ISFNT 15 All Rights Reserved.
POSTER SESSIONS
Level -3
9. San Borondón
- MONDAY 11TH
- TUESDAY 12TH
- THURSDAY 14TH
- FRIDAY 15TH
MONDAY 11TH
PS1 - TOPIC A. Plasma-Facing High Heat Flux Components
| ORDER OF POSTER | ABSTRACT ID | TITLE | PRESENTER |
|---|---|---|---|
| PS1-1 | ABSTRACT-781e | The thermohydraulic parameters of copper foam based cooling channel. | Vojtěch Smolík |
| PS1-2 | ABSTRACT-122f | Experimental Study of Boiling Heat Transfer Characteristics of Multi-Elbow Cooling System under One-sided Heating with Long Area for Fusion Divertor Cooling | Shuta Nakano |
| PS1-3 | ABSTRACT-1e2d | Numerical simulation of the erosion process in W lattice armor for sacrificial limiters under high heat flux | Pietro Vinoni |
| PS1-4 | ABSTRACT-22b5 | Design and fabrication of preliminary mock-ups for the Outboard First Wall of the DTT facility | Gabriele De Sano |
| PS1-5 | ABSTRACT-2b06 | Multi-physics lumped modeling of micro-channels cooling structure for W7X divertor unit target module | Francesco Carrone |
| PS1-6 | ABSTRACT-d38c | Capillary porous structure based divertor transient heat event mitigation capabilities modelling | Jan Cecrdle |
| PS1-7 | ABSTRACT-df22 | Experimental evaluation of capillary effects relevant to the design of semi-static liquid lithium plasma-facing components | Martin Nieto-Perez |
| PS1-8 | ABSTRACT-7545 | Conceptual design of a 3D printed liquid lithium divertor target for DEMO | Xinyuan Qian |
| PS1-9 | ABSTRACT-6a2c | Comparative study of ITER conform tungsten grades exposed to high heat flux and neutron irradiation damage | Dmitry Terentyev |
| PS1-10 | ABSTRACT-0795 | Molecular dynamics study on the slip properties of liquid lithium flow on iron surfaces | Huai Yuan Qu |
| PS1-12 | ABSTRACT-08ee | Completion of the first lower divertor cassette of JT-60SA | Takao Hayashi |
| PS1-14 | ABSTRACT-0c22 | Full-field kinematic and thermal characterisation of a DEMO divertor mono-block under high heat flux loading | Adel Tayeb |
| PS1-16 | ABSTRACT-14d5 | Structural Analysis of the DEMO Upper Limiter preliminary design | Fabio Viganò |
| PS1-17 | ABSTRACT-1808 | A Study on Stress Mitigation of Process Pipes in TBM-set | Seong Dae Park |
| PS1-18 | ABSTRACT-1a5e | A multiscale tool for Plasma Facing Materials aging simulations | Giorgio Lo Presti |
| PS1-20 | ABSTRACT-f5dd | Development of the Liquid Metal Shield Plasma-Surface-Interaction (LiMeS-PSI) linear plasma device. | Victor Tanke |
| PS1-21 | ABSTRACT-f739 | Overview of the DTT Assembly Plan | Marco Utili |
| PS1-22 | ABSTRACT-1f1c | Application of Tungsten Recrystallisation in Plasma Facing Components Design | Songke Wang |
PS1 - TOPIC B. Blanket Technology
| ORDER OF POSTER | ABSTRACT ID | TITLE | PRESENTER |
|---|---|---|---|
| PS1-23 | ABSTRACT-0ff3 | Development of repair technology for functional ceramic coating by recoating | Tetsuma Ito |
| PS1-24 | ABSTRACT-9b26 | Kinetics of helium bubble formation in liquid lead-lithium eutectic: an atomistic-simulation study | Abdulrahman Al Awad |
| PS1-25 | ABSTRACT-4916 | RELAP5/Mod3.3 MHD module Development and Validation: WCLL-TBM mock-up model | Lorenzo Melchiorri |
| PS1-26 | ABSTRACT-da35 | Silicon Carbide Neutron Detectors for Tritium Production Assessment in Breeding Blankets | Matteo Hakeem Kushoro |
| PS1-27 | ABSTRACT-7245 | Design of the mock-up of breeding blanket aiming for tritium measurement | Tianyi Liu |
| PS1-28 | ABSTRACT-7981 | Deuterium permeation and lithium-lead corrosion behaviors of ceramic-iron joint coating | Hnin Lai Lai Wai |
| PS1-29 | ABSTRACT-7dd9 | 3D MHD analysis on the COOL blanket for BEST | Xuan Zheng |
| PS1-30 | ABSTRACT-833a | Research on improving the system sensitivity for Hot Helium Leak Test | Zhen Leng |
| PS1-31 | ABSTRACT-88ad | System code simulation of DEMO WCLL Central Outboard Blanket equatorial cell operational transients | Marcello Principato |
| PS1-32 | ABSTRACT-000e | Dedicated Thermal, Thermal-hydraulic and Thermal-mechanical Analyses in support of DEMO WCLL BB design | Brahim Chelihi |
| PS1-33 | ABSTRACT-c630 | Numerical simulation of buoyant flow in a vertical channel for plasma facing component | Shin-Ichi Satake |
| PS1-34 | ABSTRACT-92f5 | Modelling transport of dust particles in the Helium-Cooled Pebble Bed breeding blanket concept | Dario Passafiume |
| PS1-35 | ABSTRACT-0b31 | Experimental investigation of MHD flows in a WCLL TBM mock-up | Cyril Courtessole |
| PS1-36 | ABSTRACT-1690 | Progress on the Neutronics Design and Analysis for CN HCCB TBS in PD phase | Qixiang Cao |
| PS1-37 | ABSTRACT-1a82 | Key Technologies of Manufacturing and Testing for The ITER Blanket Shield Block | Sa-Woong Kim |
| PS1-38 | ABSTRACT-21b4 | Instrumentation integration in the European Test Blanket Modules | Luis Maqueda |
| PS1-39 | ABSTRACT-2834 | Multiphysics Modeling and Creep Analysis of the DCLL Blanket of the Fusion Nuclear Science Facility | Sunday Aduloju |
| PS1-41 | ABSTRACT-2fb5 | Experimental measurement of hydrogen and deuterium solubility in LiPb using absorption and desorption techniques | Ciro Alberghi |
| PS1-42 | ABSTRACT-37c0 | Experimental determination of the solubility of hydrogen in a quality certified eutectic PbLi alloy | Igor Peñalva |
| PS1-43 | ABSTRACT-3abc | Hydrogen Extraction from a Helium Purge Gas. Comparison of ZrCo/ZAO Getter Material | Nicolas Bekris |
| PS1-44 | ABSTRACT-5a6c | Thermal-hydraulic assessment of the inlets and outlets of the Steam Generator mock-up for the EU DEMO WCLL | Danilo Caterino |
| PS1-45 | ABSTRACT-4146 | Mechanical testing of ceramic materials in liquid Pb-16Li at elevated temperatures | Roman Petráš |
| PS1-45B | ABSTRACT-d837 | Major improvements in the WCLL TBM design towards next review gates | Fernando Rueda |
PS1 - TOPIC C. Fuel Cycle and Tritium Processing
| ORDER OF POSTER | ABSTRACT ID | TITLE | PRESENTER |
|---|---|---|---|
| PS1-46 | ABSTRACT-a9ad | Experimental investigation of tritium release behavior from neutron irradiated LiAlO2 with Zr for tritium production in high-temperature gas-cooled reactor | Hiroki Isogawa |
| PS1-47 | ABSTRACT-3656 | Simulation and concept design of continuous mercury-driven vacuum pumps for EU-DEMO | Tim Teichmann |
| PS1-48 | ABSTRACT-6d6f | Hydrogen retention investigation in ITER monoblock using Lattice Boltzmann method | Jiewei Wu |
| PS1-49 | ABSTRACT-c1bc | Tritium-compatible monitoring of ozone production and depletion rates for the decontamination of tritiated surfaces | Dominic Batzler |
| PS1-50 | ABSTRACT-dca1 | Effects of Impurity Gases on Hydrogen Permeation in Pd-Ag Pipe | Kentaro Masuta |
| PS1-51 | ABSTRACT-088a | Development of the design of a stackable Permeator-Against-Vacuum mock-Up for tritium extraction from liquid PbLi at low speed | Andres Gomez |
| PS1-52 | ABSTRACT-129d | Investigations on Hydrogen Isotopes Separation Factor Employing Palladium-based Solid Metallic Membranes | Gheorghe Bulubasa |
| PS1-53 | ABSTRACT-1992 | Liquid metal coolant purification assessment | Sureda Croguennoc |
| PS1-54 | ABSTRACT-1b7f | Aspects concerning the maunufacture of improved contact element for water detritiation system | Gheorghe Ionita |
| PS1-55 | ABSTRACT-dc5e | The Tritium Exposure and Decontamination (TED) Experiment at the Tritium Laboratory Karlsruhe (TLK) | Florian Priester |
| PS1-56 | ABSTRACT-22b4 | The study of AMSB design using adsorption models for coolant purification system of breeding blanket | Seok-Kwon Son |
| PS1-57 | ABSTRACT-2685 | 2D Tritium retention prediction in the ITER/DEMO actively cooled divertor in the presence of neutron-induced defects | Etienne Hodille |
| PS1-58 | ABSTRACT-27e9 | Shape changes of beta-ray induced X-ray spectrum by tritium in aluminum and iron with tritium depth | Masanori Hara |
| PS1-59 | ABSTRACT-2d71 | Tritium accountancy and measurement technology in CN HCCB TBS | Yongtao An |
| PS1-60 | ABSTRACT-3058 | Advanced Modular System for tritium separation by CECE type process | Marius Zamfirache |
PS1 - TOPIC D. Material Engineering for FNT
| ORDER OF POSTER | ABSTRACT ID | TITLE | PRESENTER |
|---|---|---|---|
| PS1-62 | ABSTRACT-bba6 | New processing routes for Zr-based ODS ferritic steels | Moises Oñoro |
| PS1-63 | ABSTRACT-50e6 | Sputtering fabrication and characterization of SiC coatings for breeder blanket applications | Guillermo De La Cuerda Velázquez |
| PS1-64 | ABSTRACT-a37e | Relating the formation energies for oxygen vacancies defects to the structural properties of tungsten oxides | Ryan Kerr |
| PS1-65 | ABSTRACT-392f | Scoping the production of 6Li for ITER and DEMO BB procurements | Marc Guasch |
| PS1-66 | ABSTRACT-0965 | Effects of magnetic field and water radiolysis on corrosion properties of RAFM, F82H | Motoki Nakajima |
| PS1-67 | ABSTRACT-1218 | Investigation of hydrodynamic characteristics of Li jet flowing along concave flow channel using LES for A-FNS | Eiji Hoashi |
| PS1-69 | ABSTRACT-247e | Fusion magnet quench risk increase with radiation damage | Jacob John |
| PS1-70 | ABSTRACT-2a2f | Creep Rupture Behavior of TIG Weldment of CLAM Steel | Junyu Zhang |
| PS1-71 | ABSTRACT-be68 | Thermo-Hydraulic Analyses of the Heat Transfer in the Rib-Roughened Air Cooling Channel | Sergej Gordeev |
| PS1-72 | ABSTRACT-34bd | Galvanic process for infiltration of W fibre-reinforced heat sinks | Patrick Junghanns |
PS1 - TOPIC E. Vacuum Vessel and Ex-vessel Systems
| ORDER OF POSTER | ABSTRACT ID | TITLE | PRESENTER |
|---|---|---|---|
| PS1-73 | ABSTRACT-091b | Structural and thermal fluid dynamic analyses of the ITER Pressure Suppression System considering no stable steam condensation regimes | Luca Berti |
| PS1-74 | ABSTRACT-1e8d | Electromagnetic analysis of the Optical Hinge and Optical Relay Unit of the Wide Angle Viewing System diagnostic for ITER | Alejandro Fernandez Navarro |
| PS1-75 | ABSTRACT-d07c | Dynamic behaviour of the DTT torus complex during seismic events | Marco Fulici |
| PS1-76 | ABSTRACT-660c | Characterization of a NEG cartridge under high pressure conditions | Damiano Paoletti |
| PS1-77 | ABSTRACT-8c65 | Development of Penning ion gauge for fast neutral pressure measurement in VEST | Jeong Wonik |
| PS1-78 | ABSTRACT-0174 | Analysis of the water flow distribution in the Vacuum Vessel of the Divertor Tokamak Test facility | Roberto Bonifetto |
| PS1-80 | ABSTRACT-2d2b | CarMa0NL modelling of disruption forces on COMPASS | Vadim Yanovskiy |
| PS1-81 | ABSTRACT-330a | The FALCON facility for high-power testing of Electron Cyclotron components | Mario Cavinato |
| PS1-82 | ABSTRACT-135e | Maintenance study on WCLL-TBS Ancillary systems in Process Room | Ugo Bonavolontà |
| PS1-83 | ABSTRACT-1745 | Development of a scintillator based fast-ion loss detector for the Wendelstein 7-X stellarator | Anton Jansen Van Vuuren |
| PS1-84 | ABSTRACT-17f1 | Design and Integration of the European Diagnostic Ports of ITER | Iñigo Eletxigerra |
| PS1-84b | ABSTRACT-fbc1 | Thermal-hydraulic and mechanical analysis of the Beam Line Components for the DTT Neutral Beam Injector | Roberto Zanino |
PS1 - TOPIC F. Nuclear System Design
| ORDER OF POSTER | ABSTRACT ID | TITLE | PRESENTER |
|---|---|---|---|
| PS1-85 | ABSTRACT-0693 | Development of transport-activation internal coupling code based on cosRMC and application to fusion reactors analysis | Shengzhe Wang |
| PS1-87 | ABSTRACT-51dd | Operating Conditions of DEMO Divertor Considering Structural Safety and Thermal Efficiency | Yohan Lee |
| PS1-88 | ABSTRACT-fc7a | Conceptual design and supporting analysis of a Double-Wall Heat Exchanger for the ARC fusion reactor primary cooling system | Francesco Colliva |
| PS1-89 | ABSTRACT-049d | Overview and Origin of the STEP Design Point | Stuart Muldrew |
| PS1-90 | ABSTRACT-0682 | Design and development of the fiber Bragg grating sensors for MITICA beamline | Carlo Poggi |
| PS1-91 | ABSTRACT-0752 | Applicability of the ITER-like EC HVPS design to the DEMO ECS | Damien Fasel |
| PS1-92 | ABSTRACT-0be1 | Conceptual Design Study of a Large Bore Superconducting Test Facility Magnet, SUCCEX | Hyun Wook Kim |
| PS1-93 | ABSTRACT-0cff | New Neutron Scanner for Container Inspection based on Nuclear Fusion | Jose Maria Benlloch Baviera |
| PS1-94 | ABSTRACT-0d5b | Neutron Source Modelling for Commissioning Hydrogen Plasmas in Tokamaks | Andrej Žohar |
| PS1-96 | ABSTRACT-12b3 | Study on the Shutdown Dose Rate Calculation Method based on Nuclide Activation | Zhengyun Dong |
| PS1-97 | ABSTRACT-7a68 | The ITER Radial Neutron Camera ex-port system: nuclear analyses in support of its design development | Fabio Moro |
PS1 - TOPIC G. Safety Issues and Waste Management
| ORDER OF POSTER | ABSTRACT ID | TITLE | PRESENTER |
|---|---|---|---|
| PS1-101 | ABSTRACT-14cb | Development of radiation sources based on CAD models for nuclear analysis of IFMIF-DONES lithium loop | Juan García Bueno |
| PS1-102 | ABSTRACT-38f3 | Tritium Behavior in Soil and Mineral Rock Components used for Plant Cultivation | Michael Portuphy |
| PS1-103 | ABSTRACT-5540 | Application of a Multiphysics simulation tool to an in-box LOCA in the breeding unit of the WCLL-BB of LIFUS5/Mod4 | Vittorio Cossu |
| PS1-104 | ABSTRACT-07b4 | Fast Shutter optioneering study for the ITER Disruption Mitigation System | András Zsákai |
| PS1-105 | ABSTRACT-7ddf | ITER DMS Fast Shutter development and laboratory testing | Daniel Imre Refy |
| PS1-106 | ABSTRACT-17b6 | Investigation of a LaBr(Ce)-based Spectrometer at the KSTAR Tokamak with mixed neutron-gamma radiation fields | Youngseok Lee |
| PS1-107 | ABSTRACT-1fd7 | Establishing a Dependable Coolant Purification System Design for Fusion Reactors: Achieving Objectives through RAVAD Testing | Changwook Shin |
| PS1-109 | ABSTRACT-3748 | DEMO Toroidal Field Coil Fast Discharge Unit Integration Studies | Thomas Franke |
| PS1-110 | ABSTRACT-4386 | Shielding optimization to reduce the radiation field in the accelerator systems of IFMIF-DONES | Antonio Jesus Lopez Revelles |
| PS1-111 | ABSTRACT-da07 | New electrode supports in Neutral Beam Injection for HV breakdown incidence reduction risk | Vincenzo Variale |
| PS1-111b | ABSTRACT-91d9 | Comprehensive study of ITER Hot Cell radiation conditions for design optimisation within ALARA approach | Pablo Martínez Albertos |
| PS1-111c | ABSTRACT-e7e5 | Radwaste analysis and package optimization with the radwaste calculator and application to the ITER 1D benchmark and the IVVS ITER system | Álvaro Cubi |
PS1 - TOPIC H. Models and Experiments for FNT
| ORDER OF POSTER | ABSTRACT ID | TITLE | PRESENTER |
|---|---|---|---|
| PS1-112 | ABSTRACT-2373 | Construction of GVR Weight Windows Mapas from Very Low Density Transport Simulations | Gonzalo Farga-Niñoles |
| PS1-113 | ABSTRACT-32ae | A Reduced-Order Model to Estimate First Wall Particle and Heat Fluxes for Systems Codes | Tiago Pomella Lobo |
| PS1-117 | ABSTRACT-0dd9 | Neutron Emission characterisation of IPR 14 MeV neutron generator | Mitul Abhangi |
| PS1-119 | ABSTRACT-19f1 | Experimental validation of the fluid solver for SPIDER (FSFS2D) | Roman Zagorski |
| PS1-120 | ABSTRACT-1ae4 | Results from the Prototype Testing Phase of the CHIMERA Heating System | Petros Efthymiou |
| PS1-121 | ABSTRACT-8b16 | Beam emission spectroscopy modeling on the ITER diagnostic beam | Péter Balázs |
| PS1-123 | ABSTRACT-21c1 | Digital image correlation for modal analysis of mock-up blanket components | Alex Marsh |
| PS1-124 | ABSTRACT-2575 | Electromagnetic modelling of the central column for the STEP programme | Jiabin Yang |
| PS1-125 | ABSTRACT-2584 | Assessment of the relevancy of ENEA Water Loop facility with respect to ITER WCLL TBS Water Cooling System by considering their thermal-hydraulic performances during selected transient conditions | Bruno Gonfiotti |
PS1 - TOPIC I. Repair and Maintenance
| ORDER OF POSTER | ABSTRACT ID | TITLE | PRESENTER |
|---|---|---|---|
| PS1-126 | ABSTRACT-088c | Breeding Blanket Segment Handling: Kinematics and Dynamics | Hjalte Durocher |
| PS1-127 | ABSTRACT-ebeb | Conceptual design of DEMO Breeding Blanket In-Vessel Toroidal Transporter | Vincenzo Claps |
| PS1-128 | ABSTRACT-068f | Induction brazing of DEMO’s large bore cooling pipes | Jeno Kadi |
| PS1-129 | ABSTRACT-0ba9 | Applicability Study of Mechanical Multi-Pipe Connections for DEMO Breeding Blanket Maintenance concept | Azman Azka |
| PS1-130 | ABSTRACT-0c65 | Fabrication and Load Test of ITER Assembly Tools for Lifting Heavy Components | Jinho Bae |
| PS1-131 | ABSTRACT-1191 | Architecture for human-in-the-loop control of robotic equipment for remote maintenance: case study on the NEFERTARI project | Alessandro Sofia |
| PS1-132 | ABSTRACT-1309 | Overview of in-bore pipe cutting and welding tools for the maintenance of CFETR and EU-DEMO | Donato Sorgente |
| PS1-133 | ABSTRACT-1b98 | Design and development of a Digital Maintenance Manual for RH operations in fusion reactors | Giuseppe Di Gironimo |
| PS1-134b | ABSTRACT-b9f3 | Replacement strategy of the EU-DEMO and CFETR breeding blanket pipes | Rocco Mozzillo |
PS1 - TOPIC J. Burning Plasma Control and Operation
| ORDER OF POSTER | ABSTRACT ID | TITLE | PRESENTER |
|---|---|---|---|
| PS1-135 | ABSTRACT-3fa0 | On the accuracy of the fast time resolution inversion method for the detection of different radiation patterns in fusion reactors | Ivan Wyss |
| PS1-136 | ABSTRACT-d419 | Study on burning start-up scenario in DEMO with consideration of fuel isotope effect and helium ash transport | Kento Miyamae |
| PS1-137 | ABSTRACT-0aa7 | Proposal of a control scheme for testing a centrifuge-based pellet injection system in DIPAK-PET | Bernhard Ploeckl |
| PS1-138 | ABSTRACT-0ecf | Development of a one-step ion optics for beam emission spectroscopy and atomic beam probe measurements | Gábor Anda |
| PS1-139 | ABSTRACT-1031 | Assembly Procedure and Tooling Development for In-Situ Winding of ITER In-Vessel Vertical Stability Coils | Kyoungo Nam |
| PS1-139b | ABSTRACT-ecdb | Design and Performance analysis of a High Field Side antenna for Plasma Position Reflectometry control on DTT | Jorge Santos |
PS1 - TOPIC K. Inertial Confinement Fusion Studies and Technologies
| ORDER OF POSTER | ABSTRACT ID | TITLE | PRESENTER |
|---|---|---|---|
| PS1-140 | ABSTRACT-1eff | Theoretical methods for stopping power of plasmas in magnetic fields | Manuel D Barriga-Carrasco |
| PS1-141 | ABSTRACT-421c | Development of a Novel IEC Neutron Research Facility | Tom Wallace-Smith |
| PS1-142 | ABSTRACT-489b | Spatially resolved hot implosion core conditions via Kr K-shell X-ray spectroscopy | Enac Gallardo-Diaz |
| PS1-143 | ABSTRACT-5543 | Relativistic effects on the stopping power of high atomic number plasmas | Javier Chacón Gijón |
| PS1-144 | ABSTRACT-00a7 | Effects of impurities in DT plasmas on burning gains and self-heating and ignition curves in ion fast ignition scheme. | Pablo Rodríguez Beltrán |
TUESDAY 12TH
PS2 - TOPIC A. Plasma-Facing High Heat Flux Components
| ORDER OF POSTER | ABSTRACT ID | TITLE | PRESENTER |
|---|---|---|---|
| PS2-1 | ABSTRACT-1204 | Thermal-hydraulic study of the Primary Heat Transport System of the EU-DEMO Divertor Plasma Facing Components | Silvia Vacca |
| PS2-2 | ABSTRACT-c83e | Beryllium limiters from JET tokamak with the ITER-like wall: Surface modification and fuel retention | Laura Dittrich |
| PS2-3 | ABSTRACT-607a | Experimental Evaluation of Thermal-Fluids Performance of Helium-Cooled Flat Plate Divertor | Daniel Lee |
| PS2-4 | ABSTRACT-d517 | Design Progress of DTT Divertor Fixation System | Nicola Massanova |
| PS2-5 | ABSTRACT-6ab4 | Effect of neutron irradiation on the W/CuCrZr joint strength | Kateryna Poleshchuk |
| PS2-7 | ABSTRACT-f5c0 | Engineering tool to optimize for leading edges in a full-tungsten divertor for W7-X | Antara Menzel-Barbara |
| PS2-8 | ABSTRACT-fba8 | Brittle Fracture Assessment for Tungsten and Tungsten alloy components | Mathias Jetter |
| PS2-11 | ABSTRACT-243d | Manufacturing and high heat flux testing of zirconium carbide tungsten monoblock for CFETR | Le Han |
| PS2-12 | ABSTRACT-24b3 | Modelling of NBI shine-through in ITER PFPO phase to limit heat fluxes on first wall | Pietro Vincenzi |
| PS2-13 | ABSTRACT-26e7 | Coupled Model for Liquid Lithium Plasma Facing Components | Andrei Khodak |
| PS2-14 | ABSTRACT-29c7 | Thermal and structural analyses of an additive manufactured panel mock-up for Wendelstein7-X | Zhongwei Wang |
| PS2-15 | ABSTRACT-3164 | Screening of the metal foil from energetic neutrals | Yuri Igitkhanov |
| PS2-16 | ABSTRACT-3327 | Development of non-destructive X-ray based techniques for evaluation of Tungsten-metal joints quality | Ion Tiseanu |
| PS2-17 | ABSTRACT-380c | Integrity assessment of armour materials for innovative high heat flux components for fusion reactor by the ultrasonic method | Emanuele Cacciotti |
| PS2-18 | ABSTRACT-41fb | Optimization in cooling design of poloidal horseshoe limiter concept for JA DEMO | Weixi Chen |
| PS2-20 | ABSTRACT-4601 | Overview of Japan-US Collaboration FRONTEIR Project —Fusion Research Oriented to Neutron Irradiation Effects and Tritium Behavior at Material Interfaces— | Yuji Hatano |
| PS2-21 | ABSTRACT-491a | Research on a renewable extruded plasma-facing divertor material for magnetic fusion energy reactors | Eric Hollmann |
| PS2-22 | ABSTRACT-4979 | Hypothetical porous medium concept as a virtual swirl tape: A novel modelling technique towards efficient CFD simulation of swirl tape cooling pipe | Andrea Quartararo |
PS2 - TOPIC B. Blanket Technology
| ORDER OF POSTER | ABSTRACT ID | TITLE | PRESENTER |
|---|---|---|---|
| PS2-23 | ABSTRACT-8b63 | Equilibrium distribution of lithium isotope between liquid metal and chloride molten salt containing CsCl | Ryo Ito |
| PS2-24 | ABSTRACT-8dda | Quest for magneto-convective unstable flow regime in horizontal MHD duct flows | Srikanta Sahu |
| PS2-25 | ABSTRACT-4472 | Tritium Breeding Ratio Optimization in Simple Multi-Layer Blanket with Genetic Algorithm | Soobin Lim |
| PS2-26 | ABSTRACT-9c69 | Neutronic Studies for the Dual Coolant Lithium Lead Breeding Blanket HELIAS design | David Sosa Sánchez |
| PS2-27 | ABSTRACT-5f0a | Fabrication and characterization of enamel coating as a promising hydrogen and oxygen diffusion barrier | Yuka Shimizu |
| PS2-28 | ABSTRACT-f33d | Buoyancy-assisted thermal convection and tritium diffusion in an upward magnetohydrodynamic duct flow | Nian-Mei Zhang |
| PS2-29 | ABSTRACT-fe8f | Numerical study of MHD mixed convection flow in the the EU DEMO WCLL breeding blanket | Long Chen |
| PS2-30 | ABSTRACT-41ef | Magneto-hydraulic and MHD mixed convection flow in a rectangular channel filled with streamwise obstacles | Alessandro Tassone |
| PS2-31 | ABSTRACT-45c0 | Analysis and modelling of gas-liquid contactors for tritium extraction from eutectic PbLi | Eduardo Garciadiego-Ortega |
| PS2-32 | ABSTRACT-490c | Helical-shaped Double Wall Tubes solution for the Breeding Zone cooling in the WCLL Breeding Blanket | Pietro Maccari |
| PS2-33 | ABSTRACT-e23e | Implications of Reduced Geometric Modeling on MHD Predictions in a Liquid Metal Breeding Blanket Concept | Alice Ying |
| PS2-34 | ABSTRACT-507c | Gas-Liquid Contactor experimental campaign in TRIEX-II facility | Francesca Papa |
| PS2-35 | ABSTRACT-5489 | Investigation and Qualification on First Wall Fabrication Technologies of Fusion Reactor Blanket in China | Bo Huang |
| PS2-36 | ABSTRACT-3d8f | Experimental investigation of the corrosion behavior of Eurofer97 steel in contact with Lithium ceramic breeder pebbles under specific Helium Cooled Pebble Bed breeding zone atmosphere | Regina Krüssmann |
| PS2-37 | ABSTRACT-5ba8 | Evaluation of the impact of plasma operation scenarios on the fusion reactor blanket design using an integrated numerical plasma and neutronics analysis suite | Rin Choi |
| PS2-38 | ABSTRACT-6076 | Functional tests for water cooled ceramic breeder blanket system using full-scale mockups | Takanori Hirose |
| PS2-39 | ABSTRACT-6217 | Characterization of aged Li4SiO4 pebbles performance | Rosa Lo Frano |
| PS2-40 | ABSTRACT-623c | A multi-region MHD OpenFOAM solver for fusion reactor analysis | Simone Siriano |
| PS2-41 | ABSTRACT-64ca | Tritium release from titanium beryllide after high-dose neutron irradiation | Vladimir Chakin |
| PS2-42 | ABSTRACT-684e | Optimization of the first wall of WCCB for the CFETR | Li Yuanjie |
| PS2-43 | ABSTRACT-f826 | Lumped Parameter Porous Flow Modeling of Solid Tritium Breeding Blanket Materials | Monica Gehrig |
| PS2-44 | ABSTRACT-6af3 | Characteristics of Pb-16Li droplets generated by a perforated plate | Ladislav Vala |
| PS2-45 | ABSTRACT-6c08 | Thermofluid-Dynamic and Thermal-Structural Assessment of the EU-DEMO WCLL “Double Bundle” Breeding Blanket Concept Left Outboard segment | Pietro Alessandro Di Maio |
| PS2-46 | ABSTRACT-6c4e | Adaptation of the first wall cooling circuits to achieve an efficient distribution of the coolant flow in the SMS DCLL breeding blanket | Jose Ángel Nogueron Valiente |
PS2 - TOPIC C. Fuel Cycle and Tritium Processing
| ORDER OF POSTER | ABSTRACT ID | TITLE | PRESENTER |
|---|---|---|---|
| PS2-47 | ABSTRACT-078e | Tritium Management in ITER Test Blanket Systems Port Cell for Maintenance Operations | Yingwu Jiang |
| PS2-49 | ABSTRACT-d88d | Increasing the accuracy of the Viscosity Measurement Apparatus (ViMA) for measuring the viscosity of tritium between 77K and 300K | Johanna Wydra |
| PS2-50 | ABSTRACT-758e | Process Design of Hydrogen Isotope Separation using Temperature Swing Absorption in the EU-DEMO Fuel Cycle | Annika Uihlein |
| PS2-52 | ABSTRACT-36e3 | Plasma Exhaust Processing System with Tritium Compatible Reciprocating Pump | Yoshifumi Kume |
| PS2-53 | ABSTRACT-3b4c | A magnetic compression platform for compact torus injector (central fuelling system for EAST tokamak) | Mingsheng Tan |
| PS2-54 | ABSTRACT-4884 | Experimental results to evaluate the use of cryopumps to separate helium from hydrogen isotopes in a tokamak exhaust stream | Sophie Davies |
| PS2-55 | ABSTRACT-4a21 | Analysis of super-permeable membrane surfaces for tritium separation applications | Robert Kolasinski |
| PS2-56 | ABSTRACT-50cc | Highly efficient and direct recovery of low-pressure hydrogen isotopes from tritium extraction gas by Pd-Y alloy membrane permeator | Xingwen Feng |
| PS2-57 | ABSTRACT-5117 | Preliminary evaluation of NEG materials in view of CMSB replacement in HCPB TER architecture | Alina Elena Niculescu |
| PS2-58 | ABSTRACT-5577 | Development of lab-scale Atmospheric Molecular Sieve Bed and generation of experimental break through curves for adsorption studies | Deepak Yadav |
| PS2-60 | ABSTRACT-58d1 | The influence of the extraction of gas/liquid samples on the isotopic separation regime of the CECE (Combined Electrolysis Catalytic Exchange) process | Anisia Mihaela Bornea |
| PS2-61 | ABSTRACT-5a68 | Influence of chemical form of tritium extracted from solid breeder on tritium balance in fuel cycle system of fusion reactors | Kazunari Katayama |
PS2 - TOPIC D. Material Engineering for FNT
| ORDER OF POSTER | ABSTRACT ID | TITLE | PRESENTER |
|---|---|---|---|
| PS2-62 | ABSTRACT-a9a0 | An effectiveness of deuterium electrochemical charging method for a desorption study in low-alloy steel and pure Zr | Zuoming Wang |
| PS2-64 | ABSTRACT-183c | Quantification of the uncertainties in the determination of the final dose of the HFTM samples in IFMIF-DONES | Irene Alvarez-Castro |
| PS2-65 | ABSTRACT-c0b9 | Tritium permeation through Inconel 600 under high temperature, high pressure water environment: Influence of oxidation of coexisting materials | Azusa Matsumoto |
| PS2-66 | ABSTRACT-d586 | Predicting the ductile-to-brittle transition (DBT) in BCC fusion materials | Florence Goodrich |
| PS2-67 | ABSTRACT-377f | Effect of Hydrogen on stress corrosion cracking behavior of Oxide Dispersion Strengthened Steel Compared with RAFMs | Rongrong Luo |
| PS2-68 | ABSTRACT-05ad | High-throughput evaluation of primary radiation damage on combinatorial thick films | Greg Wallace |
| PS2-70 | ABSTRACT-44fc | scCVD diamond based µ-loss monitors for neutron detection at low temperature | Donny Cosic |
| PS2-71 | ABSTRACT-4502 | Deuterium permeation of low-activation vanadium alloys possible for reuse in a short time in fusion reactors | Yuji Yamauchi |
| PS2-72 | ABSTRACT-5bc3 | Research Progress of High Strength Jacket Based on Super-Austenitic Stainless Steel for Future Fusion Magnets | Weijun Wang |
| PS2-73 | ABSTRACT-6cec | Integration and commissioning of the water-cooling system for the beam dump of the linear IFMIF prototype accelerator (LIPAc) | Kohki Kumagai |
PS2 - TOPIC E. Vacuum Vessel and Ex-vessel Systems
| ORDER OF POSTER | ABSTRACT ID | TITLE | PRESENTER |
|---|---|---|---|
| PS2-74 | ABSTRACT-979c | Corrosion Phenomena and Deposits in ITER Neutral Beam Test Facility Primary Cooling Circuits | Caterina Cavallini |
| PS2-75 | ABSTRACT-9cee | Iterative design and structural assessment of the DTT divertor interface to Vacuum Vessel | Andrea Zoppoli |
| PS2-76 | ABSTRACT-324b | Preliminary Analysis of Phase Transition Characteristics in case of in-vessel LOCA for CFETR Divertor Primary Heat Transfer System | Jinxuan Zhou |
| PS2-77 | ABSTRACT-ed11 | Mechanical Design of ITER Radial Neutron Camera Ex-Port system | Enrico Occhiuto |
| PS2-78 | ABSTRACT-25c7 | Conceptual design studies and preliminary analysis of the STEP Vacuum Vessel | Nisarg Patel |
| PS2-79 | ABSTRACT-0467 | Thermal-hydraulic analysis of the CORC® conductor for the DEMO CS coil | Aleksandra Dembkowska |
| PS2-80 | ABSTRACT-2ae3 | Thermal analysis between the high-temperature nitrogen and in-vessel components in the EAST baking process | Zhe Liu |
| PS2-81 | ABSTRACT-0803 | Design of a Position Monitoring System for the ITER Radial Neutron Camera | Silvia Cesaroni |
| PS2-82 | ABSTRACT-08fa | Analysis and optimization of the secondary circuit for the option WCLL BB Direct Coupling with small ESS of the EU DEMO power plant | Monika Lewandowska |
| PS2-83 | ABSTRACT-3da8 | Investigation on the pressure drop characteristics of ITER thermal shield cooling pipes | Kwanwoo Nam |
| PS2-84 | ABSTRACT-49bb | Design and Performance Research of Baking for HL-2M Vacuum Vessel | Hong Ran |
PS2 - TOPIC F. Nuclear System Design
| ORDER OF POSTER | ABSTRACT ID | TITLE | PRESENTER |
|---|---|---|---|
| PS2-89 | ABSTRACT-7231 | Overview on the conceptual design of TRUST: the new nuclear fusion experiment of University of Tuscia | Simone Carusotti |
| PS2-90 | ABSTRACT-1c2f | Development Progress of Advanced Neutronics Software TopMC | Jing Song |
| PS2-91 | ABSTRACT-1fce | Design and integration of Tokamak Coolant Systems based on water technology in the EU-DEMO | Ivo Moscato |
| PS2-93 | ABSTRACT-2560 | Development of a Cherenkov probe with high time resolution for runaway electron measurements in the HL-2M Tokamak | Yuxuan Zhu |
| PS2-94 | ABSTRACT-cc48 | Nuclear analyses for the ITER Equatorial Port #8 | Andrea Colangeli |
| PS2-95 | ABSTRACT-433d | Development and Test of In-vessel Coil System for Magnetic Compression of Field Reversed Configuration Plasmas | Qinglong Zhang |
| PS2-96 | ABSTRACT-4966 | A Two-Step Neutron Energy Regulation Method based on Multi-Dimensional Response Matrix | Bin Wu |
| PS2-97 | ABSTRACT-5089 | Integration of the Beam Dynamics and Neutronics simulation tools for the IFMIF-DONES accelerator design | Marta Ternero Gutiérrez |
| PS2-98 | ABSTRACT-5105 | Balance of Plant conceptual design of EU DEMO integrating different Breeding Blanket concepts | Matteo Zaupa |
| PS2-99 | ABSTRACT-6d3b | Analysis on fluid-induced acoustic resonance coupling in series T-structure fusion device | Lidong Yao |
PS2 - TOPIC G. Safety Issues and Waste Management
| ORDER OF POSTER | ABSTRACT ID | TITLE | PRESENTER |
|---|---|---|---|
| PS2-101 | ABSTRACT-aa67 | Requirements analysis for fusion reactor safety analysis software development based on existing one for fission reactor | Yifei Wang |
| PS2-102 | ABSTRACT-c750 | Electronic effects of aryl groups in modified polysilane liquid scintillator on its fluorescence properties | Wenjing Pu |
| PS2-103 | ABSTRACT-dc97 | Neural network-based source biasing to speed-up challenging MCNP simulations | Elena Martínez Fernández |
| PS2-105 | ABSTRACT-51a6 | Qualitative safety analysis for the Divertor Tokamak Test (DTT) | Tonio Pinna |
| PS2-106 | ABSTRACT-5412 | Mechanical design of a Fast Shutter for the Disruption Mitigation System | Richard Csiszar |
| PS2-107 | ABSTRACT-545a | Overview of detritiation processes applicable to tritiated soft housekeeping waste | Karine Liger |
| PS2-109 | ABSTRACT-56aa | LIFUS5/Mod3 Series-E Experiment Test 6.1 for SIMMER-III code validation | Satya Prakash Saraswat |
| PS2-110 | ABSTRACT-5888 | Eddy current actuated fast valve development for disruption mitigation applications | Domonkos Nagy |
| PS2-111 | ABSTRACT-58c0 | A Proportionate Approach to Regulation for Fusion Power Plants | Bethany Colling |
PS2 - TOPIC H. Models and Experiments for FNT
| ORDER OF POSTER | ABSTRACT ID | TITLE | PRESENTER |
|---|---|---|---|
| PS2-113 | ABSTRACT-b35e | ITER relevant conditions of the closed-water activation loop at the JSI TRIGA | Domen Kotnik |
| PS2-114 | ABSTRACT-4d88 | Effect of argon additive in Cs-free negative hydrogen ion source TPDsheet-U | Kaito Miura |
| PS2-115 | ABSTRACT-f064 | Preliminary Electromagnetic Analyses of the Effects of Plasma Disruptions on SPARC Vacuum Vessel for the Construction of a Synthetic VDE Database | Mattia Scarpari |
| PS2-116 | ABSTRACT-fed0 | Low-power testing of the EU-DEMO Steam Generator mock-up | Alessandra Vannoni |
| PS2-117 | ABSTRACT-262d | Validation of the GETTHEM Tritium Transport and Permeation model Against Experimental Data | Fabrizio Lisanti |
| PS2-118 | ABSTRACT-2696 | Design of the ENEA Water Loop facility in support of the design of the DEMO Water Cooled Lead Lithium Breeding Blanket | Pietro Arena |
| PS2-119 | ABSTRACT-2940 | Thermal-hydraulics characterization of the Steam Generator mock-up during operational transients in STEAM facility in support of the design of the DEMO WCLL BoP | Marica Eboli |
| PS2-122 | ABSTRACT-38bd | A Tungsten-wall Sputtering Model for the Plasma Start-up Simulation in Tokamaks | Sangil Lee |
| PS2-123 | ABSTRACT-4c11 | Technology trade-off for remote lithium jet thickness monitoring system | Paloma Matia |
| PS2-124 | ABSTRACT-4062 | Development of liquid metal key technology for advanced nuclear system | Yong Song |
| PS2-125 | ABSTRACT-47d6 | Nuclear irradiation rig design for the Irradiation of ITER prototype bolometers in SCK-CEN BR2 reactor | Jorge Aguilar Villamor |
| PS2-126 | ABSTRACT-4a47 | Combined analysis of laser interferometer and microwave reflectometer for improved density measurement on HL-2A tokamak | Dong Li |
PS2 - TOPIC I. Repair and Maintenance
| ORDER OF POSTER | ABSTRACT ID | TITLE | PRESENTER | |
|---|---|---|---|---|
| PS2-127 | ABSTRACT-c9ce | An obstacle avoidance path planning algorithm to simulate hyper redundant manipulators for tokamaks maintenance | Sara Buonocore | |
| PS2-128 | ABSTRACT-a1cd | Interactive simulations for logistics and maintenance of DONES | Andrea Benito Fuentes | |
| PS2-129 | ABSTRACT-2ecf | Material Flow Planning in Fusion Test Facilities | Timo Lehmann | |
| PS2-130 | ABSTRACT-310d | Remote Maintenance Study for the DEMO | Namil Her | |
| PS2-131 | ABSTRACT-31dd | Maintenance and optimization of the TCV power supply system | Ugo Siravo | |
| PS2-132 | ABSTRACT-3635 | The Electro-hydraulic Mix-drive Robotic Platform Used for General Technology Research of the Remote Handling in Tokamak Devices | Chao Huang | |
| PS2-133 | ABSTRACT-d583 | Linear IFMIF Prototype Accelerator (LIPAc) Radio Frequency Quadrupole’s (RFQ) RF couplers enhancement towards CW operation at nominal voltage | Fabio Cismondi | |
| PS2-134 | ABSTRACT-3af3 | Research on gas-liquid two-phase counter-current flow limitation Mechanism for Fusion Reactor Airflow Drying Behavior | Weibao Li |
PS2 - TOPIC J. Burning Plasma Control and Operation
| ORDER OF POSTER | ABSTRACT ID | TITLE | PRESENTER |
|---|---|---|---|
| PS2-136 | ABSTRACT-20f7 | Design of a Cherenkov gamma-ray counter for fusion power measurements in ITER | Oscar Putignano |
| PS2-137 | ABSTRACT-57a6 | Design of the In-Vessel Componens of ITER In-Vessel Neutron Flux Monitor Equipped with Microfission Chambers to Withstand High Thermal Load | Masao Ishikawa |
| PS2-138 | ABSTRACT-7583 | Experimental Environment for Testing the Shattered Pellet Injection of KSTAR | Soohwan Park |
PS2 - TOPIC K. Inertial Confinement Fusion Studies And Technologies
| ORDER OF POSTER | ABSTRACT ID | TITLE | PRESENTER |
|---|---|---|---|
| PS2-139 | ABSTRACT-1bc9 | Design of High Power Supply Protection System for CRAFT Sensor Test Platform | Xu Wu |
| PS2-140 | ABSTRACT-7fc9 | Experimental studies of laser-driven Ions and extreme plasmas Interaction | Luca Volpe |
| PS2-141 | ABSTRACT-28a5 | Novel analysis method for BNCT pharmacokinetic evaluation by use of a neutron source based on Inertial electrostatic confinement fusion and particle detector | Mahmoud Bakr |
| PS2-144 | ABSTRACT-7054 | Spectroscopic characterization of core conditions in highly magnetized cylindrical implosions | Ricardo Florido |
| PS2-145 | ABSTRACT-737a | Inadequacy of magnetohydrodynamics to model shock waves in some Inertial Confinement Fusion settings | Antoine Bret |
THURSDAY 14TH
PS3 - TOPIC A. Plasma-Facing High Heat Flux Components
| ORDER OF POSTER | ABSTRACT ID | TITLE | PRESENTER |
|---|---|---|---|
| PS3-2 | ABSTRACT-4e23 | Investigation of Erosion/Deposition by Charge-exchange Neutrals in Far-SOL Region | Soo-Hyun Son |
| PS3-3 | ABSTRACT-6340 | Thermal-hydraulic assessment of the EU DEMO Upper Limiter | Antonio Froio |
| PS3-4 | ABSTRACT-64a5 | Molecular dynamics modelling of the stress effect on diffusion behavior of hydrogen in tungsten | Xingang Yu |
| PS3-6 | ABSTRACT-048b | Engineering strategy for the European DEMO divertor: challenges and approaches | Jeong-Ha You |
| PS3-8 | ABSTRACT-710b | Experimental investigation on the MHD effects of liquid metal film flow relating to the plasma-facing components | Juan-Cheng Yang |
| PS3-10 | ABSTRACT-78cd | Design of in-Vessel Mirror of ITER Poloidal Polarimeter | Ryota Imazawa |
| PS3-11 | ABSTRACT-8736 | Manufacturing of advanced target mock-ups for the DEMO Divertor | Pierdomenico Lorusso |
| PS3-12 | ABSTRACT-8bf5 | Characteristics of detached/attached plasma formation on ICR heating in a linear divertor plasma simulator TPDsheet-U | Akira Tonegawa |
| PS3-14 | ABSTRACT-d12e | A calorimetric evaluation method for beam targets with IR imaging: implementation for the negative ion source BATMAN Upgrade | Guillermo Orozco |
| PS3-15 | ABSTRACT-03a1 | Wrapping the Sun in a Blanket and putting it in a Box - The Design and Manufacture of Plasma Facing Components | Garreth Aspinall |
| PS3-16 | ABSTRACT-9791 | Mock-ups fabrication by HRP technology with advanced W-alloy monoblocks for DEMO divertor target | Francesco Crea |
| PS3-17 | ABSTRACT-98cd | Development of Divertor Heat Removal Component Using Tungsten-Copper Alloy Bonding with SPS Method | Takanori Murase |
PS3 - TOPIC B. Blanket Technology
| ORDER OF POSTER | ABSTRACT ID | TITLE | PRESENTER |
|---|---|---|---|
| PS3-19 | ABSTRACT-7419 | Preliminary Design and Analysis Activities of the Deuteron Accelerator Target for Tritium Breeding Unit Test | Sungjin Kwon |
| PS3-20 | ABSTRACT-789e | Two-way coupled CFD-DEM investigation on gas and powder flow characteristics of pebble bed of Fusion Blanket | Jian Wang |
| PS3-21 | ABSTRACT-78ec | Weldability of F82H for WCCB TBM Application | Wenhai Guan |
| PS3-22 | ABSTRACT-7d51 | Design and Analysis of the HCCB Breeding Blanket with Casing Structures for DEMO reactor | Xiaoyong Wang |
| PS3-23 | ABSTRACT-7fc5 | Basic study on Simulating Moving Bed chromatography for separation of lithium isotopes | Takahiko Sugiyama |
| PS3-24 | ABSTRACT-7fee | Influence Of Various Gases and Water Vapors on The Processes of Tritium Release from Two-Phase Lithium Ceramics | Inesh Kenzhina |
| PS3-25 | ABSTRACT-876c | Updated conceptual design and analysis of breeding blanket modules integrated with divertor for CFETR | Xuebin Ma |
| PS3-26 | ABSTRACT-91bf | Characterization of a Permeator Against Vacuum mock-up with niobium membrane in lithium-lead eutectic at 350°C | Alessandro Venturini |
| PS3-27 | ABSTRACT-91d7 | Main nuclear responces of the DEMO tokamak with different in-vessel components configurations | Jin Hun Park |
| PS3-28 | ABSTRACT-0add | Numerical and experimental analysis of magneto-convective flows around pipes | Chiara Mistrangelo |
| PS3-29 | ABSTRACT-9e1b | EUROfusion and F4E collaboration for the European Test Blanket Module | Francesca Fantini |
| PS3-30 | ABSTRACT-9e3f | Laser powder bed fusion additive manufacturing of ODS-RAFM steel by prefabricated multi-component nano-oxides | Wei Chen |
| PS3-31 | ABSTRACT-a755 | Preliminary thermo-mechanical assessment of the Top Cap region of the Water-Cooled Lead-Ceramic Breeder Breeding Blanket alternative concept | Salvatore Giambrone |
| PS3-33 | ABSTRACT-a928 | Thermal-hydraulic study of the EU-DEMO Water Cooled Lithium Lead Breeding Blanket Primary Heat Transport System | Eugenio Vallone |
| PS3-34 | ABSTRACT-e909 | Experimental Investigation of Heat Transfer Performance of the Helium-cooled Annular Gap in the Breeder Zone of the EU-DEMO HCPB Breeding Blanket | Ali Abou-Sena |
| PS3-35 | ABSTRACT-ad6c | Solubility of Chromium in Lead-Lithium Eutectic Alloy | Adéla Gottfriedová |
| PS3-36 | ABSTRACT-bc8a | Electrochemical extraction of nitrogen impurities in liquid lithium using chloride molten salt | Shun Aratani |
| PS3-37 | ABSTRACT-bd5a | Evaluation of the impact of various operation parameters on isotopic exchange process for TER HCPB DEMO | Mirela Draghia |
| PS3-38 | ABSTRACT-c077 | Design and manufacturing of tritium-carrier process pipes and associated guard-pipe for ITER Test Blanket Systems | Romain Pascal |
PS3 - TOPIC C. Fuel Cycle and Tritium Processing
| ORDER OF POSTER | ABSTRACT ID | TITLE | PRESENTER | |
|---|---|---|---|---|
| PS3-39 | ABSTRACT-604b | San Borondón | Tritium Compatible Pump Development | Jim Klein |
| PS3-40 | ABSTRACT-64d8 | San Borondón | Planning Tritium Recovery System for Integrated Breeding Test Facility in South Korea | Min Ho Chang |
| PS3-42 | ABSTRACT-752a | San Borondón | Development of a semiconductor hybrid pulse switch module with high repetitive rate for compact torus injector | Yang Ye |
| PS3-43 | ABSTRACT-76ca | San Borondón | Upgrade and test of the compact torus injection system for the EAST central fuelling | Defeng Kong |
| PS3-44 | ABSTRACT-793f | San Borondón | On the possibility to recover Plasma Enhancement Gases from DEMO tokamak exhaust stream | Vincenzo Narcisi |
| PS3-45 | ABSTRACT-7a71 | San Borondón | Engineering Design of Multiple shattered Pellet Injection System for HL-2M | Yi Hu |
| PS3-46 | ABSTRACT-86c7 | San Borondón | Empirical model for the time dependence of the radio-induced D-T equilibration in a turbulent flow | Simon Niemes |
| PS3-47 | ABSTRACT-898c | San Borondón | Tritium sorption measurement of an elementary tungsten sample by BIXS | Marco Roellig |
| PS3-48 | ABSTRACT-8bda | San Borondón | Tritium Extraction and Accountancy Systems Design for ITER HCCP-TBS | Rafael Bocanegra |
| PS3-49 | ABSTRACT-8d5a | San Borondón | Overview of Tritium Management in WCLL Test Blanket System of ITER | Luigi Candido |
| PS3-50 | ABSTRACT-9cff | San Borondón | Superhydrophilic Metal-Organic Frameworks Film Modified Surface for Tritium Removal from Tritiated Heavy Water | Xiaolong Fu |
PS3 - TOPIC D. Material Engineering for FNT
| ORDER OF POSTER | ABSTRACT ID | TITLE | PRESENTER |
|---|---|---|---|
| PS3-51 | ABSTRACT-6d3d | Fracture toughness evaluation by the 3 points bending for pure tungsten | Ju-Hyeon Yu |
| PS3-52 | ABSTRACT-6d59 | Thermal Cycling of Titanium Beryllide to Simulate its Operating Conditions in DEMO HCPB Breeding Blanket | Ramil Gaisin |
| PS3-53 | ABSTRACT-1925 | Development of the design of a resistivimeter and an electrochemical sensor for impurities detection on liquid lithium for IFMIF-DONES | Julia Romero |
| PS3-54 | ABSTRACT-71b4 | Diffusion bonding of CDS composite with Al2O3 and 316L stainless steel at a Gleeble 3800 | Teteny Baross |
| PS3-55 | ABSTRACT-72b0 | Properties of CLAM Steel after Irradiation in Fission and Spallation Neutron Environment up to 21dpa | Jingping Xin |
| PS3-56 | ABSTRACT-74b1 | Development of thick nanostructured tungsten coatings for ionic radiation protection | Javier Barriga |
| PS3-58 | ABSTRACT-a0e3 | A "proof of principle" experiment quantifying helium nucleation and transport parameters in lead-lithium eutectic (CAVITEST) | Luis Angel Sedano Miguel |
| PS3-59 | ABSTRACT-8d97 | Corrosion Behavior of CLAM steel in Liquid Lead-Lithium Alloy | Xinyu Wang |
| PS3-60 | ABSTRACT-8e61 | Investigation of applicability of long-distance LP system for Li target diagnostics in Fusion Neutron Source | Takafumi Okita |
| PS3-61 | ABSTRACT-8f74 | Engineering design status of IFMIF-DONES high energy beam transport line and beam dump system inside the TIR and RIZ | Llorenç Macià |
| PS3-63 | ABSTRACT-99af | Strength Evaluation of Oxide Scale on FeCrAl Alloys by Micro Double-Notch Shear Test | Naoko Oono-Hori |
PS3 - TOPIC E. Vacuum Vessel and Ex-vessel Systems
| ORDER OF POSTER | ABSTRACT ID | TITLE | PRESENTER |
|---|---|---|---|
| PS3-64 | ABSTRACT-5895 | Electromagnetic Analysis on Conceptual Design of the EU DEMO CE equatorial Laucher | Irene Pagani |
| PS3-65 | ABSTRACT-6660 | Preliminary Assessment of Vertical Motions of HL-2M Vacuum Vessel during 1MA Operation | Yuncong Huang |
| PS3-66 | ABSTRACT-c699 | Electromagnetic Loads on the European DEMO divertor | Gennaro Di Mambro |
| PS3-67 | ABSTRACT-71be | Progress and challenges of the ECH transmission line design for DTT | Alessandro Moro |
| PS3-68 | ABSTRACT-7370 | Core plasma Thomson scattering diagnostic design | Maitane Amarika |
| PS3-69 | ABSTRACT-7b4d | Shutter development study for the ITER Visible Spectroscopy Reference System | Imre Katona |
| PS3-70 | ABSTRACT-839e | Design of the hybrid joint using low and high-temperature superconductors | Mu-Yong Kim |
| PS3-72 | ABSTRACT-9643 | Overcoming reionization issues in the diagnostic neutral beam for the RFX-mod2 experiment | Marco Barbisan |
| PS3-73 | ABSTRACT-a070 | Technology challenges and integration of the plasma position reflectometer in RFX-mod2 | Gianluca De Masi |
| PS3-74 | ABSTRACT-a907 | EU-DEMO Vacuum Vessel Port Closure Plate fastening developments | Thomas Haertl |
| PS3-75 | ABSTRACT-f940 | ITER Visible Spectroscopy Reference System design development status | Ad Verlaan |
PS3 - TOPIC F. Nuclear System Design
| ORDER OF POSTER | ABSTRACT ID | TITLE | PRESENTER |
|---|---|---|---|
| PS3-77 | ABSTRACT-eaf9 | Updates of the Removable Biological Shielding Blocks inside of the Test Cell, part of the Test Systems of IFMIF-DONES | Dénes Oravecz |
| PS3-78 | ABSTRACT-7a61 | Structural assessment of the contamination protection structure placed on the top of the DEMO bioshield roof | Lukasz Ciupinski |
| PS3-79 | ABSTRACT-169e | An overview of steady-state electrical loads in the DEMO fusion power plant | Stefano Panella |
| PS3-80 | ABSTRACT-8458 | Approach to Spatial Integration on a Novel & Complex Major Project – STEP Concept Tokamak | Adam Woods |
| PS3-81 | ABSTRACT-8517 | Thermal-hydraulic analysis and last process design update of the ITER Component Cooling Water System 1 | Giuseppe Agnello |
| PS3-83 | ABSTRACT-97ee | Nuclear analyses for the integration of ITER Equatorial Port 2 | Simone Noce |
| PS3-87 | ABSTRACT-a049 | Neutronic Analyses for the IFMIF-DONES Test Cell and Adjacent Rooms | Arkady Serikov |
| PS3-89 | ABSTRACT-a8ed | Neutronics analysis and workflow for First Light Fusion reactor design. | Jonathan Shimwell |
| PS3-90 | ABSTRACT-a8fb | Design status of the neutrons and gamma-rays diagnostics for the Divertor Tokamak Test (DTT) facility | Daniele Marocco |
| PS3-91 | ABSTRACT-ae98 | Design of a THz interferometer system for Korea Superconducting Tokamak Advanced Research | Dongjae Lee |
| PS3-91b | ABSTRACT-cbb2 | Thermal and structural analyses on different mirrors of the Multi Beam Transmission Line of DTT ECRH system | Alessandra Salvitti |
PS3 - TOPIC G. Safety Issues and Waste Management
| ORDER OF POSTER | ABSTRACT ID | TITLE | PRESENTER |
|---|---|---|---|
| PS3-92 | ABSTRACT-5dc0 | Investigation on MELCOR code capabilities for the simulation of Lithium-Lead chemical interactions for fusion safety applications | Francesco Galleni |
| PS3-93 | ABSTRACT-6bf1 | Preliminary risk analysis for a CECE-CD system at ICSI Rm. Valcea | Gheorghe Popescu |
| PS3-94 | ABSTRACT-6c4d | Radiation Data Analysis Tool (RaDAT) | Gianluca Borgese |
| PS3-95 | ABSTRACT-131d | Development of RELAP5/MOD3.3 for dynamic tritium transport analysis and its application to the COOL blanket | Wenjia Wang |
| PS3-96 | ABSTRACT-81f5 | Contamination assessments of DEMO WCLL breeding blanket primary heat transport system | Nicholas Terranova |
| PS3-97 | ABSTRACT-8a0f | Ex-vessel LOCA analysis for the EU-WCLL TBS using a fusion-adapted MELCOR model | Carmen Niculae |
| PS3-98 | ABSTRACT-9dbf | Neutron Activation Analysis of CNS-I Corrosion Products in Fusion Reactor | Jingyu Zhang |
| PS3-99 | ABSTRACT-ab2e | Preparation of activated carbon from biofibers for capture of tritium containing compounds | Liga Avotina |
| PS3-100 | ABSTRACT-ae68 | Investigation on dust resuspension under in-vessel loss of coolant accident of fusion reactor | Zhijie Qin |
| PS3-101 | ABSTRACT-af83 | Solid waste products of EU DEMO – focus on tungsten dust reprocessing | Jaroslav Stoklasa |
| PS3-102 | ABSTRACT-2fa7 | Prospects for Melt Refining of Radioactive Waste from Fusion Reactors | Paul Humrickhouse |
| PS3-103 | ABSTRACT-cb76 | Neutron Irradiation-Induced Shut-Down Dose Rate Estimation In EU DEMO Divertor | Simona Breidokaite |
PS3 - TOPIC H. Models and Experiments for FNT
| ORDER OF POSTER | ABSTRACT ID | TITLE | PRESENTER |
|---|---|---|---|
| PS3-104 | ABSTRACT-399b | Computational scheme for fast production of parametric stellarator models suitable for neutronic analysis | Javier Alguacil |
| PS3-105 | ABSTRACT-4c72 | Neutron Yield Semi-Monte Carlo Simulating Method for DT Fusion Neutron Source | Jieqiong Jiang |
| PS3-106 | ABSTRACT-5345 | Design of an Energy Transfer Storage System Based on EAST | Hongyan Wang |
| PS3-108 | ABSTRACT-d28e | Calculation of Neutralization Efficiency and Beam Transport for the Two Region Arc Plasma Negative Ion Source | Tae-Seong Kim |
| PS3-109 | ABSTRACT-c63f | HCPB TBS Tritium transport model at system level with EcosimPro® | Almudena Rueda |
| PS3-110 | ABSTRACT-6bff | Design of modular Hydrogen trap for the lithium purification system of IFMIF-DONES | Juan Diego Iberico |
| PS3-111 | ABSTRACT-75d4 | Sensitivity and uncertainty analyses of SAD and SED in the FNG HCPB Tritium Breeder Module benchmark | Bin Zhang |
| PS3-112 | ABSTRACT-7af8 | The Water cooled lithium lead thermal-HYDRAulic experimental platform | Alessandro Del Nevo |
| PS3-113 | ABSTRACT-7dda | 'Effects of multi-toroidal neon injections on the asymmetry of heat flux distribution with EMC3-EIRENE modelling | Shuyu Dai |
| PS3-114 | ABSTRACT-858e | Numerical and analytic solutions for liquid metal flows under non-uniform magnetic field gradients in a circular pipe | Antulio Tarazona |
| PS3-115 | ABSTRACT-88d1 | Visible cameras as a tool to study electron-beam shape | Margherita Ugoletti |
| PS3-116 | ABSTRACT-1ddd | Preparing for CHIMERA commissioning by virtual testing via systems simulations | Michelle Tindall |
| PS3-117 | ABSTRACT-8b32 | Verification and validation procedure for the tritium processing modelling libraries of EcosimPro | Carlos Moreno |
PS3 - TOPIC I. Repair and Maintenance
| ORDER OF POSTER | ABSTRACT ID | TITLE | PRESENTER |
|---|---|---|---|
| PS3-120 | ABSTRACT-4984 | A Conceptual Design of Automatic In-vessel Inspection Systems | Dohee Lee |
| PS3-121 | ABSTRACT-4b00 | Assessment of different lifting devices for the shipping bays for DONES main building | Yan Wang |
| PS3-122 | ABSTRACT-4dce | Manufacturing and Repair of ITER Blanket Panels: Exploring Joining Techniques for Beryllium Tiles and CuCrZr/Cu Joints | Bernaitz Arregi |
| PS3-123 | ABSTRACT-8d81 | Design and development of a flexible manipulator as test rig platform for robot flexible behaviors in remote handling operations | Stanislao Grazioso |
| PS3-126 | ABSTRACT-8017 | Assessment of architectural changes that benefit remote maintenance structural feasibility for Large Port-Based Tokamaks focusing on the study of the aspect ratio and the inboard blanket segmentation. | László Poszovecz |
| PS3-127 | ABSTRACT-86ce | RAMI analysis of ITER diagnostic Radial Neutron Camera | Danilo Nicola Dongiovanni |
PS3 - TOPIC J. Burning Plasma Control and Operation
| ORDER OF POSTER | ABSTRACT ID | TITLE | PRESENTER |
|---|---|---|---|
| PS3-128 | ABSTRACT-796a | Development of a real time spectroscopic neutron camera for feedback plasma control of a DT burning plasma | Agostino Celora |
| PS3-129 | ABSTRACT-79ee | Visible imaging system with changeable field of view on the HL-2A tokamak | Liang Liu |
| PS3-130 | ABSTRACT-8508 | Integrated Physics Analysis of the 100 MWe-class Compact Helical Fusion Reactor | Takuya Goto |
| PS3-132 | ABSTRACT-c651 | Special Plasma Control technologies with novel Results on EXL-50 | Xianming Song |
PS3 - TOPIC K. Inertial Confinement Fusion Studies and Technologies
| ORDER OF POSTER | ABSTRACT ID | TITLE | PRESENTER |
|---|---|---|---|
| PS3-133 | ABSTRACT-7b03 | Phase imaging of irradiated foils at the OMEGA EP facility using phase-stepping X-ray Talbot-Lau deflectometry | Gabriel Pérez-Callejo |
| PS3-135 | ABSTRACT-1e18 | Spectrally resolved emittance monitor for Laser-Plasma Ion Accelerators | Carlos Salgado López |
| PS3-136 | ABSTRACT-9d47 | Commissioning experiment on proton acceleration and characterization with the petawatt-femtosecond class Laser VEGA-3 at CLPU | M Dolores Rodríguez Frías |
| PS3-139 | ABSTRACT-e645 | Preliminary nuclear analysis of HYLIFE-3: a thick-liquid-wall chamber for inertial fusion energy | Francisco Ogando |
| PS3-140 | ABSTRACT-f734 | Characterization of hot spots generated in DT plasmas by fast quasi-monoenergetic ion beams: self-heating/igniton curves and burning gains | Juan Miguel Gil |
PS3 - TOPIC L. Fission-Fusion Synergy and Cross Cutting Technologies
| ORDER OF POSTER | ABSTRACT ID | TITLE | PRESENTER |
|---|---|---|---|
| PS3-143 | ABSTRACT-4f73 | TRISO fuel processing using a spherical tokamak based fusion neutron source | Martin Nieto-Perez |
| PS3-144 | ABSTRACT-6121 | IAEA activities on synergies in technology development between nuclear fission and fusion for energy production | Vladimir Artisiuk |
| PS3-145 | ABSTRACT-cc65 | Fusion for high-value heat production | Samuel Ward |
| PS3-146 | ABSTRACT-bddb | Applicability of neutron measurement techniques in fission reactors to breeding blankets of DEMO | Philippe Filliatre |
FRIDAY 15TH
PS4 - TOPIC A. Plasma-Facing High Heat Flux Components
| ORDER OF POSTER | ABSTRACT ID | TITLE | PRESENTER |
|---|---|---|---|
| PS4-1 | ABSTRACT-a573 | Thermal and structural analysis of JT-60SA Actively Cooled Divertor target submitted to high heat flux | Silvia Garitta |
| PS4-2 | ABSTRACT-a6b8 | Pre-conceptual design of the steering mirror for the DEMO Electron Cyclotron Heating system | Avelino Mas Sánchez |
| PS4-3 | ABSTRACT-a9b2 | Brazing alloys characterization for EU-DEMO Divertor Target | Emanuela Martelli |
| PS4-4 | ABSTRACT-ae29 | STEP Limiters – Manufacturing Trials of PFCs with Low Thermal Conductivity Features | James Roberts |
| PS4-5 | ABSTRACT-11f1 | Selection of EU-DEMO divertor operating condition: design space and power exhaust capabilities | Domenico Marzullo |
| PS4-7 | ABSTRACT-c6da | Design, manufacturing and commissioning of endoscopes for monitoring water-cooled divertor in W7-X | Joris Fellinger |
| PS4-8 | ABSTRACT-cd7c | Reflection Discrimination of Tungsten PFC with Full Ray Information | Seungtae Oh |
| PS4-9 | ABSTRACT-cfa4 | Electromagnetic analysis in support to the EU-DEMO Upper Limiter design | Ivan Alessio Maione |
| PS4-10 | ABSTRACT-9285 | Investigation of plasma plumes created during the exposition of a liquid tin filled-tungsten Capillary Porous System target at the OLMAT High Heat Flux facility | Alfonso De Castro Calles |
| PS4-11 | ABSTRACT-e717 | Thermal and structural analysis of the European Water-Cooled Lithium Lead breeding blanket concept in the L-H mode transition | Gaetano Bongiovi |
| PS4-12 | ABSTRACT-ea5c | Calibration and uncertainty quantification of a multi-physics model for in-vessel components design in a fusion power plant | Sebastian Rosini |
| PS4-13 | ABSTRACT-ebec | Concept Design of the STEP Outboard Build | Ethan Flynn |
| PS4-14 | ABSTRACT-ec33 | Design and Modeling of a Dissipative Divertor that Isolates the Target from the X-point in DIII-D | Jonathan Yu |
| PS4-17 | ABSTRACT-1c5c | Pre-conceptual design of the fixed mirrors for the DEMO Electron Cyclotron Heating antenna | Cinta Lucía Marraco Borderas |
PS4 - TOPIC B. Blanket Technology
| ORDER OF POSTER | ABSTRACT ID | TITLE | PRESENTER |
|---|---|---|---|
| PS4-19 | ABSTRACT-c2b7 | Blanket test facility for mockup testing on water cooled ceramic breeder blanket system | Takuya Katagiri |
| PS4-20 | ABSTRACT-c304 | Development and characterization of electrochemical hydrogen sensors using different fabrication techniques | Sergi Colominas |
| PS4-21 | ABSTRACT-0331 | Low pressure hydrogen isotope transport parameters in materials for tritium recycling systems. | Marta Malo |
| PS4-22 | ABSTRACT-c653 | Recent Progress of Fusion Nuclear Safety and Nuclear Materials at INEST, CAS | Jie Yu |
| PS4-24 | ABSTRACT-d089 | The high chemical compatibility with static PbLi of oxide ceramic candidates for the advance DCLL | Julián Patiño |
| PS4-25 | ABSTRACT-d0e7 | Procurement Status of ITER Blanket Shield Block in China | Kun Wang |
| PS4-27 | ABSTRACT-d5c9 | Introduction on Tritium Transport Analysis model for HCCP Breeding Blanket System | Yonghee Lee |
| PS4-29 | ABSTRACT-e269 | Validation of V, Si and Ni cross sections from trial versions of JEFF-4 ND library on fusion-relevant shielding benchmarks | Jan Malec |
| PS4-30 | ABSTRACT-e622 | Solubility of helium in liquid Pb-16Li | Michal Kordac |
| PS4-32 | ABSTRACT-e9c6 | Deuterium detection using electrochemical sensors | Jordi Abella |
| PS4-33 | ABSTRACT-ea55 | Study on Hot Isostatic Pressing conditions of ARAA for fabrication of the Korean breeding blanket first wall | Hyoseong Gwon |
| PS4-34 | ABSTRACT-f2dc | Impact of Nuclear Heating Distribution on the structural behavior of ITER FW Panel 11 | Eduardo Masia |
| PS4-35 | ABSTRACT-f7a5 | Electrical properties of ceramic coatings after heavy-ion irradiation and lithium implantation | Takumi Chikada |
| PS4-37 | ABSTRACT-f8d8 | A second-order partial diffusion equation model to compute the diffusion of hydrogen deuterium and tritium assisted by stress and strain fields | Jesús Toribio |
| PS4-38 | ABSTRACT-fa16 | Electrical conductivity of candidate ceramic materials for flow channel inserts | Jaroslav Kekrt |
| PS4-40 | ABSTRACT-fe7c | Simulation study of tritium diffusion in the liquid lithium lead eutectic alloy. | Luis E. Gonzalez |
PS4 - TOPIC C. Fuel Cycle and Tritium Processing
| ORDER OF POSTER | ABSTRACT ID | TITLE | PRESENTER |
|---|---|---|---|
| PS4-41 | ABSTRACT-b997 | Design and development of a hydrogen pellet centrifuge accelerator for the JT-60SA | Guillem Olivella |
| PS4-42 | ABSTRACT-be4e | Continuous tritium extraction from falling LiPb droplets in a vacuum | Fumito Okino |
| PS4-43 | ABSTRACT-c5b8 | Tritium Compatible Vacuum Pump Train for Plasma Exhaust | Yoshinao Matsunaga |
| PS4-44 | ABSTRACT-ce22 | Ammonia Palladium Membrane Reactor Development | Tyler Guin |
| PS4-46 | ABSTRACT-1c1e | Gas Raman: Detecting Gases within the Fuel Cycle | Jessica Gabb |
| PS4-47 | ABSTRACT-dc6e | Assessment of Metal Foil Pump Configurations for EU-DEMO | Xueli Luo |
| PS4-48 | ABSTRACT-df34 | Concept of the HCPB TER using non-evaporable getters for tritium recovery | George Ana |
| PS4-49 | ABSTRACT-e9a9 | The interaction between some candidate blanket materials with tritium and associated detritiation technologies for a magnetic confined fusion reactor | Changan Chen |
| PS4-51 | ABSTRACT-f9c7 | Organic vacuum pump fluids for the vacuum pumping of fusion power plants | George Larsen |
| PS4-52 | ABSTRACT-faec | Design Study on Fuel Buffer System for Continuous Processing of the Tritium Plant Considering Burn and Dwell Operation Scenarios | Jae-Uk Lee |
| PS4-53 | ABSTRACT-fcce | Alkali metal vapor diffusion pump for fusion reactor evacuation | Juro Yagi |
PS4 - TOPIC D. Material Engineering for FNT
| ORDER OF POSTER | ABSTRACT ID | TITLE | PRESENTER |
|---|---|---|---|
| PS4-56 | ABSTRACT-a347 | Research on the Low Cycle Fatigue Behaviors of Gradient Nano-Structured CLAM Steel | Shaojun Liu |
| PS4-57 | ABSTRACT-a3ce | Weld Technologies for Group V materials (V, Nb) | Igor Rueda |
| PS4-58 | ABSTRACT-aad9 | The effects of heat treatment process on mechanical properties of Bi-2212 Round Wires | Mengliang Zhou |
| PS4-59 | ABSTRACT-add9 | Effects of Size and Static Temperature Exposure on the Shear Strength of Tungsten Bonded CFC Blocks for Divertor in JT-60SA | Hirotatsu Kishimoto |
| PS4-60 | ABSTRACT-bca6 | Radiation safety study for the high-duty operation of the LIPAc RFQ in Rokkasho | Keitaro Kondo |
| PS4-61 | ABSTRACT-31a4 | Comparative study of preparation methods and properties of lead-lithium eutectic for fusion technology | Alberto J. Quejido-Cabezas |
| PS4-62 | ABSTRACT-c1b9 | The Impact of Nitrogen Pre-Implantation, the Crystal Orientation and the Recovery on the helium blisters growth mechanism in copper | Gabriel Zamir |
| PS4-63 | ABSTRACT-c2c9 | Influence of Thermal Aging on the Deuterium Retention and Permeation Behavior in the RAFM Steel | Wei Wang |
| PS4-64 | ABSTRACT-c4ac | Development of Advanced Ternary Beryllium Intermetallic Compounds | Taehyun Hwang |
| PS4-65 | ABSTRACT-dbe7 | A Material Production and Qualification Plan for lead-lithium eutectic nuclear grades | José Luis Herranz |
| PS4-66 | ABSTRACT-ea83 | Excellent mechanical property of W-Y2O3 alloy processed by Kocks rolling | Fan Feng |
| PS4-67 | ABSTRACT-ec41 | Effect of Ion Implantation on microstructure and critical current for YBCO superconductor | Haiying Fu |
| PS4-68 | ABSTRACT-f64d | Sputter yield of tungsten with strongly different microstructure | Till Höschen |
| PS4-68b | ABSTRACT-fae3 | Calculation of production of Mo-99 in the IFMIF-DONES facility | María Isabel Ortíz |
PS4 - TOPIC E. Vacuum Vessel and Ex-vessel Systems
| ORDER OF POSTER | ABSTRACT ID | TITLE | PRESENTER |
|---|---|---|---|
| PS4-69 | ABSTRACT-b0c8 | Final design of ex-vessel components for the Wide Angle Viewing System diagnostic for ITER Equatorial Port 12 | Carmen Pastor |
| PS4-70 | ABSTRACT-b659 | Cooling design and analysis of the EU DEMO EC Launcher port plug modules | Peter Spaeh |
| PS4-71 | ABSTRACT-c23e | Plasma disruptions in the design of DTT and strategies for their mitigation | Giuseppe Ramogida |
| PS4-72 | ABSTRACT-6f82 | Thermo-mechanical Analysis of the Components in the Launcher Transmission Line of ITER Ex-Port Plug Collective Thomson Scattering | Esther Rincón Rincón |
| PS4-73 | ABSTRACT-ee57 | Preparation for Korean procurement scope of ITER sealing flanges | Geunhong Kim |
| PS4-74 | ABSTRACT-f325 | First Experiences of the new Cryo Vacuum Pumps at Wendelstein 7-X during Hydrogen Operation | Torsten Braeuer |
| PS4-76 | ABSTRACT-af9a | Final design analysis of the Optical Hinge of the Wide Angle Viewing System for ITER Equatorial Port 12 | Santiago Cabrera |
PS4 - TOPIC F. Nuclear System Design
| ORDER OF POSTER | ABSTRACT ID | TITLE | PRESENTER |
|---|---|---|---|
| PS4-78 | ABSTRACT-aec8 | Fatigue analysis based on LEFM for a HTS CS coil of the next generation fusion reactor | Jiandong Zhu |
| PS4-79 | ABSTRACT-b302 | IFMIF DONES lithium pump design studies | Leonids Buligins |
| PS4-80 | ABSTRACT-b80b | TBM Piping Systems: Design according to RCC-MRx code | Stephane Gazzotti |
| PS4-81 | ABSTRACT-bafa | Conceptual Design Study of a Large Bore Superconducting Test Facility Magnet, SUCCEX | Keenam Kim |
| PS4-82 | ABSTRACT-c08f | Development of compact gyrotron for start-up scenario in KSTAR ECH system | Sunggug Kim |
| PS4-85 | ABSTRACT-2616 | Neutronics assessment of the radar diagnostic for the IFMIF-DONES lithium target | Fernando Mota |
| PS4-86 | ABSTRACT-d463 | Thermal and structural analysis of the DONES Target System under steady state and transient loading conditions | Ilenia Catanzaro |
| PS4-87 | ABSTRACT-d66c | Nuclear and sensitivity analyses in Equatorial Port Plug, Port Interspace and Port Cell #12 in ITER | Davide Flammini |
| PS4-88 | ABSTRACT-dc8d | Deterministic neutronics for stellarator system design | Timo Bogaarts |
| PS4-89 | ABSTRACT-eb05 | Manufacturing demonstration of a STEP inboard neutron shield | Sunchi Chen |
| PS4-90 | ABSTRACT-6f53 | Overview of European Fusion Neutron Source activities within the IFMIF/EVEDA Project | David Jimenez Rey |
| PS4-92 | ABSTRACT-f904 | An approach to improve the tension constancy of a TF coil shape | Xiaogang Liu |
PS4 - TOPIC G. Safety Issues and Waste Management
| ORDER OF POSTER | ABSTRACT ID | TITLE | PRESENTER |
|---|---|---|---|
| PS4-93 | ABSTRACT-cbf6 | Potential of radioactive isotopes production in DEMO for commercial use | Pereslavtsev Pavel |
| PS4-94 | ABSTRACT-ce81 | ACABLoop simulation tool: improving the activation prediction of flowing PbLi alloy in support of DEMO fusion reactor design | Mauricio Garcia |
| PS4-95 | ABSTRACT-d8db | The LiFIRE experimental facility: final design, construction and experimental campaign | Gianluca D'Ovidio |
| PS4-96 | ABSTRACT-4b32 | Safety Issues of Lithium-Water Reaction for Fusion Reactor | Danna Zhou |
| PS4-97 | ABSTRACT-dfae | Simulation of tritium trapping on impurities in beryllium | Pavel Vladimirov |
| PS4-99 | ABSTRACT-ef14 | Improving the efficiency of MELCOR modelling for accident analysis of a tokamak | J.J. Nebrensky |
| PS4-100 | ABSTRACT-f3e6 | Assessment of radiation dose rate in main building area of A-FNS facility | Saerom Kwon |
| PS4-101 | ABSTRACT-f63b | Instantaneous Risk Monitoring Method for Fusion Reactors based on Level Three Probabilistic Safety Assessment | Shanqi Chen |
| PS4-102 | ABSTRACT-fd13 | Assessment of air activation discharge from JET during DT operations | Steven Bradnam |
PS4 - TOPIC H. Models and Experiments for FNT
| ORDER OF POSTER | ABSTRACT ID | TITLE | PRESENTER |
|---|---|---|---|
| PS4-103 | ABSTRACT-97b4 | Methods for characterization of voids and bubbles in tungsten using S/TEM | Witold Chrominski |
| PS4-104 | ABSTRACT-9ca5 | Optimizing Plasma Parameters for High Negative Ion Density in a Two-Region Arc Plasma ion source | Kihyun Lee |
| PS4-106 | ABSTRACT-a564 | Current Status and Plan of Fusion Material and Blanket R&Ds using Various Ion and Neutron Irradiation Facilities at KAERI | Dong Won Lee |
| PS4-107 | ABSTRACT-8922 | IFMIF-DONES radiofrequency conditioning | David Regidor |
| PS4-108 | ABSTRACT-c1c8 | Assessment of a millimeter-wave radar system for real-time diagnosis of the IFMIF-DONES lithium target | Cristina De La Morena |
| PS4-109 | ABSTRACT-650c | LITEC: an experimental facility for the validation of the IFMIF-DONES Impurity Control System | Belit Garcinuño |
| PS4-110 | ABSTRACT-c921 | Neutronic analyses for EU DEMO upper limiter | Aljaz Cufar |
| PS4-111 | ABSTRACT-ca86 | Design and Testing of Windowless Gas Target for High Intensity Neutron Sources | Tao Zhou |
| PS4-112 | ABSTRACT-cfd8 | Experiments for testing the H-trap and proposal of experiments in LITEC. | María Sánchez Arenillas |
| PS4-113 | ABSTRACT-5e37 | Towards an improved version of Fluorescence Profile Monitor for IFMIF-DONES | Víctor Villamayor |
| PS4-114 | ABSTRACT-d25b | Gas flow modelling of the IFMIF-DONES beamline | Volker Hauer |
| PS4-115 | ABSTRACT-d368 | Validation of Modular Cryogenics code (ModCryo) developed for lab-size test cryostats | Erik Walcz |
| PS4-116 | ABSTRACT-f3c8 | Vacuum Thermal Contact Conductance determination between CucrZr and TZM electrodes coated by alumina and copper | Santiago Dominguez Meister |
| PS4-119 | ABSTRACT-f682 | Electromagnetic computer codes validation for ITER related analyses. | Pietro Testoni |
PS4 - TOPIC I. Repair and Maintenance
| ORDER OF POSTER | ABSTRACT ID | TITLE | PRESENTER |
|---|---|---|---|
| PS4-120 | ABSTRACT-623b | Logistics and maintenance applied to building plant system of IFMIF DONES | Enrique Poveda Martinez |
| PS4-121 | ABSTRACT-9bba | The Remote Handling maintenance in IFMIF-DONES Project: status of the activities and future development program | Gioacchino Miccichè |
| PS4-123 | ABSTRACT-c850 | Kinematics analysis of a novel hybrid manipulator for optomechanical modules assembly in SG-Ⅲ | Xiaoyong Wu |
| PS4-124 | ABSTRACT-ced0 | Data Driven Modeling of Heavy-duty Joint System for DEMO Manipulators | Ming Li |
| PS4-125 | ABSTRACT-3717 | Alignment strategy for IFMIF-DONES facility | Fernando Arranz |
| PS4-126 | ABSTRACT-db02 | Development of Lower Manipulator System for Breeding Blanket Maintenance within Large Port-Based Tokamaks | Marcell Malics |
| PS4-128 | ABSTRACT-e992 | Assessment and recovery from the damage of SPIDER RF driver Faraday shield lateral wall | Alessandro La Rosa |
PS4 - TOPIC J. Burning Plasma Control and Operation
| ORDER OF POSTER | ABSTRACT ID | TITLE | PRESENTER |
|---|---|---|---|
| PS4-129 | ABSTRACT-c6b6 | Bismuth Hall sensors for magnetic measurements in the HL-2A/2M tokamak | Ao Wang |
| PS4-130 | ABSTRACT-dc58 | Design and operation results of KSTAR 105/140GHz ECH system | Mi Joung |
| PS4-133 | ABSTRACT-f3f9 | Time series methods for the control of fusion plasma instabilities and disruption prediction | Teddy Craciunescu |
PS4 - TOPIC L. Fission-Fusion Synergy and Cross Cutting Technologies
| ORDER OF POSTER | ABSTRACT ID | TITLE | PRESENTER |
|---|---|---|---|
| PS4-134 | ABSTRACT-7d26 | Tokamaks as convenient neutron sources for nuclear materials testing | Massimo Zucchetti |
| PS4-135 | ABSTRACT-b250 | Numerical Prediction of the Physical Properties of Beryllium and Long-Lived Fission Products Fluoride Mixtures for Transmutation Using Fusion Neutrons Sources | Hiroki Shishido |
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