-046   30
                                             TBM
                                             Neutronics Experiments on TBM - HCPB and HCLL Mock-ups in
 14:30                              IO4-C2                                                                      Paola Batistoni           ENEA                EU      08-045   30
                                             Preparation of Nuclear Measurements in ITER TBMs
                           8
 15:00    OR4C                      IO4-C3 Status and Prospect of the JT-60SA Project                           Shinichi Ishida           JAEA              Japan     08-001   30

                                             Recent Developments in Fusion Vacuum Flow Modelling for ITER
 15:30                              IO4-C4                                                                      Christian Day              FZK                EU      08-043   30
                                             and Beyond
                                             Impact of Various Plasma Instabilities on Reliability and
 16:00                     1        SO4-C5                                                                      A. Hassanein        Purdue University        USA      01-019   20
                                             Performance of Tokamak Fusion Devices
  16:20 Break                                                                                                                                                                  10
Poster Room
  16:30 Poster Session 2                                                                                                                                                       120
  18:30            Break                                                                                                                                                       30
 19:00   Dinner Meeting (ISC members only)




                                                                                         11
                                                                Thursday Schedule (Tentative)
                                                                                                                  First                                          Abstract
 Time    Session        Topic         PID                                  Title                                                     Affiliation       Country              min
                                                                                                                 Autohr                                            ID
Room A

                                           Tritium Breeder Blankets Design and Technologies in Europe:
 8:30      KN5             2        KN5-A1 Development Status for ITER Test Blanket Modules, Test &           Yves Poitevin             F4E              EU      02-097     45
                                           Qualification Strategy and Roadmap Towards DEMO


                                           Ferritic Steels in Breeding Blankets: Road map from
 9:15                               PL3-A1 Qualification and Validation of Technology for TBM Towards        Eberhard Diegele           F4E              EU      04-064     35
                                           New Developments and Improved Knowledge for DEMO

           PL3             4
                                             Progress in the Development of Reduced Activation Ferritic-
 9:50                               PL3-A2                                                                     Baldev Raj             IGCAR             India    04-065     35
                                             Martensitic Steels and Fabrication Technologies in India

                                             The R&D of Reduced Activation Ferritc/Martensitic Steels in
 10:25                              PL3-A3                                                                   Tanigawa / Shiba          JAEA             Japan    04-067     35
                                             Japan
 11:00   Break                                                                                                                                                              20
                                             The Recent Efforts on Industrialization of SiC/SiC for Fusion                      Muroran Institute of
 11:20                              IO5-A1                                                                     A. Kohyama                               Japan    04-047     30
                                             Application                                                                           Technology
                           4
          OR5A        (Functional            Progress in the Development of Insulator Coating for Liquid
 11:50                              IO5-A2                                                                    Takeo Muroga             NIFS             Japan    04-068     30
                       Material)             Lithium Blankets
                                             Development of Advanced Processes for Al-based Anti-
 12:20                              SO5-A3                                                                    Juergen Konys             FZK              EU      02-001     20
                                             corrosion and T Permeation Barriers
 12:40   Lunch Time                                                                                                                                                         80

                                             Operating Experiences from Existing Fusion Facilities in View
 14:00                              IO6-A1                                                                     Tonio Pinna             ENEA              EU      07-028     30
                                             of ITER Safety and Reliability

                                             Experimental and Numerical Investigations on Hydrogen and
 14:30                              SO6-A2                                                                     A.Denkevits              FZK              EU      07-029     30
                                             Dust Explosion Risk in ITER
          OR6A             7
 15:00                              SO6-A3 Steam Oxidation Measurements of Beryllium Dust and Pebbles          J.P. Sharpe              INL             USA      04-014     20

                                             Development of a IRSN Code for Dust Mobilization Problems       José R. García-    Technical University
 15:20                              SO6-A4                                                                                                               EU      07-022     20
                                             in ITER                                                            Cascales           of Cartagena
 15:40 Break                                                                                                                                                                20
Room B




                                                                                        12
 11:20                   12        IO5-B1 Design of the LIFE Engine                                                 J.F. Latkowski          LLNL            USA      12-014   30

                                             Fusion Reactor Design Study with a Self-consistent System
 11:50    OR5B                     IO5-B2                                                                          Bong Guen Hong           KAERI           Korea    06-009   30
                                             Analysis Code
                         6
                                             Fifty Years of Magnetic Fusion Research (1958-2008): Brief                                 University of
 12:20                            SO5-B3                                                                           Laila El-Guebaly                         USA      06-006   20
                                             Historical Overview and Future Trends                                                    Wisconsin-Madison
 12:40   Lunch Time                                                                                                                                                           80

 14:00                             IO6-B1 Material Testing and MHD Research in DRAGON LiPb Loops                    Zhiqiang Zhu            ASIPP           China    02-103   30

                         2                   Direct Numerical Simulation of Unstable Stratified Turbulent                             Tokyo University of
 14:30    OR6B                    SO6-B2                                                                           Shin-ichi Satake                         Japan    08-003   20
                      (MHD-2)                Flow Under a Magnetic Field                                                                   Science

                                             Primary Experimental Results of an MHD Flow in the Duct with
 14:50                            SO6-B3                                                                             Zengyu Xu               SWIP           China    02-011   20
                                             Flow Channel Insert (FCI)
 15:10 Break                                                                                                                                                                  50
Room C
                                             IFMIF, a Major Facility for the Fusion Programme – Status of
 14:00                             IO6-C1                                                                              P. Garin             JAEA            Japan    04-054   30
                                             EVEDA

 14:30                             IO6-C2 High-Flux Test Module Design for IFMIF-EVEDA                            Takehiko Yokomine    Kyushu University    Japan    04-069   30
          OR6C           4
                                             Boundary Condition Definitions and Conceptual Design of
 15:00                            SO6-C3                                                                              Kuo Tian               FZK             EU      04-021   20
                                             IFMIF Target and Test Cell

                                             Irradiation Facilities Available in Institute of Reactor Materials
 15:20                            SO6-C4                                                                          Leonid Sinelnikov          IRM            Russia   04-039   20
                                             Used in Support of Fusion Reactors Development
  15:40 Break                                                                                                                                                                 20
Poster Room
  16:00 Poster Session 3                                                                                                                                                      120
  18:00 Break                                                                                                                                                                 60
  19:00 Conference Banquet (To be decided)




                                                                                           13
                                                                  Friday Schedule (Tentative)
                                                                                                                      First                                      Abstract
 Time    Session      Topic    PID                                       Title                                                        Affiliation      Country              min
                                                                                                                     Autohr                                        ID
Room A
                                       Status and Strategy of Fusion Energy Development Towards DEMO in
 8:30      KN6         6      KN6-A1                                                                               Yuanxi Wan       USTC& ASIPP         China    06-038     45
                                       China
                                                                                                                                                                  To be
 9:15                  2      PL4-A1 Technological R&D Activities and Progress of China TBM Program               Chuanhong Pan          CNS            China               35
                                                                                                                                                                  added

 9:50      PL4         6      PL4-A2 Overview of Fusion Nuclear Technology Activities at SWIP                       Yong Liu            SWIP            China    06-042     35

                                       Progress in Technology and Experiment of Superconducting Tokamaks
 10:25                 8      PL4-A3                                                                               Baonian Wan          ASIPP           China    08-042     35
                                       in ASIPP
 11:00   Break                                                                                                                                                              20
                                       Progress on an Integrated Multi-physics Simulation Predictive Capability
 11:20                        IO7-A1                                                                                Alice Ying          UCLA            USA      01-072     30
                                       for Plasma Chamber Nuclear Components
          OR7A         1
                                       Initial Results from the Lithium Tokamak eXperiment (LTX) and the
 11:50                        IO7-A2                                                                                R. Majeski          PPPL            USA       01-073    30
                                       Impact of Lithium Wall Coatings on NSTX Discharges
 12:20   Lunch Time                                                                                                                                                         100

                                       Design and R&D Activities in EU in Support of ITER Water Detritiation
 14:00                        IO8-A1                                                                               Ion Cristescu         FZK             EU      03-020     30
                                       and Cryogenic Distillation Systems as in Kind Contribution

          OR8A         3
 14:30                        SO8-A2 On the Fuel Balance of a DT Reactor                                          Tetsuo Tanabe    Kyushu University    Japan    03-046     20

                                       Experimental Design of Tritium Extraction Loop from Lead Lithium
 14:50                        SO8-A3                                                                              Sadhana Mohan      HWD/ BARC          India    03-006     20
                                       Eutectic
 15:10   Break                                                                                                                                                              10
 15:20                        CC-A1 Chair of International Steering Committee (ISC)                                                                                         10
 15:30                        CC-A2 Presentation of Miya-Abdou Award for FNT                                                                                                10
           Closing Ceremony
 15:40                        CC-A3 General Chair of ISFNT-9                                                                                                                10
 15:50                        CC-A4 Mayor of Dalian                                                                                                                         10
Room B
 11:20                 8      IO7-B1 Status of Korea ITER Procurement Activities                                   Ki Jung Jung         NFRI            Korea    08-048     30

 11:50    OR7B                IO7-B2 ITER Vacuum Vessel Design and Construction                                   Kimihiro Ioki    ITER Organization    ITER     05-010     30
                       5
                                                                                                                    Vladimir
 12:20                        SO7-B3 Impact Interaction Between Blanket and Vacuum Vessel of ITER                                      NIKIET          Russian    05-009    20
                                                                                                                    Kolganov




                                                                                       14
12:40   Lunch Time                                                                                                                                   80
14:00                    IO8-B1 Construction of the Plasma-Wall Experiment Magnum-PSI            J. Rapp       FOM, Nieuwegein       EU     01-035   20

         OR8B        1            Performances of Helium, Neon and Argon Glow Discharges for
14:20                    SO8-B2                                                                Tomoaki Hino   Hokkaido University   Japan   01-003   20
                                  Reduction of Fuel Hydrogen Retention
14:40                    SO8-B3 Plasma Facing Components of EAST Tokamak                        Y.T. Song           ASIPP           China   01-007   20
15:00   Break                                                                                                                                        20




                                                                               15
                                                    ISFNT-9 Satellite Meetings Program (Tentative)
List                                 Topic                                Organizer          Affiliation        Room          Meeting Time          Remarks
                                                                                                                              Wednesday afternoon
 1     International Workshop on Sub-Task Fusion Neutronics               Paola Batistoni     EU, ENEA        To be decided     (16:30~18:30)       25 persons
                                                                                                                                Oct. 14, 2009

       ExCo Meeting:
                                                                          Rainer Laesser                                      Thursday afternoon
          Executive Committee (ExCo) of the Implementing Agreement (IA)
 2                                                                        (Plant Systems    ITER Department   To be decided     (16:00~18:00)       30 experts
       on Nuclear Technology for Fusion Reactors (NTFR)
                                                                          Division Head)                                        Oct. 15, 2009




                                                                                   16

				
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