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October 27 – November 1, 2019
La Jolla, California, U.S.A.
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Welcome to ICFRM‐19 ICFRM is the premier international forum connecting specialists in the area of development of materials for both near and longer‐term fusion energy systems. A central theme is+ the sharing of new insights, cutting‐edge research, and technology in materials science pertaining to the realization of fusion energy. The conference consists of daily overview plenary lectures, invited and contributed oral presentations, and a series of technical poster sessions. In addition to hosted satellite meetings, pre‐conference technical tutorials, and stimulating discussions. We would like to welcome you to the 19th International Conference on Fusion Reactor Materials (ICFRM‐19), which is held in La Jolla, California, U.S.A. during the period October 27 through November 1, 2019. We wish you a pleasant experience, full of great technical discussions and interactions, and a wonderful social and friendly atmosphere.
Nasr Ghoniem Conference Chair
Hosted by the University of California, Los Angeles Assisted by Pacific Northwest National Laboratory
With participation by: UTK, ORNL, SBU, UCSB, UCSD, GA
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Contents Venue & Layout ........................................................................................................................................................................................... 4
Topics .......................................................................................................................................................................................................... 6
Organization ................................................................................................................................................................................................ 7
International Advisory Committee ............................................................................................................................................................. 8
Tutorials .................................................................................................................................................................................................... 10
General Information ................................................................................................................................................................................. 11
Speaker Information ................................................................................................................................................................................. 13
Program Overview .................................................................................................................................................................................... 14
Oral Presentations .................................................................................................................................................................................... 15
Keynote & Plenary Speakers ..................................................................................................................................................................... 32
Poster Presentations ................................................................................................................................................................................. 39
Poster Layout ............................................................................................................................................................................................ 40
List of Poster Presentations ...................................................................................................................................................................... 42
Hotel Layout .............................................................................................................................................................................................. 73
Satellite Meetings ..................................................................................................................................................................................... 79
Technical Tours ......................................................................................................................................................................................... 81
Sponsors & Partners ................................................................................................................................................................................. 82
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Venue & Layout
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All subjects on materials for current near‐term fusion devices and advanced power systems are appropriate for this conference, including but not limited to: 1. Advanced materials development and qualification, including fabrication and joining methods
2. Divertor and plasma facing applications 3. Fusion‐specific applications of materials, including environmental effects 4. Materials engineering and testing in ITER, neutron sources, accelerators, and other test systems
5. The materials design interface, codes, and standards 6. Modeling, theory, and fundamental studies of radiation effects, including advanced characterization methods
7. Cross cutting issues and synergisms with other materials applications
Topics
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Nasr Ghoniem, UCLA, General Chair Rick Kurtz, PNNL, Co‐Chair
INTERNATIONAL ADVISORY COMMITTEE Brian Wirth, UTK TECHNICAL PROGRAM Chuck Henager, PNNL Jaime Marian, UCLA PUBLICATIONS Steve Zinkle, UTK PUBLICITY Lauren Garrison, ORNL SATELLITE MEETINGS & WORKSHOPS Lance Snead, Stony Brook University FUND RAISING Wahyu Setyawan, PNNL CONFERENCE ADMINISTRATION Dylan Dickstein, UCLA LOGISTICAL COORDINATION Alicia Moore, PNNL
Organization
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International Advisory Committee
Europe Maria Jose Caturla Jean Henry Angel Ibarra Christian Linsmeier Kai Nordlund Gerald Pintsuk Michael Rieth
University of Alicante, Spain CEA, France CIEMAT, Spain Forschungzentrum Juelich, Germany University of Helsinki, Finland Forschungzentrum Juelich, Germany Karlsruhe Institute of Technology, Germany
[email protected] [email protected] [email protected] [email protected] [email protected] [email protected] [email protected]
Japan Akira Hasegawa Yuji Hatano Ryuta Kasada Takeo Muroga Hiroyasu Tanigawa Takayuki Terai Yoshio Ueda
Tohoku University University of Toyama Tohoku University NIFS QST University of Tokyo Osaka University
[email protected] [email protected] [email protected] [email protected] [email protected] [email protected] [email protected]
United States Nasr Ghoniem Chuck Henager Yutai Katoh Jaime Marian Lance Snead Brian Wirth (IAC Chair) Steve Zinkle
University of California, Los Angeles Pacific Northwest National Laboratory Oak Ridge National Laboratory University of California, Los Angeles Stony Brook University University of Tennessee, Knoxville University of Tennessee, Knoxville
[email protected] [email protected] [email protected] [email protected] [email protected] [email protected] [email protected]
China Jinmeng Chen Changchun Ge Guan-Nan Luo Yican Wu
Southwest Institute of Physics University of Science and Technology, Beijing Institute of Plasma Physics, Chinese Academy oSciences Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences
[email protected] [email protected] [email protected] [email protected]
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Wen Yang
China Institute of Atomic Energy, CNNC
Russia Viacheslav Chernov Boris Kuteev
Bochvar Institute, Moscow Kurchatov Institute, Moscow
[email protected] [email protected]
Korea Yi-Hyun Park Young Bum Chun
National Fusion Research Institute, Daejeon Korea Atomic Energy Research Institute, Daejeo
[email protected] [email protected]
India Paritosh Chaudhuri Institute for Plasma Research, Bhat, Ganhinagar [email protected]
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A very strong and comprehensive tutorial program is planned for Sunday, October 27, 2019. These valuable tutorials will be free of charge, and are open to all registered conference attendees. They will cover all aspects of fundamental and applied research on fusion reactor materials from a pedagogical perspective. The tutorials are taught by 9 world experts on the fundamental materials science of fusion materials, advanced methods of material characterization, and putting it all together in the “Materials‐Design” applied area. Details are provided on the website.
1. Multiscale Modeling a. Scope Multiscale Modeling b. Lecturers
1. Dr. Sergei Dudarev Dudarev 2. Professor Jaime Marian Marian 3. Professor Giacomo Po Po
2. Materials‐Design Integration a. Scope Materials‐Design Integration b. Lecturers
1. Dr. Eberhard Diegele Diegele 2. Dr. Hiroyasu Tanigawa Tanigawa
3. Advanced Materials Characterization a. Scope Advanced Materials Characterization b. Lecturers
1. Professor Sosuke Kondo Kondo 2. Dr. Chad M. Parish Parish 3. Professor David Sprouster Sprouster 4. Dr. Philip D Edmondson Edmondson
Tutorials
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Registration The registration desk is located in the Grand Foyer area. On‐site registration will be available with credit card payments. The desk will be open on Sunday, October 27th, 2019 (4‐7 PM). It will be also open every morning from 8:00‐9:00 AM. Logistical assistance will be available at the registration desk Monday October 28th, 2019 – Friday November 1st , 2019 from 9:00 AM‐ 4:00 PM. Best Poster Award A committee will select the best poster from each poster session for an award to be given at the Conference Banquet. Best Student Paper Award A committee will select the best student paper for an award to be given at the Conference Banquet. WiFi Service
o Attendees can connect to complimentary Wi‐Fi in open areas including: Barcino Restaurant Lobby Area Drift Restaurant Pool Area If attendees are close to these areas, they can connect to the @Hyatt_WiFi Network
General Information
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Lunches A variety of restaurants are available for lunch (on your own). In addition to the hotel restaurents, guests are encouraged to explore restaurants at the Westfield UTC Mall (https://www.westfield.com/utc/entertainment/dining), and Costa Verde Center (http://costaverdecenter.com/). The Westfield UTC Mall is easily accessible by uber or taxi ( a few minutes). The Costa Verde Center is within 10 min walking distance. Publication of Conference Proceedings All contact authors for keynote/plenary, invited parallel session, and contributed oral presentations, along with “best poster” and “best student presentation” award winners will be requested to submit a regular length article to the Journal of Nuclear Materials (JNM) for normal peer review. Successful papers from ICFRM‐19 will be published in JNM immediately upon completion of peer review, and all the published papers will be electronically grouped together as a “virtual special issue” that will be available to all registrants of ICFRM‐19. There would be no cost applied for publishing in JNM, unless the authors wish to publish open access (in which case standard open access publishing fees would apply). The Elsevier publisher has indicated they can work out a way to offer the delegates of the conference access to these papers once they’re published, without a fee, if they don’t have a subscription through their institution. Dates and timeline: October 27, 2019‐February 1, 2010 Manuscript submission window. Each manuscript will be immediately available in electronic format after successful conclusion of the normal JNM peer review and proof processing. It is anticipated that the review and revision of all manuscripts will be completed before August 1, 2020, and that the full special issue will be available online on or before October 1, 2020.
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All oral presentations (Keynote, Plenary, and Oral) are given in the Aventine Ballroom on the
lower level of the hotel (see hotel layout).
The Aventine Ballroom will be reconfigured for three parallel oral sessions promptly after the last speaker in the morning Plenary/ Keynote session at 10:30 AM. Please join the coffee break at 10:30 AM sharp to allow time for the Aventine Ballroom reconfiguration.
All speakers must bring their presentation on a USB flash drive in power point or pdf format, to be uploaded on conference computers at least 30 minutes in advance of the session.
Session chairs: please assist in making sure that technicians upload all presentations ahead of
each oral session.
Conference projectors will be wide screen. Please make sure that your presentation is formatted for wide screen (16:9), or else you will lose side space on your slides if you have standard format (4:3).
Speaker Information
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Program Overview
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Oral Presentations
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Opening Session: MONDAY, October 28, 2019 9:00‐10:30 Chair: N. Ghoniem Session Presenter Title Time
OPENING SESSION
K1 Dr. Greg deTemmerman ITER Organization
ON THE LIFETIME AND OPERATIONAL LIMITS OF TUNGSTEN AS PLASMA‐FACING MATERIAL IN ITER 9:10 ‐9:50
P1 T. Schwarz‐Selinger IPP Garching
TRANSPORT AND RETENTION OF HYDROGEN AND HELIUM IN TUNGSTEN 9:50‐10:30
Monday Morning: 3 Parallel Oral Sessions
RAFM‐1: Monday Morning, October 28, 2019 11:00‐13:00 Chair: L. Tan Session Presenter Title Time
RAFM–1
I1 K. Field (ORNL) (1a7)
STRUCTURE‐PROPERTY RELATIONSHIPS FOR 12‐18%Cr ODS AND 9% Cr RAFM STEELS IRRADIATED TO HIGH DOSE (> 40 DPA) AT FUSION RELEVANT TEMPERATURES 11:00‐11:30
I2 H. Tanigawa (QST) (1a24)
NEW INSIGHTS ON THE HARDENING MECHANISMS IN IRRADIATED RAFM STEELS 11:30‐12:00
C1 W. Krauss (KIT) (7b1)
COMPATIBILITY OF RAFM STEELS WITH FLOWING PB‐LI EXAMINED IN THE CORROSION TESTING LOOP PICOLO DURING THE LAST DECADES 12:00‐12:20
C2 T. Graening (KIT) (1a28)
IMPACT OF THE CHEMICAL COMPOSITION OF THREE EUROFER97 STEEL VARIANTS ON THE MICROSTRUCTURE BEFORE AND AFTER NEUTRON IRRADIATION 12:20‐12:40
C3 M. Ando (QST) (1a33)
THE μ‐TENSILE DEFORMATION BEHAVIOR OF SINGLE BLOCK STRUCTURE OF F82H IRRADIATED AT 573K 12:40‐1:00
PFM‐1: Monday Morning, October 28, 2019 11:00‐13:00 Chair: A. Hasegawa
Session Presenter Title Time
PFM–1
I1 J.W. Coenen (FZJ) (2a56)
MATERIALS R&D FOR A 2ND ITER DIVERTOR AND BEYOND: AN OVERVIEW OF AVAILABLE CONCEPTS AND NEW MATERIAL CLASSES 11:00‐11:30
I2 X. Liu (SWIP) (2a28)
PROGRESS OF ADVANCED TUNGSTEN BASE MATERIALS DEVELOPED FOR FUSION APPLICATIONS IN CHINA 11:30‐12:00
C1 L. Snead
(Stonybrook) (2b26)
KINETICS OF PROCESSING ADVANCED COPPER ALLOYS FOR GRADED HHF STRUCTURES 12:00‐12:20
C2 Q. Li (IPP) (2b24) DESIGN AND MANUFACTURING OF FLAT‐TYPE W/CU MOCKUP WITH NOVEL HYPERVAPOTRON COOLING STRUCTURE FOR CFETR DIVERTOR 12:20‐12:40
C3 M. Tokitani (NIFS) (1f7)
NOVEL FABRICATION METHOD FOR HIGH HEAT FLUX COMPONENT BY THE MULTI‐STEP BRAZING TECHNIQUE 12:40‐1:00
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CERAMICS: Monday Morning, October 28, 2019 11:00‐13:00 Chair: R. Kasada Session Presenter Title Time
CERAMICS
I1 A. Bhattacharya (ORNL) (1c1)
IRRADIATION EFFECTS AND ADVANCED CHARACTERIZATION OF NEUTRON AND ION IRRADIATED TITANIUM DIBORIDE 11:00‐11:30
I2 T. Koyanagi (ORNL) (1c11)
DESIGN AND STRATEGY FOR NEXT GENERATION SILICON CARBIDE COMPOSITES FOR FUSION ENERGY 11:30‐12:00
C1 M. Ferraris (Torino) (1c2)
IRRADIATION STABILITY OF SIC‐BASED JOINTS FOR NUCLEAR FUSION APPLICATIONS 12:00‐12:20
C2 T. Nozawa (QST) (1c5)
FAILURE EVALUATION OF NEUTRON‐IRRADIATED SiC/SiC COMPOSITES BY UNDERWATER ACOUSTIC EMISSION 12:20‐12:40
C3 T. Nishitani (NIFS) (1c4)
RECENT ACTIVITIES OF IRRADIATION EFFECTS ON DIAGNOSTICS COMPONENTS UNDER THE IEA FUSION MATERIAL COLLABORATION AGREEMENT 12:40‐1:00
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Monday Afternoon: 3 Parallel Oral Sessions RAFM‐2: Monday Afternoon, October 28, 2019 14:30AM‐16:30PM Chair: H. Tanigawa
Session Presenter Title Time
RAFM–2
I1 Q. Huang (INEST) (1a6)
DEVELOPMENT AND STRATEGY ON CLAM STEEL FOR ITS ENGINEERING APPLICATION 14:30‐15:00
I2 L. Tan (ORNL) (1a27) DEVELOPMENT OF CASTABLE NANOSTRUCTURED ALLOYS AS U.S. REDUCED‐ACTIVATION FERRITIC‐MARTENSITIC STEEL 15:00‐15:30
C1 B. Huang (INEST) (3a1)
JOINING QUALIFICATION AND ADVANCED FABRICATION TECHNIQUE DEVELOPMENT ON FUSION REACTOR BLANKET IN CHINA 15:30‐15:50
C2 Y.B. Chun (KAERI) (1a3)
ENHANCED MECHANICAL PROPERTIES OF ARAA BY TYPE IIIa THERMO‐MECHANICAL TREATMENTS 15:50‐16:10
C3 S. Bonk (KIT) (1a34) ADDITIVE MANUFACTURING TECHNOLOGIES FOR EUROFER COMPONENTS 16:10‐16:30
PFM‐2: Monday Afternoon, October 28, 2019 14:30AM‐16:30PM Chair: S. Dudarev Session Presenter Title Time
PFM–2
I1 S. Brezinsek (FZJ) (2a23)
PLASMA‐SURFACE INTERACTION IN THE STELLARATOR W7‐X OPERATING WITH INERTIALLY COOLED GRAPHITE PLASMA‐FACING COMPONENTS 14:30‐15:00
I2 A. Hasegawa (Tohoku Univ.) (5d9)
HELIUM EFFECTS ON RECOVERY AND RECRYSTALLIZATION BEHAVIOR AND TENSILE PROPERTIES OF POWDER‐METALLURGICAL PROCESSED TUNGSTEN 15:00‐15:30
C1 M. Shimada (INL) (2a29)
SURFACE ANALYSIS OF SHIELDED AND UNSHIELDED NEUTRON‐IRRADIATED POLYCRYSTALLINE TUNGSTEN BY SCANNING AUGER MICROSCOPE 15:30‐15:50
C2 N. Zimber (KIT) (5d31)
INVESTIGATION OF HIGH‐DOSE IRRADIATED BERYLLIUM MICROSTRUCTURE INCLUDING STEM‐EELS ANALYSIS OF HELIUM/TRITIUM‐BUBBLES 15:50‐16:10
C3 T. Wada (Shizuoka Univ.) (2a18)
INFLUENCE OF DAMAGE DEPTH DISTRIBUTION FORMED BY HYDROGEN ION ON THE DEUTERIUM RETENTION BEHAVIOR IN TUNGSTEN 16:10‐16:30
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FUTURE ALLOYS: Monday Afternoon, October 28, 2019 14:30AM‐16:30PM Chair: A. Bhattacharya Session Presenter Title Time
FUTURE ‐ 1
I1 M. Satou (HIT) (1e2) INFLUENCE OF ALLOYING ELEMENTS ON STABILITY OF MICROSTRUCTURE AFTER NEUTRON IRRADIATION OF VANADIUM ALLOYS 14:30‐15:00
I2 R. Kasada (Tohoku Univ.) (2b18)
JAPANESE R&D ON ODS‐CU FOR DIVERTOR APPLICATION 15:00‐15:30
C1 S. Jiang (SAS) (1e4) DISSIMILAR‐METALS BONDING BETWEEN A LOW‐ACTIVATION VANADIUM ALLOY AND HASTELLOY X ALLOY BY EXPLOSIVE WELDING 15:30‐15:50
C2 S. Sakurai (Taiyokoko Co.) (1e6)
EFFECT OF CR AND TI CONCENTRATION ON MECHANICAL PROPERTIES OF LOW‐ACTIVATION VANADIUM ALLOYS FOR NUCLEAR FUSION REACTOR 15:50‐16:10
C3 Y. Yang (ORNL) (1f3) TENSILE AND THERMAL CREEP BEHAVIOR OF A NOVEL COPPER ALLOY FOR FUSION ENERGY APPLICATIONS 16:10‐16:30
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TUESDAY, October 29, 2019 Plenary Session1
8:30‐10:30 Chair: R. Kurtz Session Presenter Title Time
PLEN–1
P2 C. Zhang Tsinghua University
DESIGN AND DEVELOPMENT OF NEW STRUCTURAL MATERIALS FOR FUSION REACTORS 8:30‐9:10
P3 S. Dudarev UKAEA Culham
RECENT PROGRESS IN RESEARCH IN MODELLING FUSION REACTOR MATERIALS IN EUROPE: THE IREMEV COLLABORATION 9:10‐9:50
P4 J. Chen SWIP
MATERIAL CHALLENGES FOR CFETR AND R&D STRATEGIES 9:50‐10:30
Tuesday Morning
3 Parallel Oral Sessions ODS‐1: Tuesday Morning, October 29, 2019: 11:00‐13:00 Chair: Y. de Carlan
Session Presenter Title Time
ODS–1
I1 N. Oono‐Hori (Hokkaido Univ.) (1b30)
STABILITY OF OXIDE PARTICLES IN ODS STEELS UNDER IRRADIATION 11:00‐11:30
I2 S. Dryepondt (ORNL) (1b1)
LONG‐TERM CREEP RESISTANT ODS FeCrAlZr ALLOYS WITH IMPROVED Pb‐Li COMPATIBILITY 11:30‐12:00
C1 N. Ordás (CEIT) (1b18) EFFECT OF HOT ROLLING PARAMETERS ON THE MICROSTRUCTURE AND MECHANICAL PROPERTIES OF ODS FERRITIC STEELS PRODUCED WITH THE STARS ROUTE
12:00‐12:20
C2 L. Song (INEST) (1b5) A Y‐SI‐O STRENGTHENED 9CR ODS STEEL DESIGNED FOR HIGH TEMPERATURE APPLICATION IN ADVANCED NUCLEAR REACTOR 12:20‐12:40
C3 Y. Shi (Northeastern Univ.) (1b38)
MICROSTRUCTURE AND MECHANICAL PROPERTIES OF 9CR‐ODS ALLOYS PRODUCED BY LASER ADDITIVE MANUFACTURING 12:40‐1:00
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PFM–3: Tuesday Morning, October 29, 2019: 11:00‐13:00 Chair: F. Gao Session Presenter Title Time
PFM ‐ 3
I1 A. Hollingsworth (UKAEA Culham) (5d14)
EXPERIMENTAL AND THEORETICAL STUDY OF HYDROGEN ISOTOPES RETENTION AND RELEASE FROM IRRADIATED FUSION REACTOR MATERIALS 11:00‐11:30
I2 Y. Hatano (Univ. Toyama) (7a11)
ISOTOPE EFFECTS ON HYDROGEN RETENTION, TRAPPING AND PERMEATION IN COPPER‐BASED MATERIALS 11:30‐12:00
C1 A. Kreter (FZJ) (2a47) ENHANCED FUEL RETENTION IN TUNGSTEN PROVOKED BY NITROGEN AS SEEDED SPECIES 12:00‐12:20
C2 E. Bernard (CEA) (5d23) IMPACT OF W FUZZ ON TRITIUM TRAPPING AND DESORPTION 12:20‐12:40
C3 S. Nakazawa (Shizuoka Univ.) (7c7)
GAMMA‐RAY IRRADIATION EFFECT ON DEUTERIUM RETENTION IN REDUCED ACTIVATION FERRITIC/MARTENSITIC STEEL AND CERAMIC COATINGS
12:40‐1:00
IRRADIATION FACILITIES: Tuesday Morning, October 29, 2019: 11:00‐13:00 Chair: C. Parish Session Presenter Title Time
FACILITIES
I1 T. Muroga (NIFS) (3c3) USERS' PERSPECTIVE ON D‐Li NEUTRON SOURCES (A‐FNS and IFMIF‐DONES) FOR DEMO AND BEYOND 11:00‐11:30
I2 A. Ibarra (CIEMAT) (3c1) IFMIF‐DONES PROJECT: STATUS AND NEAR FUTURE 11:30‐12:00
C1 W. Leysen (SCK‐CEN) (3c10)
FUSION MATERIAL IRRADIATION STATION ON MYRRHA FACILITY: BASELINE CONCEPT 12:00‐12:20
C2 Y. Wu (INEST) (3c5) NEUTRONICS EXPERIMENTS FOR ADVANCED NUCLEAR SYSTEMS AT HINEG FACILITY 12:20‐12:40
C3 A. Kasugai (QST) (3c2) PROGRESS OF CONCEPTUAL DESIGN OF ADVANCED FUSION NEUTRON SOURCE A‐FNS 12:40‐1:00
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Tuesday Afternoon: 3 Parallel Oral Sessions ODS–2: Tuesday Afternoon, October 29, 2019: 14:30AM‐16:30PM Chair: TBD
Session Presenter Title Time
ODS ‐ 2
I1 J. Henry (CEA) (1b24) EUROPEAN DEVELOPMENT OF ADVANCED RAFM STEELS AND ODS ALLOYS FOR DEMO 14:30‐15:00
I2 H. Abe (Univ. Tokyo) (1b6)
ON THE STABILITY OF OXIDE/CARBIDE NM‐SCALE PARTICLES IN ODS AND F82H STEELS UNDER IRRADIATION; A REVIEW OF IN‐SITU OBSERVATION STUDIES IN HVEM
15:00‐15:30
C1 K. Kruska (PNNL) (1b31) STABILITY OF OXIDE PARTICLES IN 14YWT EXPOSED TO NEUTRON IRRADIATION AT 500˚C 15:30‐15:50
C2 H. Kim (TAMU) (1b9) MICROSTRUCTURAL EVOLUTION IN HELIUM PRE‐IMPLANTED DUAL‐PHASE 12CR OXIDE DISPERSION STRENGTHENED ALLOY DURING SELF‐ION IRRADIATION TO 100 DPA
15:50‐16:10
C3 Y. Yano (JAEA) (1b32) MICROSTRUCTURAL STABILITY OF ODS STEEL AFTER LONG‐TIME CREEP TEST 16:10‐16:30
PFM–4: Tuesday Afternoon, October 29, 2019: 14:30AM‐16:30PM Chair: A. Hollingsworth Session Presenter Title Time
PFM ‐ 4
I1 H. Greuner (MP‐IPP) (2b9) INVESTIGATION OF THE THERMAL PERFORMANCE OF NEWLY DEVELOPED EUROPEAN DEMO DIVERTOR TARGET CONCEPTS 14:30‐15:00
I2 A. Shoshin (Novosibirsk Univ.) (2a58)
IN SITU STUDY OF THE PROCESSES OF DAMAGE TO THE TUNGSTEN SURFACE UNDER TRANSIENT HEAT LOADS POSSIBLE IN ITER 15:00‐15:30
C1 E. Gaganidze (KIT) (2b13) EUROPEAN TUNGSTEN MATERIAL PROPERTY HANDBOOK 15:30‐15:50
C2 M. Wirtz (FZJ) (2a59) LASER AND ELECTRON BEAM EXPERIMENTS TO QUANTIFY THE THERMAL SHOCK BEHAVIOR OF TUNGSTEN 15:50‐16:10
C3 M. Fukuda (QST) (2b8) INFLUENCE OF CYCLIC HEAT LOAD ON PURE TUNGSTEN FOR ITER DIVERTOR 16:10‐16:30
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Advanced Characterization: Tuesday Afternoon, October 29, 2019: 14:30AM‐16:30PM Chair: A. Ibarra Session Presenter Title Time
Advanced Charact.
I1 M. J. Lloyd (Oxford) (5b32)
NANOSCALE CHARACTERISATION OF RE/OS PRECIPITATION IN NEUTRON IRRADIATED TUNGSTEN 14:30‐15:00
I2 C. Parish (ORNL) (5e12) HIGH‐THROUGHPUT PHASE‐CHEMISTRY MAPPING OF NANO‐PRECIPITATES IN RAFM STEELS BY TRANSMISSION KIKUCHI DIFFRACTION AND ANALYTICAL ELECTRON MICROSCOPY
15:00‐15:30
C1 Y. Zhu (Univ. Conn.) (5e14)
ACCELERATING THE UNDERSTANDING OF RADIATION EFFECTS VIA A NEW END‐TO‐END DEFECT QUANTIFICATION WORKFLOW 15:30‐15:50
C2 P. Warnicke (PSI) (5e18) EXTENDED X‐RAY ABSORPTION FINE STRUCTURE ANALYSIS OF TRANSMUTATION INDUCED RE LATTICE DEFECTS IN IRRADIATED W 15:50‐16:10
C3 W. A. Garcia (UTK) (5e7) DEPTH DEPENDENT HELIUM AND HYDROGEN CONCENTRATIONS IN MATERIALS MEASURED BY LASER INDUCED BREAKDOWN SPECTROSCOPY AND LASER ABLATION MASS SPECTROMETRY
16:10‐16:30
WEDNESDAY, October 30, 2019
Plenary Session2 8:30‐10:30 Chair: C. Henager
Session Presenter Title Time
PLEN–2
K2 Prof. Michael E. Mauel Dept of Applied Physics, Columbia University
NATIONAL ACADEMY OF SCIENCE FUSION STUDY REPORT 9:10 – 9:50
P5 G.R. Odette UCSB
CURRENT STATUS OF ODS ALLOYS 9:10‐9:50
P6 M. Nakamichi QST
CURRENT STATE AND STABLY SECURING OF BERYLLIUM RESOURCE FOR FUSION BLANKETS 9:50‐10:30
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Wednesday Morning 3 Parallel Oral Sessions
PFM‐5: Wednesday Morning, October 30, 2019: 11:00‐13:00 Chair: M. Sokolov Session Presenter Title Time
PFM–5
I1 Y. Oya (Shizuoka Univ.) (7a8)
OVERVIEW OF PHENIX TASK 3 ACTIVITIES FOR TRITIUM BEHAVIOR IN HIGH‐TEMPERATURE NEUTRON‐IRRADIATED TUNGSTEN 11:00‐11:30
I2 L. Garrison (ORNL) (2b1)
MICROSTRUCTURAL CHANGES IN PLASMA‐ARC LAMP HIGH HEAT FLUX EXPOSED NEUTRON IRRADIATED TUNGSTEN 11:30‐12:00
C1 Y. Sugimoto (Shimane Univ.) (2a65)
DEUTERIUM AND HELIUM DESORPTION BEHAVIOR AND MICROSTRUCTURE EVOLUTION IN BERYLLIUM DURING ANNEALING 12:00‐12:20
C2 E. Lang (UIUC) (2a48) UNRAVELLING THE EFFECTS OF SECOND PHASE PARTICLES ON THE MORPHOLOGY, RETENTION, AND MECHANICAL PROPERTIES OF W ALLOYS UNDER HIGH FLUX D/HE IRRADIATION
12:20‐12:40
C3 Z. Chen (Univ. S&T China) (5d20)
HYDROGEN ISOTOPE RETENTION AND TRANSPORT PROPERTY IN FUSION STRUCTURAL MATERIALS 12:40‐1:00
NEW MODELING METHODS: Wednesday Morning, October 30, 2019: 11:00‐13:00 Chair: Y. Osetsky
Session Presenter Title Time
MOD METHODS
I1 B. N. Nguyen (PNNL) (6c6)
TAILORING MECHANICAL PROPERTIES OF DUCTILE‐PHASE TOUGHENED TUNGSTEN COMPOSITES BY A MULTISCALE MICROSTRUCTURAL APPROACH 11:00‐11:30
I2 L. Messina (KTH‐RIT) (6c9)
TRANSPORT PROPERTIES OF TRANSMUTATION PRODUCTS IN CONCENTRATED W‐RE‐OS ALLOYS BY SMART FITTING OF AB INITIO DATASETS 11:30‐12:00
C1 E. Martinez (LANL) (6b20)
ATOMISTIC MODELING OF HELIUM SEGREGATION TO GRAIN BOUNDARIES IN TUNGSTEN AND ITS EFFECT ON DE‐COHESION 12:00‐12:20
C2 T. Oppelstrup (LLNL) (6b42)
LARGE SCALE KINETIC MONTE‐CARLO MODELING OF RECRYSTALLIZATION IN TUNGSTEN 12:20‐12:40
C3 F. Gao (Univ. Michigan) (6a3)
MACHINE LEARNING FOR PREDICTING SEGREGATION AND HELIUM BUBBLES AT GRAIN BOUNDARIES IN METALS 12:40‐1:00
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MECHANICAL PROPERTIES: Wednesday Morning, October 30, 2019: 11:00‐13:00 Chair: L. Garrison Session Presenter Title Time
MECH. PROP.
I1 E. Wakai (J‐PARC) (5c10)
REVIEWS AND ANALYSIS OF IRRADIATION DAMAGE OF STRUCTURAL MATERIALS AND DESIGN WINDOWS UNDER DIFFERENT IRRADIATION ENVIRONMENTS 11:00‐11:30
I2 M. Sokolov (ORNL) (3d10)
IAEA COORDINATED RESEARCH PROJECT ON SMALL SPECIMEN TEST TECHNIQUES FOR FUSION APPLICATIONS 11:30‐12:00
C1 T. Tanno (JAEA) (5c17)
TENSILE PROPERTY CHANGES OF 11CR FERRITIC/MARTENSITIC STEEL IRRADIATED IN FAST REACTOR JOYO 12:00‐12:20
C2 X. Chen (ORNL) (5c3) EFFECTS OF NEUTRON IRRADIATION ON FRACTURE TOUGHNESS PROPERTIES OF STANDARD AND NI‐DOPED F82H STEELS 12:20‐12:40
C3 C. Yao (PSI) (5c9) DBTT SHIFT OF FERRITIC/MARTENSITIC AND ODS STEELS AFTER SPALLATION IRRADIATION EVALUATED WITH SMALL PUNCH TESTING 12:40‐1:00
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Wednesday Afternoon 3 Parallel Oral Sessions
HONORING PROF. BOB ODETTE (SPECIAL SESSION): Wednesday Afternoon, October 30, 2019: 14:30‐16:30 Chair: B. Wirth Session Presenter Title Time
ODETTE
I1 G. Lucas (UCSB) ODETTE HISTORICAL OVERVIEW 14:30‐15:10
I2 N. Ghoniem (UCLA) PLASTICITY OF IRRADIATED MATERIALS AT THE NANO‐ & MICRO‐SCALES REVEALED BY DISLOCATION DYNAMICS SIMULATIONS 15:10‐15:40
I3 T. Yamamoto (UCSB) MODELING OF HELIUM EFFECTS ON MICROSTRUCTURAL EVOLUTION IN TMS AND NFA: THE EFFECTS OF HE/DPA, TEMPERATURE, DOSE AND DOSE RATE 15:40‐16:05
I4 Y. Dai (PSI) APT/TEM CHARACTERIZATION OF THE MICROSTRUCTURAL AND CHEMICAL EVOLUTIONS IN RAFM AND ODS STEELS AFTER IRRADIATION AT SWISS SPALLATION NEUTRON SOURCE
16:05‐16:30
BULK MATERIALS MODELING: Wednesday Afternoon, October 30, 2019: 14:30‐16:30 Chair: L. Messina
Session Presenter Title Time
MOD BULK
I1 Y. Osetsky (ORNL) (5a19)
WHAT IS THE MAXIMUM POSSIBLE STRENGTHENING DUE TO LOCALIZED OBSTACLES IN FERRITIC ALLOYS? 14:30‐15:00
I2 S. Hayakawa (Univ. Tokyo) (6b1)
STUDY OF THE STABLE CONFIGURATION OF CASCADE‐INDUCED DEFECTS IN FCC METALS USING THE TEMPERATURE PARALLEL SIMULATED ANNEALING WITH SELF‐GENERATED BASINS
15:00‐15:30
C1 A. El‐Azab (Purdue University) (6b38)
CONTINUUM THEORY OF DEFECTS AS A FRAMEWORK FOR PREDICTIVE MODELING OF RADIATION EFFECTS IN CRYSTALLINE SOLIDS 15:30‐15:50
C2 P‐W. Ma (UKAEA Culham) (6b26)
ANISOTROPIC ELASTIC FIELDS OF RADIATION DEFECTS 15:50‐16:10
C3 X‐C. Li (IPP CAS) (6b27)
FIRST‐PRINCIPLES STUDY ON DISSOLUTION AND DIFFUSION PROPERTIES OF HYDROGEN IN Α‐AL2O3 16:10‐16:30
27
TRITIUM BREEDING: Wednesday Afternoon, October 30, 2019: 14:30‐16:30 Chair: K. Field Session Presenter Title Time
BREEDING
I1 A. Ying (UCLA) (2c1) CELLULAR BREEDER MATERIALS: A TRANSFORMATIVE CERAMIC SOLID BREEDER FOR FUSION REACTOR BLANKETS 14:30‐15:00
I2 V. Chakin (KIT) (2c13) TRITIUM AND HELIUM RELEASE FROM BERYLLIUM PEBBLES IRRADIATED UP TO 640 APPM TRITIUM AND 6000 APPM HELIUM 15:00‐15:30
C1 P. Vladimirov (KIT) (2c16)
DEVELOPMENT AND CHARACTERIZATION OF ADVANCED NEUTRON MULTIPLIER MATERIALS 15:30‐15:50
C2 S. Waters (Univ. Sheffield) (2c12)
RADIATION DAMAGE AND HELIUM ACCOMMODATION IN LITHIUM METATITANATE CERAMIC BREEDER MATERIALS 15:50‐16:10
C3 I. L. Tazhibayeva (IEA NNC‐RK) (2c7)
REACTOR STUDIES OF TRITIUM RELEASE FROM LEAD‐LITHIUM EUTECTIC LI15.7PB WITH DEUTERIUM OVER THE SAMPLE 16:10‐16:30
THURSDAY, October 31, 2019 Plenary Session3
8:30‐10:30 Chair: J. Marian Session Presenter Title Time
PLEN–3
P7 C. García‐Rosales CEIT
CURRENT STATUS OF THE DEVELOPMENT OF OXIDATION‐RESISTANT TUNGSTEN‐BASED ALLOYS FOR FIRST WALL APPLICATION IN FUSION
DEVICES 8:30‐9:10
P8 S. Nogami Tohoku University
MECHANICAL PROPERTIES OF TUNGSTEN 9:10‐9:50
P9 J‐H. You IPP Garching
STATUS OF TECHNOLOGY R&D AND THE RESULTS OF PRE‐ CONCEPTUAL EVALUATION OF THE EU DEMO DIVERTOR TARGET CONCEPTS 9:50‐10:30
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Thursday Morning 3 Parallel Oral Sessions
TUNGSTEN‐1: Thursday Morning, October 31, 2019: 11:00‐13:00 Chair: J. Coenen Session Presenter Title Time
TUN–1
I1 T. Miyazawa (Tohoku Univ.) (1d23)
NEUTRON IRRADIATION EFFECTS ON MECHANICAL PROPERTIES OF TUNGSTEN ALLOYS 11:00‐11:30
I2 J. Trelewicz
(Stonybrook Univ.) (1d31)
CONTROLLING STABILITY AND RADIATION TOLERANCE OF TUNGSTEN THROUGH NANOSCALE GRAIN BOUNDARY ENGINEERING 11:30‐12:00
C1 J. Matějíček (IPP Prague) (1d26)
IRRADIATION EFFECTS ON MECHANICAL PROPERTIES OF SPARK PLASMA SINTERED W‐BASED MATERIALS 12:00‐12:20
C2 M. Akiyoshi (Osaka Univ.) (1d2)
THERMAL DIFFUSIVITY OF IRRADIATED TUNGSTEN AND TUNGSTEN‐RHENIUM ALLOYS 12:20‐12:40
C3 D. Schwalenberg (FZJ) (1d21)
UPSCALING OF TUNGSTEN‐FIBER REINFORCED TUNGSTEN PRODUCTION VIA CVD 12:40‐1:00
RADIATION DAMAGE‐1: Thursday Morning, October 31, 2019: 11:00‐13:00 Chair: X. Hu
Session Presenter Title Time
DMG–1
I1 S. Zinkle (UTK) (5a14) DEFECT PRODUCTION, DIFFUSION AND INTERACTION WITH HE IN IRRADIATED MATERIALS 11:00‐11:30
I2 S. Ohnuki (USTB) (5c8) ANOMALOUS PHASE SEPARATION IN FE‐CR ALLOYS UNDER THREE TYPES OF IRRADIATION 11:30‐12:00
C1 J. Byggmästar (Univ. Helsinki) (5a21)
CASCADE OVERLAP EFFECTS IN IRON AND TUNGSTEN 12:00‐12:20
C2 D. Edwards (PNNL) (5b24)
RESISTANCE TO VOID FORMATION IN ODS ALLOYS IN THE PRESENCE OF IN‐SITU HELIUM INJECTION 12:20‐12:40
C3 A. Gentils (CSNSM Paris) (5d34)
THE EFFECTS OF HIGH‐DOSE HE AND H ION IMPLANTATION ON THE MICROSTRUCTURAL DEVELOPMENT IN EUROFER‐ODS STEEL 12:40‐1:00
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PSI MODELING: Thursday Morning, October 31, 2019: 11:00‐13:00 Chair: W. Setyawan Session Presenter Title Time
MOD PSI
I1 Q. Yu (UCLA) (6b31) KINETIC MODELING OF HYDROGEN RETENTION IN TUNGSTEN UNDER FUSION CONDITIONS USING SPATIALLY RESOLVED STOCHASTIC CLUSTER DYNAMICS 11:00‐11:30
I2 D. Martin (UTK) (2a50) LARGE SCALE MD STUDY OF THE EFFECT OF A HELIUM BUBBLE LAYER ON HYDROGEN DIFFUSION IN TUNGSTEN 11:30‐12:00
C1 C. Stihl (KIT) (5d33) MULTISCALE TRITIUM DESORPTION MODELS FROM (0001) BE SURFACES 12:00‐12:20
C2 M. A. Cusentino (SNL) (6b46)
MOLECULAR DYNAMICS MODELING OF MIXED MATERIALS IN TUNGSTEN USING MACHINE LEARNED INTERATOMIC POTENTIALS 12:20‐12:40
C3 Y. Huang (UCLA) (6a2) MULTISCALE‐MULTIPHYSICS BASED DESIGN OF A SOLID‐LIQUID HYBRID DIVERTOR MODULE 12:40‐1:00
Thursday Afternoon
3 Parallel Oral Sessions TUNGSTEN‐2: Thursday Afternoon, October 31, 2019: 14:30‐16:30 Chair: J. Trelewicz
Session Presenter Title Time
TUN–2
I1 T. Höschen (IPP Garching) (1d7)
PRE‐CHARACTERIZATION OF WF/W MATERIAL FOR THE EUROFUSION IRRADIATION CAMPAIGN 14:30‐15:00
I2 K. Li (Tsinghua Univ.) (1d33)
CHALLENGES AND ACHIEVEMENTS ON ADDITIVE MANUFACTURING OF TUNGSTEN 15:00‐15:30
C1 E. Tejado (Univ. Polit. Madrid) (1d5)
SELECTIVE LASER BEAM MELTING OF PURE TUNGSTEN: MICROSTRUCTURE AND MECHANICAL BEHAVIOR 15:30‐15:50
C2 M. J. Pfeifenberger (ESI Austria) (1d12)
FRACTURE TOUGHNESS ANISOTROPY OF ULTRAFINE GRAINED TUNGSTEN MATERIALS 15:50‐16:10
C3 F. Fan (SWIP) (1d27) MECHANICAL PROPERTY AND MICROSTRUCTURE OF W‐TA ALLOY PROCESSED BY HIGH ENERGY RATE FORGING 16:10‐16:30
30
RADIATION DAMAGE‐2: Thursday Afternoon, October 31, 2019: 14:30‐16:30 Chair: E. Wakai Session Presenter Title Time
DMG‐ 2
I1 M. Klimenkov (KIT) (5b31)
CORRELATION OF MICROSTRUCTURAL AND MECHANICAL PROPERTIES OF NEUTRON IRRADIATED EUROFER97 14:30‐15:00
I2 X. Hu (ORNL) (5b30) OVERVIEW OF TRANSMUTATION‐INDUCED PRECIPITATION IN TUNGSTEN DURING NEUTRON IRRADIATION 15:00‐15:30
C1 W. Jiang (PNNL) (5a6) DAMAGE ACCUMULATION AND VOID FORMATION IN SELF‐ION IRRADIATED TUNGSTEN 15:30‐15:50
C2 Y‐R. Lin (UTK) (5b17) VOID SWELLING IN ION IRRADIATED HIGH‐PURITY FE AND FE‐CR ALLOYS: PEAK SWELLING TEMPERATURES AND CARBON EFFECT 15:50‐16:10
C4 M. Miyamoto (Shimane Univ.) (5b26)
FORMATION AND MIGRATION OF HELIUM BUBBLES IN REDUCED ACTIVATION FERRITIC/MARTENSITIC STEEL F82H 16:10‐16:30
FUSION STARTUP COMPANIES (SPECIAL SESSION): Thursday Afternoon, October 31, 2019: 14:30‐16:30 Chair: L. Snead
Session Presenter Title Time
FUSION STARTUPS
FS1 A. Smirnov TAE Technologies, Inc
PROGRESS AND CHALLENGES IN TAE’S QUEST TOWARDS A PRACTICAL FRC‐BASED FUSION REACTOR 14:30‐15:00
FS2 Zach Hartwig Commonwealth Fusion
MATERIALS CHALLENGES AND OPPORTUNITIES FOR HIGH‐FIELD TOKAMAK POWER PLANTS 15:00‐15:30
FS3 W. M. Solomon GA DIII‐D Team
DIII‐D RESEARCH TOWARD FUSION ENERGY, CURRENT STATUS AND FUTURE PLANS 15:30‐16:00
FS4 T. P. Davis
Davis & Musgrove Ltd., Oxford
MATERIALS STRATEGY FOR FIRST‐OF‐A‐KIND FUSION POWER STATIONS 16:00‐16:30
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FRIDAY, November 1, 2019 Plenary Session4
8:30‐10:30 Chair: S. Zinkle Session Presenter Title Time
PLEN–4
P10 T. Hinoki Kyoto University
DEVELOPMENT AND CHARACTERIZATION OF ADVANCED SIC COMPOSITES FOR FUSION 8:30‐9:10
P11 Y. Katoh ORNL
PROJECT PHENIX FOR TECHNOLOGICAL ASSESSMENT OF PLASMA FACING COMPONENTS FOR DEMO REACTORS: SUMMARY OF MATERIALS RESEARCH
ACCOMPLISHMENTS 9:10‐9:50
P12 D. J. Sprouster Stonybrook University
ADVANCED SYNCHROTRON CHARACTERIZATION TECHNIQUES FOR FUSION MATERIALS SCIENCE 9:50‐10:30
FRIDAY, November 1, 2019
Technical Tours 14:30‐17:00
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ME Mauel
MICHAEL MAUEL is a professor of applied physics at Columbia University. He received his B.S., M.S., and Sc.D. at Massachusetts Institute of Technology (MIT). While at MIT, Dr. Mauel was awarded the Fortesque Fellowship from the Institute of Electrical and Electronics Engineers (IEEE) and the Ernst A. Guillemin Thesis Award from MIT. Before joining Columbia in 1985, Dr. Mauel conducted postdoctoral research at MIT and conducted high‐power electron cyclotron heating experiments at the Tara Tandem Mirror. His fields of interest include advanced tokamak operating regimes, feedback techniques to control tokamak instabilities, nonlinear turbulent transport in magnetized plasma including energetic particle modes, and the relationship between laboratory and space plasma physics. In 1995, Dr. Mauel was elected a fellow of the American Physical Society (APS). From 2000‐2006, he was chair of the Department of Applied Physics and Applied Mathematics at Columbia. In 2006, he was a Jefferson Science Fellow for the U.S. Department of State. Dr. Mauel has served as a member of several committees in the APS and served as chair of the APS Division of Plasma Physics from 2002‐2003. He was president of the University Fusion Association from 1997‐1998, co‐chair of the 1999 Fusion Summer Study in Snowmass, chair of the U.S. International Thermonuclear Experimental Reactor (ITER) Forum in 2003, chair of the U.S. Burning Plasma Council from 2010‐2013, and chair of the Plasma Science Committee of the National Academies of Sciences, Engineering, and Medicine from 2012‐2015. He served on several Department of Energy (DOE) Fusion Energy Sciences Advisory Committee (FESAC) activities, including the FESAC Office of Fusion Energy Committee of Visitors (2003‐2004), FESAC Fusion Major Facilities Panel.
Keynote & Plenary Speakers
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Greg deTemmerman
Greg De Temmerman is currently working as coordinating scientist for plasma edge and plasma‐wall interactions at the ITER Organization. He graduated as a chemist in 2003 and obtained his PhD in experimental physics in 2006. He specialises in the study of the interactions between fusion plasmas and surrounding materials. He worked in several laboratories including PISCES (UCSD, USA), CCFE (UK) and DIFFER (NL) before joining the ITER Organization in 2014. At ITER, the main focus of his research has been on assessing the impact of plasma‐material interactions on the thermal and mechanical properties of tungsten. He has developed the concept of operational budget for the tungsten material based on the recrystallization kinetics, and recently proposed a growth/annealing equilibrium model to describe the formation of helium‐induced nanostructures (‘fuzz’) which has been applied to evaluate the possibility of fuzz growth in ITER and the possible influence of transient heat loads.
During his spare time he is also a passionate ultra‐trail runner, and is active in outreach activities around ITER and fusion.
Chi Zhang
Not Received
S.L. Dudarev
Sergei Dudarev, PhD Moscow, MA Oxford, has made transformative contributions to three areas of materials science: the density matrix approach in electron diffraction and electron microscopy, the electronic structure of transition metal and actinide oxides, and models for radiation damage in materials for nuclear power generation. When exploring UO2, Dudarev developed a first principles approach that treats strong electron correlations on equal footing with chemical bonding in the material. This is now among the most frequently used ab initio methods, with the original work cited more than 5000 times. After joining the UK Atomic Energy Authority, Dudarev led the first ab initio investigation of radiation‐induced intrinsic point defects, spanning the entire group of refractory bcc metals and iron, and highlighting the need to develop interatomic potentials that include magnetism. The first of such potentials was formulated in 2005, enabling simulations of radiation damage in iron on a million‐atom scale. In 2007 Dudarev was appointed co‐chair of the EU fusion materials programme where, following a large expansion of the programme in 2014, he became the leader of materials modelling part of it. Sergei Dudarev leads materials modelling and simulation research at UKAEA, he is a Visiting Professor in Materials at the University of Oxford, and a member of editorial boards of Journal of Nuclear Materials, and Nuclear Fusion.
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Jiming Chen
Post‐graduating from Xi’an Jiaotong University (China) in 1988 with the master degree in technology, he has been working in Southwestern Institute of Physics (SWIP) in China since then for more than 30 years, majoring in R&Ds for fusion reactor materials and engineering technologies, such as irradiation effects and simulations, liquid metal corrosion, MHD pressure drop for liquid metal blanket, mechanical property evaluation, blanket design and manufacturing technologies. He studied on V‐base alloys for nearly 10 years with good collaboration with NIFS in Japan and obtained his Ph. D in the Graduate University for Advanced Studies in Japan in 2006. At the same time the CLF‐1 RAFM steel was successfully developed in China with his effort. Thereafter, he has been leading a team in SWIP and working for ITER first wall and shield blanket for 15 years, making significant contributions to the development of high heat flux technologies. He is the director of the Fusion Reactor Technology Division in SWIP and the leader of the Sichuan High Heat Load Material & Component Engineering Technology Centre, which covers wider research areas including ITER TBM & CFETR blanket, DEMO divertor, neutron irradiation of fusion reactor materials.
T. Sdchwarz‐Sellinger
Thomas Schwarz‐Selinger is a senior scientist at the Max‐Planck‐Institut für Plasmaphysik (IPP), Garching, Germany. He is an experimental physicist working for the last 23 years on questions related to fuel retention and release from fusion reactor materials. He received his PhD at the university of Bayreuth, Germany in 2000 working on the question of tritium co‐deposition with carbon. He was a Postdoctoral research fellow at the Frederick Seitz Materials Research Laboratory, University of Illinois at Urbana/Champaign in 2001 to return to Garching to continue working on hydrogen isotope retention in carbon. In 2010 he was a visiting scientist at the PISCES laboratories, Center for Energy Research, University of California at San Diego within the EU‐US collaborative program on “Beryllium Mixed Material Effects on Erosion and Redeposition in Fusion Devices” to extend his knowledge to beryllium. Since 2013 he is coordinating the tandem accelerator laboratory at IPP Garching and focuses on hydrogen isotope transport and release from tungsten. He concentrated in the last years on so‐called self‐damaged tungsten as a surrogate for neutron irradiated tungsten and specialized on the influence of the presence of hydrogen on displacement damage as well as the influence of helium on hydrogen transport and retention. He authored till now 143 peer reviewed articles.
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GR Odette
Professor Odette is a Distinguished Professor (Emeritus) of Materials and Mechanical engineering at UCSB, He received a PhD in Nuclear Engineering from MIT in 1970, and joined the UCSB faculty that same year, where he has been ever since. His MS project was to measure the damage rate produced by 14 MeV D‐T fusion neutrons compared to that in a fission reactor spectrum, using a very sensitive internal friction technique. Thus Professor Odette’s research on fusion materials has spanned over 50 years. The general theme of his research is predicting and enhancing the performance of structural alloys used in long‐term service in hostile service environments. These environments include nuclear fission and fusion reactors, high temperature hypersonic aerospace conditions, and fossil energy systems. Professor Odette retired from teaching in 2014 but remains active in research. He admits that the rumor that he has “flunked” retirement is probably true. Indeed. Professor Odette looks forward to three more years in the fusion materials program.
M. Nakamichi
1) I finished my doctor’s degree in engineering from Tohoku University, Japan.
2) I am engaged in the Fusion Energy Directorate of National institutes for Quantum and Radiological Science and Technology (QST) as the group leader of the Breeding Functional Materials Development Group.
3) I am also in charge of the responsible officer of R&D on neutron multipliers and tritium breeders as breeding functional materials in the framework for the Broader Approach activities.
4) I specialize in the resources, materials and energy engineering including a fusion blanket functional materials development, an irradiation technology development and an instrumentation technology development.
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Carmen García‐Rosales
Carmen García‐Rosales is Senior Researcher at the Materials and Manufacturing Division of CEIT‐IK4 Technology Center in San Sebastian, Spain, and Professor for Solid State Physics at the University of Navarra’s School of Engineering (Tecnun), also in San Sebastian. She obtained her degree in Physics (1987) at the University of Münster, Germany, and her PhD in Physics (1991) at the Technical University Aachen (RWTH), Germany, after spending three years at the Institute for Reactor Materials at the Jülich Research Centre in Germany on a doctoral grant. She moved to the Max‐Planck‐Institute for Plasma Physics in Garching, Germany, for a two‐ year post‐doctoral position at the Plasma‐Wall‐Interaction Division. Afterwards, she spent two and a half years as a staff scientist on the fusion experiment ASDEX‐Upgrade at the Max‐ Planck‐Institute for Plasma Physics in Garching, Germany, working in the field of plasma‐wall interaction processes and materials selection for the first wall of the tokamak ASDEX‐Upgrade. 1996 she joined CEIT and the School of Engineering of the University of Navarra, where she has been conducting research primarily on the development of materials for nuclear fusion application, especially of oxidation‐resistant tungsten‐based alloys for first wall application, porous SiC‐based materials for DCLL blankets, ODS steels and doped carbon‐based materials, using mainly powder metallurgical routes.
She has supervised more than 20 research projects, most of them international collaborative projects. She is author or co‐author of above 100 scientific peer‐reviewed papers.
S. Nogami
Shuhei Nogami is an Associate Professor in the Department of Quantum Science & Energy Engineering, Graduate School of Engineering, Tohoku University. He received his Ph.D. in Engineering from Tohoku University in 2003. He was a researcher at HITACHI Ltd. until 2006, where he worked on creep‐ fatigue phenomena of materials and components utilized for the steam and gas turbines based on the experimental and computational approaches. He started his career as an Assistant Professor at Department of Quantum Science & Energy Engineering, Graduate School of Engineering, Tohoku University in 2006. He has been dedicated to the development and characterization of tungsten based materials, SiC/SiC composites, and ferritic/martensitic steels for fusion reactor applications and the development of small specimen test techniques for testing neutron‐irradiated materials.
37
J.H. You
Jeong‐Ha You is working at Max Planck Institute of Plasma Physics in Garching since 1999 and has been leading the DEMO divertor project of EUROfusion Consortium as project leader since 2014. He is also serving as adjunct professor at the Physics Department of Ulm University where he completed Habilitation in materials science. He is also an editorial board member of journal “Nuclear Materials & Energy”
Prof. You was educated at Seoul National University majoring in metallurgy for his undergraduate and master study and at RWTH Aachen for his doctoral degree in mechanical engineering for which he was awarded Borchers prize. Before joining the IPP, he was trained as postdoctoral fellow at Institute of Energy Materials in Research Center Jülich and Institute of General Mechanics in RWTH. His research expertise covers materials, mechanics, design, manufacturing technology and testing of high‐heat‐flux plasma‐facing components (divertor, limiter) for fusion power plants.
Tatsuya Hinoki
Tatsuya Hinoki graduated and was granted Ph. D in energy science from Kyoto University, Japan, 2001. He had worked on R&D of SiC ceramics and SiC/SiC composites for nuclear application including refractory armor coating in 2001 through 2003 at Oak Ridge National Laboratory, USA. He has worked on R&D of ceramics and ceramic matrix composites for advanced nuclear energy system including assembly joining technique and for aerospace application since 2003 at Institute of Advanced Energy, Kyoto University. He is a member of several Japanese academic societies and committees and a member of the American Ceramic Society. He had been responsible for several domestic and international research projects. Over 150 scientific papers as author or co‐author are published.
38
Yutai Katoh
Yutai Katoh, Ph.D. is Distinguished Research Staff at Materials Science and Technology Division, Oak Ridge National Laboratory, and Joint Appointment Professor with Department of Nuclear Engineering, University of Tennessee at Knoxville. Dr. Katoh has over 25 years of combined experiences in academia and national laboratories with research focuses on radiation effects in materials, materials for fusion and fission energy, and refractory ceramics, graphite and composites. His research interest spans from physics of fundamental radiation defects in metals and ceramics to processing and applications of advanced materials for severe environment services and qualification of new materials for nuclear applications.
D. J. Sprouster
Dr. Sprouster is an Assistant Research Professor in the Materials Science and Chemical Engineering Department at Stony Brook University. His research expertise lies in utilizing advanced synchrotron‐ radiation techniques to quantify neutron and ion beam modifications of structural and nanomaterials. He previously held an Assistant Material Scientist position at Brookhaven National Laboratory and was a Research Fellow at The Australian National University. He has developed synchrotron beamline infrastructure, novel sample processing and analysis procedures, which have proved to be essential for the extraction of quantitative microstructural information. His current research efforts are focused towards the high‐throughput, in situ and analysis of data collected on materials for advanced nuclear and fusion energy systems at the National Synchrotron Light Source‐II (NSLS‐II). He commonly engages with the wider materials community, aiding in the collection, analysis and interpretation of experimental data.
39
Poster Presentations
40
All posters will be displayed at the Vicino Ballroom
Poster Layout
41
Vicino Ballroom
Poster Sessions will be held here.
42
List of Poster Presentations
43
No. Author Abstract Title Poster
Address
1 Hoon Lee1*, Mark Warren2, Xiang Liu1, Zhengrong Lee2, Huan Yan1, Kuan-Che Lan1, Joshua Wright3, Meimei Li3, Jonathan Almer3, Jeff Terry2, James F. Stubbins1
In-situ Synchrotron X-ray Diffraction Study on Mechanical deformations of Neutron Irradiated Fe-Cr-C Alloys
1a
2 Chang-Hoon Lee1*, Joonoh Moon1, Tae-Ho Lee1, Seong-Jun Park1, Hyun-Uk Hong2, Chansun Shin3, Dong-Chan Jang4, Myoung-Gyu Lee5, and Hyoung Chan Kim6
Ta and Ti added RAFM steel with enhanced mechanical properties and resistance to irradiation
1b
3 C. Cristalli1*, L. Pilloni2 , O. Tassa3 , L. Bozzetto3 Mechanical properties of several newly produced RAFM steels with Tungsten content in the range of 2 wt.%
2a
4 Anne A. Campbell1*, J. Wilna Geringer1, Yutai Kato1, Masami Ando2, Dai Hamaguchi2
IRRADIATION CREEP OF F82H MEASURED USING PRESSURIZED TUBES IRRADIATED IN THE HFIR
2b
5 Sho Kano1, Huilong Yang1, John McGrady1, Dai Hamaguchi2, Masami Ando2, Hiroyasu Tanigawa2 and Hiroaki Abe1
The amorphization of M23C6 in RAFM steel under ion accelerator irradiation 3a
6 Niyanth Sridharan1*, Kevin G. Field1
A ROAD MAP TO DEVELOP AND PROCESS FERRITIC MARTENSITIC STEELS FOR FUSION REACTORS USING ADDITIVE MANUFACTURING
3b
7 R. Coppola1*, D. Mirabile Gattia2, T. Mueller3, L. Pilloni2, A. Radulescu3
SANS AND NEUTRON DIFFRACTION STUDY OF EUROFER97/2 STEEL SUBMITTED TO THERMO-MECHANICAL TREATMENTS
4a
8 Mengtian Liang, Yanyun Zhao, Shaojun Liu* Yican Wu, Qunying Huang, FDS Team
IMPROVEMENT OF LOW CYCLE FATIGUE PROPERTIES OF CLAM STEEL BY GENERATING A GRADIENT NANOGRAINED SURFACE LAYER
4b
44
No. Author Abstract Title Poster Address
9 Joonoh Moon1*, Chang-Hoon Lee1, Tae-Ho Lee1, Seong-Jun Park1, Hyoung Chan Kim2
Development of Ta-Ti containing RAFM steel and its weldability 5a
10 Lei Peng1*, Yao Xie1, Wangzi Zhang1, Hongbin Liao2, Jingyi Shi3
Temperature impact on fracture toughness of CLF-1 steel 5b
11 Yanyun Zhao*, Mengtian Liang, Huang Bo, Shaojun Liu, Yican Wu, Qunying Huang, FDS Team
FATIGUE CHARACTERIZATION AND MODELING OF CLAM STEEL UNDER MULTI-AXIAL NON-PROPORTIONAL CYCLE LOADING
6a
12 Keiji Oishi1*, Shinichi inoue1*, Kazuhiro Fudemae1*, Rika Ishioka1*, Takayuki Terai1*
Compatibility between Fusion Reactor Blanket Structure Material F82H and Solid Breeder Lithium Meta-Titanates
6b
13
Sergey Rogozhkin1,2*, Alexander Nikitin1,2, Artem Khomich1, Nasib Iskandarov1, Vasiliy Khoroshilov1, Anton Lukyanchuk1, Oleg Raznitsyn1, Anton Shutov1, Petr Fedin1, Timur Kulevoy1, Alexander Vasiliev3, Michael Presniakov3, Komstantin Kravchuk4, Mariya Leontyeva-Smirnova5, Evgeny Mozhanov5, Rainer Lindau6, Anton Möslang6, Pavel Vladimirov6
EFFECT OF Fe ION IRRADIATION ON MICROSTRUCTURE AND NANOINDENTATION HARDNESS OF FERRITIC/MARTENSITIC STEELS AT LOW TEMPERATURES
7a
14 Lizhen Tan*, Jonathan D. Poplawsky, Arunodaya Bhattacharya
CHARACTERIZATION OF CASTABLE NANOSTRUCTURED ALLOYS USING APT AND TEM
7b
15 Yiyin Shan1*, Chao Liu1, Wei Yan1, Yanfen Li1
HOT DEFORMATION BEHAVIOR OF A NEW NUCLEAR USE REDUCED ACTIVATION FERRITIC/MARTENSITIC STEEL
8a
16 K. Wang1, 2*, K. G. Field1, C. M. Parish1, L. Tan1, Y. Katoh1, Hiroyasu Tanigawa3
MICROSTRUCTURAL EVOLUTION OF REDUCED ACTIVATION FERRITIC/MARTENSITIC (RAFM) STEELS AFTER NEUTRON-IRRADIATION UP TO 72 DPA
8b
17 Sangeun Kim1, Hyung-Ha Jin2, Joonoh Moon3, Chang-Hoon Lee3, Chansun Shin1*
ION-IRRADIATION HARDENING AND SWELLING OF Ti/Ta-added RAFM STEEL 9a
18 Yasuhide Yano*, Takashi Tanno, Hiroshi Oka, Yoshihiro Sekio, Satoshi Ohtsuka, Takeji Kaito and Yoshiaki Tachi
Tensile properties on dissimilar welds between 11Cr-ferritic/martensitic steel and 316 stainless steel after thermal aging
9b
45
No. Author Abstract Title Poster Address
19 Hongbin Liao1*, Xiaoyu Wang1, Xinghua Wu1, Zhiqiang Hu1, Guoping Yang1, Qin Chao1, Xueqing Wang1, Shikai Wu2, Liangying Xiong3
The recent welding technologies research progress of CLF-1 steel 10a
20 So Young Im1*, Joon Oh Moon2, Chang Hoon Lee2, Hyun Uk Hong1
Effect of Ti addition on Low cycle fatigue of RAFM steel 10b
21 T. P. Davis1*, M. P. Moody1, P.A.J. Bagot1, M. Auger1,2, D. E. J. Armstrong1
A Microstructural and Mechanical Investigation of Fe+ Ion vs Neutron Damage in Ferritic-Martensitic Steels for first-of-a-kind Fusion Reactors
11a
22 Huan Yan1*, Xiang Liu2, Linfeng He2, Yaqiao Wu3, Jatuporn Burns3, James Stubbins1
Microstructure Characterization and Mechanical Testing of HT9 and T91 Irradiated in Advanced Test Reactor
11b
23 Matej Kocen1*, Petra Jenuš2, Anže Abram2, Saša Novak2 Development of binderless WC for DEMO divertor 12a
24 Zhihong Zhong*, Zhiquan Wang, Bowen Sun, Yucheng Wu Enhanced mechanical properties of SiC joint by forming carbides composite interlayer and zigzag joining interface
12b
25 Thanataon Pornphatdetaudom1*, Katsumi Yoshida2, Tohru Suzuki3, Toyohiko Yano2
Particle Orientation Effect on Lattice Parameter Change by Neutron Irradiation and Recovery Behavior of Aluminum Nitride
13a
26 Monica Ferraris1, Sergio Perero1, Alice Scarpellini2, Simon Heuer 3
CO-SPUTTERED W/FE INTERLAYERS FOR JOINING TUNGSTEN TO STEEL 13b
27 H. Noto1*, Y. Hishinuma1, T. Muroga1 H.Benoki2 Effect of thermal changes of microstructure on mechanical properties of W-1.1wt%TiC 14a
28 Kazutoshi Tokunaga1*, Satoru Matsuo1, Hiroaki Kurishita2, Takeshi Toyama3, Makoto Hasegawa1 and Kazuo Nakamura1
Fatigue pre-cracking and fracture toughness evaluations in an ITER-grade rolled tungsten plate
14b
29 Magdalena Galatanu1*, Monica Enculescu1, Andrei Galatanu1, Jens Reiser2 W-W laminates processed by FAST 15a
30 Thorsten Loewenhoff*, Daniel Dorow-Gerspach, Gerald Pintsuk, Marius Wirtz
Repair and regeneration of plasma-facing tungsten surfaces 15b
31 Shunsuke Makimura1*, Hiroaki Kurishita1, Koichi Niikura2, Hun-Chea Jung2, Masahiro Onoi2, Yutaka Nagasawa2, Tatsuaki Sakamoto3, Hiroaki Ohfuji3
DEVELOPMENT OF TUNGSTEN ALLOY, TFGR W-1.1%TiC, AS ADVANCED TARGET MATERIAL FOR HIGH-POWER PROTON ACCELERATOR
16a
46
No. Author Abstract Title Poster Address
32 Shuhei Nogami1*, Akira Hasegawa1, Jens Reiser2, Michael Rieth2, Shotaro Watanabe1, Hiroyuki Noto3, Takuya Nagasaka3, and Takeshi Miyazawa1
DEVELOPMENT OF DISPERSION STRENGTHENED TUNGSTENALLOYS AND THEIR LAMINATED COMPOSITES
16b
33 Kwangmo Park1*, Sangpill Lee1, Jinkyung Lee1, Moonhee Lee2, Sungwon Kim2
Effect of sintering temperature and titanium content on the characterization of tungsten material
17a
34 Sanghyun Jung1*, Sangpill Lee1, Jinkyung Lee1, Moonhee Lee2, Seungkuk Hwang3
Solid State Sintering of Wf/W Composites and Their Characteristics 17b
35 Samuel A. Humphry-Baker1*, George D. W. Smith2,3 DEVELOPMENT OF TUNGSTEN CARBIDE-BASED MATERIALS FOR FUSION ENGINEERING APPLICATIONS
18a
36 Kazuki Saito1*, Takuya Nagasaka1,2, Makoto Kobayashi1,2, Jingjie Shen2, Gaku Yamazaki1, Valentyn Tsisar2,3, Takeo Muroga1,2
Effect of nitrogen impurity and alloy composition on mechanical properties of low-activation vanadium alloy
18b
37 M. Khalid Hossain1,2*, Kenichi Hashizume1**
VISUALIZATION OF HYDROGEN ISOTOPES DISTRIBUTION IN YTTRIUM AND COBALT DOPED BARIUM-ZIRCONATES
19a
38 Teruya Tanaka1, 2*,Takuya Nagasaka1, 2, Takeo Muroga1, 2, Masanori Yamazaki3, Takeshi Toyama3
ACTIVATION ANALYSYS FOR THE REFERENCE LOW-ACTIVATION VANADIUM ALLOY NIFS-HEAT-2
19b
39 Ran Wei, Pengfei Zheng, Haiying Fu, Liwen Zhang
EVOLUTION OF DISPERSION PARTICLES NEAR JOINT INTERFACE OF HIPED V-4CR-4TI ALLOYS W/O TI3SIC2 ADDITION DURING LONG-TERM ANNEALING AT ELEVATED TEMPERATURE
20a
40 Paul J. Barron1*, Michael Preuss1, Mike J. Gorley2, and Ed J. Pickering1
Towards V-based High Entropy Alloys for Fusion Blanket Applications 20b
41
Takuya Nagasaka1, 2*, Jingjie Shen1, Teruya Tanaka1, 2, Makoto Kobayashi1, 2, Takeo Muroga1, 2, Akio Sagara1, Kazuki Saito2, Valentyn Tsisar3, Kouji Fujita4, Ken-ichi Fukumoto4, Takeshi Toyama5, Takamasa Sugawara5, Kunio Yubuta5, Ryuta Kasada5, Yuji Yamauchi6, Kiyohiro
NO MORE THAN TEN YEARS FOR VANADIUM ALLOY RECYCLING AFTER THE USE IN FUSION REACTORS
21a
47
No. Author Abstract Title Poster Address
Yabuuchi7, Akihiko Kimura7, Seiji Sakurai8, Kazuhiro Nomura8, Hideo Yoshinaga8
42 Ken-ichi Fukumoto1*, Koji Fujita1, Masanori Yamazaki2 Effect of Temperature History on Swelling behavior of Vanadium Binary Alloy Irradiated in a Fast Reactor JOYO
21b
43 Tatsuya Fukushi1*, N. Hashimoto2 Research and development of High Entropy Alloys for nuclear reactor 22a
44 Yu Lei1*, Naoyuki Hashimoto2 Study on Cu-based High Entropy Alloys for Nuclear Fusion Application 22b
45 Yutao Zhai*, Bo Huang, Xiaodong Mao, Shaojun Liu, Yican Wu, Qunying Huang, FDS Team
MICROSTRUCTURES AND TENSILE PROPERTIES OF 316L STEEL PRODUCED BY SELECTIVE LASER MELTING
23a
46 Yukinori Yamamoto*, Roger G. Miller, Arthur F. Rowcliffe DESIGN OF ADVANCED BAINITIC STEELS WITH IMPROVEMENT IN CROSS-WELD PROPERTIES
23b
47 Da Chen1*, Shijun Zhao, Jianrong Sun2, Ji-Jung Kai Effect of minor doping elements on the radiation defects in FeCoNiCr-based high entropy alloys 24a
48 Taku Ishida1,2*, Hiroaki Kurishita1,2, Hiroyuki Noto3, Shunsuke Makimura1,2 and Eiichi Wakai1,4
AN EXPLORATORY PRODUCTION OF TITANIUM-BASED OXIDE DISPERSION-STRENGTHENED ALLOY MATERIAL
24b
49 R. Arredondo1, K.Schmid1, A. Houben2, W. Jacob1 Modelling of gas-driven deuterium permeation in EUROFER 25a
50
F. Effenberg1*, S. Brezinsek2, Y. Feng3, H. Frerichs1, J. Geiger3, M. Jakubowski3, R. König3, M. Krychowiak3, J.D. Lore4, D. Naujoks3, H. Niemann3, F. Reimold3, J.C. Schmitt5, O. Schmitz1, T. Sunn Pedersen3, G.A. Wurden6, D. Zhang3 and the W7-X team
Development of impurity seeding for divertor power flux handling in Wendelstein 7-X long-pulse scenarios
25b
51 Heung Nam Han1,*, Yeonju Oh 1, Nojun Kwak1, Ki-Baek Roh2, Gon-Ho Kim2, and Hyoung Chan Kim3
Materials properties and characterization of tungsten developed by spark plasma sintering 26a
52 Nojun Kwak1,*, Yeonju Oh 1, Ki-Baek Roh2, Gon-Ho Kim2, Hyoung Chan Kim3, and Heung Nam Han1
A comparative study on the deuterium irradiation behavior of tungsten materials fabricated by spark plasma sintering technique
26b
53 R. Mateus1, M.B. Costa2, J.P.S. Loureiro1, R. Gomes1, T. Pereira1, H. Alves1, H. Figueiredo1, C. Silva1, N. Catarino1,
DEUTERIUM RETENTION INVESTIGATIONS IN Li-Sn ALLOYS 27a
48
No. Author Abstract Title Poster Address
M. Dias1, R.C. da Silva1, L.C. Alves3, M. Guedes2,4, A.C. Ferro2,5, H. Fernandes1, E. Alves1,*
54 Elisa Sal1,2, Carmen García-Rosales1,2*, Aida Calvo1,2, Karsten Schlueter3,4, Iñigo Iturriza1,2, Rudolf Neu3,4, Gerald Pintsuk5
Microstructure, oxidation behavior and thermal shock resistance of self-passivating W-Cr-Y-Zr alloys
27b
55 Benjamin Spilker*1, Gerald Pintsuk1, Marius Wirtz1, Jonathan H. Yu2, Miroslaw Zlobinski1
Laser-Induced Desorption of Transient Thermally Damaged Beryllium 28a
56 Marlene I. Patino*, Russell P. Doener, George R. Tynan Al enrichment of AlN and Al2O3 during D plasma exposure 28b
57 Dwaipayan Dasgupta1*, Robert D. Kolasinski2, Chun-Shang Wong2, Dimitrios Maroudas3, Brian D. Wirth1,4
MODELING OF SURFACE MORPHOLOGICAL EVOLUTION OF PLASMA-FACING TUNGSTEN
29a
58 Dwaipayan Dasgupta1*, Robert D. Kolasinski2, Sophie Blondel1, Dimitrios Maroudas3, Brian D. Wirth1,4
MODELING OF HELIUM RETENTION AND BUBBLE BURSTING IN LOW-ENERGY HELIUM PLASMA-EXPOSED TUNGSTEN
29b
59 Umberto M. Ciucani1*, Hanns Gietl2, Lea Haus1, Johann Riesch2, Wolfgang Pantleon1
Microstructural arrangement and texture evolution in single tungsten fibre-reinforced tungsten: recrystallization and abnormal grain growth
30a
60 Z.J. Bergstrom1*, L. Yang1, B.D. Wirth1 Hydrogen Trapping and Segregation Strength of Helium Interfaces in BCC Tungsten and Iron 30b
61 Robert D. Kolasinski1,*, Aaron Engel1, Dwaipayan Dasgupta2, Chun-Shang Wong1, Josh A. Whaley1, Dean A. Buchenauer1, Dimitrios Maroudas3, and Brian D. Wirth2
In-situ spectroscopic ellipsometry for characterizing plasma-surface interactions 31a
62 Chang-Chun Ge*,§, Qing-Zhi Yan§, Xiao-Na Ren§ Progress of Research on Plasma Facing Materials for Fusion Reactors in INM, USTB 31b
63 Xiao-Na REN1, *, Min XIA1,§, Qing-Zhi YAN1, §, Chang-Chun GE1, §
Tungsten Nanowires Prepared for Bulk Tungsten Strengthening 32a
64 Michael Duerrschnabel1*, Birger Holtermann1, Ute Jaentsch1, Mirjam Hoffmann1, Jan Hoffmann1, Siegfried Baumgaertner1, Steffen Antusch1, Michael Rieth1
Characterization of powder injection molded tungsten composites via electron microscopic methods
32b
65 M. Eddahbia, M.A. Mongea, b, * R. Domínguez Reyesa, B. Savoinia, b, A. Muñoza, b
MICROSTRUCTURE AND MECHANICAL PROPERTIES OF A NOVEL COPPER COMPOSITE REINFORCED BY
33a
49
No. Author Abstract Title Poster Address
NANOMETRIC VANADIUM CARBIDE PARTICLES
66 Y. Hishinuma1,2) , B. Ma2), B. Huang3), H. Noto1,2), Y. Liu4), R. Kasada4), S. M. S. Aghamiri5), N. Oono5), S. Ukai5) and T. Muroga1,2)
Effects of Mechanical Alloying parameters on the Cu-Y2O3 ODS alloys synthesized with MA-HIP process
33b
67 Shuming Wang1*, Jiangshan Li1, Yanxin Wang1, Changchun Ge1*
Thermal shock behavior analysis of tungsten-armored plasma facing components 34a
68 Dahuan Zhu 1,*, Changjun Li 1,2, Junling Chen 1, Rui Ding 1, Baoguo Wang 1 and EAST Team
Thermal induced cracking and melting on ITER-like W/Cu PFMC in EAST 34b
69 Yuchen Liu1*, Sosuke KONDO1, Hao YU1, Haoran WANG1, Ryuta KASADA1, Kiyohiro YABUUCHI2, Takeo MUROGA3, Shigeharu UKAI4
Evaluation of irradiation hardening of ion-irradiated ODS-Cu Alloy using ultra-small testing technologies (USTT)
35a
70 Marta Dias 1*, Francisco Antão 1, José. B. Correia 2, Marcin Rosinski 3, R.C da Silva1, António P. Gonçalves 4, Patrícia Carvalho 5,6, Eduardo Alves 1
SYNTHESIS AND CARACTHERIZATION OF WxTaCrNbV HIGH ENTROPY ALLOYS 35b
71 Barbara Wielunska1, Matej Mayer1, Thomas Schwarz-Selinger1, Werner Egger2, Lukasz Ciupinski3, Tomasz Plocinski3
RADIATION DAMAGE AND DEUTERIUM RETENTION IN TUNGSTEN 36a
72 F. Borgognonia*, V. Burwitzb, W. Eggerc, T. Schwarz-Selingerb, M. Vadruccia, M. Zibrovb, L. Picardia
Vacancy creation on tungsten through MeV electron-beam irradiation 36b
73 Takaaki Koyanagi*, Hsin Wang, Yoonjo Lee, Yutai Katoh EFFECTS OF NEUTRON IRRADIATION ON ELECTRICALPROPERTIES OF HIGH-PURITY SiC CERAMICS
37a
74 M. Zibrov1*, W. Egger2, M. Mayer1
HIGH TEMPERATURE RECOVERY OF RADIATION DEFECTS IN TUNGSTEN AND ITS EFFECT ON DEUTERIUM RETENTION
37b
75 Ningning Zhang1, Yujuan Zhang1,*, Changchun Ge1,*
THEORETICAL INSIGHT INTO THE INFLUENCES OF NITROGEN/ZIRCONIUM AND VACANCY DEFECTS ON THE BEHAVIOR OF HELIUM IN TUNGSTEN
38a
76 Chase N. Taylor1*, Masashi Shimada1, Yasuhisa Oya2
CHARACTERIZATION OF BULK DEFECTS IN NEUTRON IRRADIATED TUNGSTEN BY POSITRON ANNIHILATION SPECTROSCOPY
38b
50
No. Author Abstract Title Poster Address
77 H. Watanabe*a, T. Irie b,Y. Gouya b, Y. Kamada c Effects of Mn, Ni addition on radiation induced dislocation loops and solute clusters of Fe-based model alloys under Irradiation
39a
78 W. Q. Chen1,2, X. Z. Xiao3, K. L. Li1, T. W. Morgan4, W. Liu1,* and Y. L, Chiu2
Mechanical properties of tungsten under hydrogen plasma exposure at different temperature
39b
79 Hans-Christian Schneider, Alexander Valentin Brabänder, Michael Klimenkov
Thermally Activated Recovery of Neutron-induced Defects and Mechanical Properties of Reduces Activation Ferritic/Martensitic Steels
40a
80 Takuya Yamamoto1*, Dhriti Bhattacharyya2, Emmanuelle E. Marquis3, Tarik A. Saleh4, Stuart A.Maloy4 and G. Robert Odette1
Microstructure Based Predictions of Hardening in Irradiated Fe-Cr Alloys and Tempered Martensitic Steels
40b
81 S. Hoque1, C. Hardie2, E. Tarleton1, D. Armstrong1, A. Wilkinson1
MICROTENSILE TESTING TO EXAMINE IRRADIATION RESPONSE OF IRON-CHROMIUM FOILS
41a
82
R. G. Abernethya,b, M. J. Lloyda, A. Giannattasioa, J.D. Murphya,c, O. Woutersd, M. Gilbertb, M. Klimenkove, M. Riethe, C. Hardieb, P. Bagota, M. Moodya, S. Robertsa,b, D. Armstronga
Comparing irradiation damage in ion and neutron irradiated tungsten 41b
83 Max Boleininger1*, Thomas D Swinburne2 , and Sergei L Dudarev1
A CONTINUUM NON-SINGULAR THEORY OF THERMALLY FLUCTUATING DISLOCATIONS
42a
84 Roshan Rajakrishnan*, Ermile Gaganidze, Jarir Aktaa Modelling the post-yield and post-necking behaviour of F/M steel 42b
85 Hu Jia-ju*,Zhang bin ,Liu Cong ,Chen Yi-xue
COMPUTATIONALLY OPTIMIZED MULTI-GROUP CROSS SECTION DATA COLLAPSING FOR FUSION REACTOR SHIELDING CALCULATION
43a
86 Dmitry D. Demidov1*, Alexander B. Sivak1, Polina A. Sivak1
ENERGETIC, DIFFUSIONAL AND DISSOCIATIVE CHARACTERISTICS OF SELF DI-INTERSTITIALS IN BCC FE AND V
43b
87 Michael P. Higgins1*, Chaoming Yang2, Liang Qi2, Fei Gao1
Multiscale modelling of dislocation-nanocluster interactions in Fe-Y2O3: from molecular dynamics to dislocation dynamics
44a
51
No. Author Abstract Title Poster Address
88 Y. Igitkhanov1,2*, B. Bazylev1,2 and S. Pestchanyi1 THE EFFECT OF THE RUNAWAY ELECTRONS ON THE DEMO WALL EROSION
44b
89 Lixia Liu1, Yangchun Chen2, Wangyu Hu1, Fei Gao3,1, Huiqiu Deng2*
ATOMISTIC SIMULATIONS OF TRANSMUTATION-PRODUCED RE INTERACTION WITH GRAIN BOUNDARIES IN TUNGSTEN
45a
90 Juan P. Balbuena1*, Andrea Sand2, Carolina Björkas2, Kai Nordlund2, Robin Scäublin3, Maria J. Caturla1
Simulation of dislocation loops formation after ion irradiation in UHP-Fe thin films 45b
91 Giridhar Nandipati1*, Wahyu Setyawan1, Kenneth J. Roche1, Richard J. Kurtz1, Brian D. Wirth2
Effect of Confinement of SIA Diffusion by Traps on Radiation Damage Accumulation in Tungsten 46a
92 Emil Levo1*, Fredric Granberg1, Kai Nordlund1, Flyura Djurabekova,1,2
RADIATION STABILITY OF NANOCRYSTALLINE SINGLE PHASE MULTICOMPONENT ALLOYS
46b
93 Xinfu He1*, N. Castin2, S. Van den Kerkhof 3, D. Terentyev2, Wen Yang1
Monte-Carlo modelling of microstructure induced by neutron irradiation in ITER-specification tungsten: effect of heat transients
47a
94 Yuji Nobuta1, Masashi Shimada2, Chase N. Taylor2, Yasuhisa Oya3, Yuji Hatano4
EFFECTS OF HELIUM SEEDING ON DEUTERIUM RETENTION IN NEUTRON-IRRADIATED TUNGSTEN
47b
95 Ayaka Koike 1*, Akihiro Togari 1, Moeko Nakata 1, Shota Yamazaki 1, Takuro Wada 1, Fei Sun 2, Mingzhong Zhao 1, Naoaki Yosida 3, Kazuaki Hanada 3, Yasuhisa Oya 1,2
EVALUATION OF HYDROGEN RETENTION BEHAVIORIN TUNGSTEN EXPOSED TO HYDROGEN PLASMA IN QUEST
48a
96
Jing Wang1*, Yuji Hatano1, Tatsuya Hinoki2, Alexander V. Spitsyn3, Nikolay P. Bobyr3, Sosuke Kondo4, Takeshi Toyama 4, Heun Tae Lee5, Yoshio Ueda5
DEUTERIUM RETENTION IN W AND BINARY W ALLOYS IRRADIATED WITH HIGH ENERGY FE IONS
48b
97
B. Unterberga1, M. Zlobinskia,*, G. De Temmermanb, C. Porosnicuc, D. Matveeva, G. Sergienkoa, S. Brezinseka, D. Nicolaia, M. Rasinskia, B. Spilkera, M. Freisingera, S. Möllera, Ch. Linsmeiera, C. P. Lunguc, P. Dincac
Analysis of fuel retention in Be layers by Laser-Induced Desorption (LID) 49a
98 Hai-Shan Zhou1,2 *, Lu Wang1,2, Hao-Dong Liu1,2, Xin Yang1, Guang-Nan Luo1,2
EFFECTS OF ION-INDUCED DESORPTION ON HYDROGEN ISOTOPE PERMEATION AND RETENTION IN WALL MATERIALS
49b
52
No. Author Abstract Title Poster Address
99 Joven J H Lim1* and George Fulton1 Irradiation Assisted Corrosion study of ITER-grade CuCrZr 50a
100 Teppei Otsuka1*, Natsuki Sawano1, Yuji Fujii1 Effect of rhenium contents on oxidation behaviors of tungsten-rhenium alloys 50b
101 Pablo Pérez1, Ángel Muñoz2, Paloma Adeva1, Miguel Ángel Monge2*
Influence of 1 and 5 wt.% TiC additions on the oxidation behaviour of pure tungsten 51a
102 P. Chakraborty1*, W. Krauss2, S -E. Wulf2, R.Tewari1, J. Konys2
Corrosion of Indian RAFM and EUROFER steel in Pb-Li loop PICOLO 51b
103 J. Jun, K. A. Unocic, M. Romedenne, and B. A. Pint COMPATIBILITY OF ALUMINA-FORMING STEEL IN FLOWING PbLi AT 600°-700°C WITH TEMPERATURE GRADIENTS
52a
104 Hao Yu1 *, Sosuke Kondo1, Ryuta Kasada1 Naoko Oono2, Shigenari Hayashi2, Shigeharu Ukai2
Influence of excessive oxygen addition on the oxidation resistance of Zr-added FeCrAl ODS ferritic steels
52b
105 Yichun Xu*, Yange Zhang, Xiangyan Li, Changsong Liu The dissolution corrosion of iron surfaces in liquid lithium and lead under a fusion environment
53a
106 Kodai Tabira1*, Takuya Shiratsuru1, Kenichi Hashizume1 Thermal diffusion of deuterium in nickel under temperature gradient 53b
107 Yen-Jui HUANG1*, Kousuke KAWAKITA2, Mahiro NONO2, Hideo Nakagawa2, Akihiko KIMURA1
Suppression of Stress Corrosion Cracking in Sensitized SUS304 and SUS316L in Fusion Relevant Environments
54a
No. Author Abstract Title Poster Address
108
Yang Li1, Max Boleininger2*, Christian Robertson1, Laurent Dupuy1, and Sergei L Dudarev2
FUNDAMENTAL REACTIONS BETWEEN PRISMATIC LOOPS IN STOCHASTIC DISLOCATION DYNAMICS
1a
109
Taku Ishida1,2*, Eiichi Wakai1,3, Shunsuke Makimura1,2, Masayuki Hagiwara2 Naritoshi Kawamura1,2, Makoto Teshigawara1,3, Shin-ichiro Meigo1,3 Patrick G. Hurh4, Kavin Ammigan4, Katsuya Yohehara4
NEW ASPECT OF RADIATION DAMAGE BEHAVIOR ON TITANIUM ALLOYS UNDER HIGH-INTENSITY PROTON BEAM EXPOSURE
1b
53
No. Author Abstract Title Poster Address
David J. Senor5, Andrew M. Casella5, Danny J. Edwards5 Dohyun Kim6, Nikolaos Simos6 Christopher J. Densham7, Michael Fitton7 The RaDIATE COLLABORATION
110
Pengfei Zheng1*, Jiming Chen1, Shouhua Sun2, Xiaoqiang Li3, Tielong Shen4, Yugang Wang5, Haiying Fu1, Ran Wei1, Liwen Zhang1, Xing Liu1, Engang Fu5, Yong Dai6
SELECTION OF ADVANCED FUSION MATERIALS FOR COMPREHENSIVE NEUTRON IRRADIATION TESTS USING SMALL SAMPLES IN CHINA
2a
111 Bing Bai1*, Roger Brun2, Yong Dai2 Positron annihilation spectroscopy of ODS Eurofer97
irradiated in spallation target at PSI 2b
112
Haoran Wang1*, Hao Yu1, Yuchen Liu1, Sosuke Kondo1, Ryuta Kasada1
Development of Fe-Mn-Al-Cr-C type austenitic steels for fusion application 3a
113 R. Coppola1*, P. He2, M. Klimenkov3
SMALL-ANGLE NEUTRON SCATTERING (SANS) CHARACTERIZATION OF 13.5 Cr OXIDE DISPERSION STRENGTHENED FERRITIC/MARTENSITIC STEEL FOR FUSION APPLICATIONS
3b
114
Jingjie Shen 1*, Takuya Nagasaka 1, Masayuki Tokitani 1, Takeo Muroga 1, Huilong Yang 2, Sho Kano 2, Hiroaki Abe 2
Comparisons of microstructures and mechanical properties between as-fabricated and recrystallized 12Cr ODS steel
4a
115
T. D. Shen1*, C. C. Du1, S. B. Jin2, Y. Fang3, Jin Li4, Shenyang Hu5, T. T. Yang1, Y. Zhang1, J. Y. Huang1, G. Sha2, Y. G. Wang3, Z. X. Shang4, X. Zhang4, B. R. Sun1, S. W. Xin1
STABLE NANOCRYSTALLINE AUSTENITIC STAINLESS STEELS UNDER HIGH TEMPERATURE AND INTENSE IRRADIATION
4b
116
J. Macías, M. Oñoro, V. de Castro, M. A. Auger, T. Leguey*
THERMAL STABILITY OF HOT CROSS ROLLED ODS FERRITIC STEELS 5a
117 Ty C Austin1*, Steven J Zinkle1 Additive Manufacturing of ODS FeCrAl via in situ
Oxidation 5b
118
Yanfen Li1*, Jingjie Shen3, Jiarong Zhang1, Guangquan Wang1,2, Feiyang Bao1,2, Wei Yan1, Quanqiang Shi1, Yiyin Shan1, Ke Yang1, Takuya Nagasaka3, Takeo Muroga3, Huilong Yang4, Sho Kano4, Hiroaki Abe4
THERMAL STABILITY BEHAVIOR FOR TWO MARTENSITIC AND FERRITIC ODS STEELS AT HIGH TEMPERATURE
6a
54
No. Author Abstract Title Poster Address
119
Huilong Yang1*, Sho Kano1, John McGrady1, Jingjie Shen2, Dongyue Chen1, Kenta Murakami3, Hiroaki Abe1
Effect of crystal orientation on hardness of Fe2+ ion irradiated 12Cr-ODS steel 6b
120
Caleb P. Massey1,2*, Sebastien N. Dryepondt2, David T. Hoelzer2, Steven J. Zinkle1,2
PROCESSING-MICROSTRUCTURE-PROPERTIES RELATIONSHIPS: A COMPARISON BETWEEN FERRITIC ODS FeCr AND ODS FeCrAl ALLOYS
7a
121 G. D. Samolyuk*, Y. N. Osetsky
DFT MODELING OF THE EQUILIBRIUM DISTRIBUTION OF POINT DEFECTS IN SYSTEMS WITH PRECIPITATES USING Fe-Y-O AS A REPRESENTATIVE CASE
7b
122
Tim Graening1*, Rainer Ziegler1, Harald Leiste1, Michael Rieth1
Novel design approach to develop an austenitic dual precipitation strengthened steel 8a
123
E. Visca1 ∗, J.H. You2, T. Barrett3, G. Dose4, M. Fursdon3, F. Gallay5, H. Greuner2, A. v. Müller2, M. Richou5, S. Roccella1
QUALIFICATION ROUTE FOR DIVERTOR TARGET CONCEPTS FOR EU-DEMO 8b
124
W. Chromiński1, Lukasz Ciupinski1, P. Bazarnik1, S. Markelj2, T. Schwarz-Selinger3
Evolution of dislocation structures and D retention under simultaneous W and D ions exposure in tungsten 9a
125
Daisuke Nishijima1*, Masayuki Tokitani2, Daisuke Nagata2, Marlene Patino1, Russell P. Doerner1
D retention properties of RAFM steels 9b
126
Mathias Jetter*, Marco Conte, Michael Mahler, Jarir Aktaa
Brittle Fracture Assessment for Tungsten and Tungsten alloy components 10a
127
Mauricio Gago*, Arkadi Kreter, Bernhard Unterberg and Marius Wirtz
Damage evolution in ITER-grade tungsten after simultaneous steady state plasma and high pulse number thermal shock tests
10b
128
M. Minissale1*, F. Ghiorghiu1, T. Aissou1, T. Angot1, G. De Temmerman2, R. Bisson1
Ammonia production and sticking on materials relevant to fusion reactors: tungsten and 316L stainless steel 11a
129
Gerald Pintsuk1*, Steffen Antusch2, Thorsten Loewenhoff1, Michael Rieth2, Marius Wirtz1
High heat flux and microstructural investigation of powder injection molded tungsten composites 11b
130 M. Rasinski*, A. Kreter, J.W. Coenen, Ch. Linsmeier Retarded recrystallization of tungsten due to deuterium
loading 12a
131
Chad M. Parish1*, Kun Wang1,2, Thomas Song1, Russell P. Doerner3, and Matthew J. Baldwin3
EFFECTS OF HELIUM EXPOSURE ON TUNGSTEN MECHANICAL BEHAVIOR 12b
55
No. Author Abstract Title Poster Address
132
Chad M. Parish1*, Kun Wang1,2, Russell P. Doerner3, Matthew J. Baldwin3, Fred W. Meyer1, and Mark E. Bannister1
THE INTERPLAY BETWEEN HELIUM PLASMA AND TUNGSTEN MICROSTRUCTURE IN PMI 13a
133
Massimo Zucchettia*, Raffaella Testonia, Stefano Segantina, Zachary Hartwigb, Dennis Whyteb Antonio Melia, Edoardo Andrea Pratoa,b
MATERIAL CHALLENGES AND RADIATION DAMAGE FOR THE ARC REACTOR 13b
134 J. Jun, M. Romedenne, and B. A. Pint
LIQUID METAL COMPATIBILITY WITH PLASMA-FACING COMPONENT MATERIALS
14a
135 Jiří Matějíček1*, Pavel Rohan2, Jakub Antoš2
W+CU AND W+NI COMPOSITES AND FGMS PREPARED BY PLASMA TRANSFERRED ARC CLADDING
14b
136
Y.C. Wu1,2,3,4*, X.Y. Tan1, W.J. Wang1, X. Zan1, X.Y. Zhu1, J.Q. Liu3, L.M. Luo1,2
Toughening Approaches and Mechanisms of Tungsten Materials for the Future Fusion Reactor 15a
137
Feng Ren1*, Wenjing Qin1, R. P. Doerner2, Yongqiang Wang3*, Huiqiu Deng4
Nanochannel W with enhanced radiation tolerance and He handling 15b
138
Myeong-Geon Lee1, Nam-Kyun Kim1, Ki-Baek Roh1, Gon-Ho Kim1*
Change of Tungsten Blister-generated Grain Orientation by Hydrogen Ion Incident Angle 16a
139
Kevin B. Woller1*, Felipe Bedoya1, Dennis G. Whyte1
STUDY OF MOLTEN SALT CAPILLARY POROUS SYSTEM AS FIRST WALL IN MAGNETIC FUSION PILOT PLANT
16b
140
Qiang. Li1*, Chunyi. Xie1, Zhen. Chen1, Wuqingliang. Peng1, Wangjing. Wang1, Jichao. Wang1, Xingli. Wang1, Qingran. Gao1, Xiang. Geng1, G.-N. Luo1
Creep Analysis of Cu Interlayer in W/Cu Flat-type Mock-ups under High Heat Flux of 20 MW/m2 17a
141 Mingyang Li, Pei Hu, Dong Liu, Yongqin Chang* Microstructure and mechanical properties of the
CuCrZrFeTiY alloy 17b
142
A. Muñoz1,2*, B. Savoini1,2, M.A. Monge1,2 and M. Eddahbi1
MICROSTRUCTURE AND MECHANICAL PROPERTIES OF HOT ROLLED ODS COPPER 18a
143
A. Rodriguez-Lopez1, M.A Monge1,2, B. Savoini1,2, A. Muñoz1,2 and P. Pérez3
EXPLORING CuCrFeVTi SYSTEM TO PRODUCE HIGH ENTROPY ALLOYS FOR HIGH HEAT FLUX APPLICATIONS
18b
144 Jeongwoo Heo1*, N. Hashimoto2 Development of F82H-W-Cu composites with a high
thermal conductivity 19a
56
No. Author Abstract Title Poster Address
145
R.E. Nygren1, D.L. Youchison2, J. R. Michael1, J. D. Puskar1, T.J. Lutz1
LIQUID METAL EMBRITTLELENT OF A Li-FILLED FERRITIC TARGET - IMPLICATIONS FOR FUSION COMPONENTS
19b
146
Nerea Ordás1,2*, Luis Portolés3, María Azpeleta1,2, José Ramón Blasco3, Mario Martinez3, Julia Ureña3, Iñigo Iturriza1,2
PROCESS DEVELOPMENT OF CuCrZr COMPONENTS VIA ELECTRON BEAM MELTING 20a
147
Ki-Baek Roh1*, Myeong-Geon Lee1, Nam-Kyun Kim1, Kyungmin Kim2 and Gon-Ho Kim1
Investigation of Macro Crack Enhanced by Grain Growthon Tungsten Divertor Monoblock at the Strike Point
20b
148 John R. Echols1*, A.L.Winfrey2 Evaluation of W surface damage over high heat flux
exposure range with the HELIOS device. 21a
149 D. Terentyev1, J.-H. You2, and N. Van Steenberge3 Development of pure chromium and Cr-10W for mid-
flux region PFCs for DEMO divertor 21b
150
A. Terra *, G. Sergienko, A. Kreter, Y. Martynova, M. Rasiński, M. Wirtz, Th. Loewenhoff, G. Pintsuk, D. Dorow-Gerspach, Y. Mao, J. W. Coenen, S. Brezinsek, B. Unterberg, and Ch. Linsmeier
Micro-structured tungsten, a high heat flux pulse proof material 22a
151
X.Y. Tan1*, W.J. Wang1, X. Chen3, L.M. Luo1,2, X. Zan1, X.Y. Zhu1, J.Q. Liu1, Y.C.Wu1,2,3,4
The Thermal Conductivity Behaviors and Its Influence Factors of Pure Tungsten with Different Statuses 22b
152
Pengqi Chen1,2*, Jigui Cheng1,2, Bangzheng Wei1,2
Study on preparation of functional grade W-Cu materials by a combustion-based method and its thermal properties 23a
153
Takuma Higashia*, Taichi Koyamaa, Takayuki Teraia and Juro Yagib
Nitrogen Concentration Dependence of Corrosion of SS316L in Liquid Lithium 23b
154
Saerom Kwon1*, Satoshi Sato1, Makoto Nakamura1, Masayuki Ohta1, ChangHo Park1, Makoto Oyaidzu1, Kentaro Ochiai1, Atsushi Kasugai1
CONCEPTUAL DESIGN OF BLANKET MATERIALS TEST MODULES FOR A-FNS 24a
155
Eiichi Wakai1*, Takuma Higashi2, Akihiro Suzuki2,3, Yuzuru Ito1, Hiroyasu Tanigawa4, Hiroo Nakamura1, Takayuki Terai2, Davide Bernardi5
Validation Tests of Lithium Target System of Accelerator Driven Irradiation Facility 24b
156 K. D. Weaver1*, J. D. McDuffee2, and L. L. Snead3* Current Status and Prospects for Fission Based Materials
Test Reactors for Fusion in the US 25a
157
Yuefeng Qiu1*, Fernando Mota2, Ulrich Fischer1, Alexandre Konobeyev1
Comparison of different DPA models for the irradiation of iron in IFMIF-DONES 25b
57
No. Author Abstract Title Poster Address
158
Arunodaya Bhattacharya*, David T. Hoelzer, Dalong Zhang1, Kun Wang, Josina W. Geringer, Kevin G. Field, Yutai Katoh
MICROSTRUCTURES OF MA957, 12YWT AND PM2000 ODS STEELS AFTER > 50 DPA NEUTRON IRRADIATIONS
26a
159
Matheus A Tunes1, Stephen E Donnelly1, Philip D Edmondson2
ACCELERATED RADIATION EFFECTS IN MAX PHASES AT HIGH TEMPERATURES 26b
160
Yao Li1*, Yajie Zhao1, Arunodaya Bhattacharya2, Jean Henry3, Steven John Zinkle1,2
Effect of Cr and C on dislocation loops in heavy ion irradiated ultra-high purity FeCr alloys 27a
161 Weilin Jiang*, David J. Senor
DIFFUSION OF HYDROGEN ISOTOPES AND MICROSTRUCTURE IN ION IRRADIATED LITHIUM ALUMINATE
27b
162
Dai Hamaguchi1, Masami Ando1, Hiroyasu Tanigawa1, Arunodaya Bhattacharya2, Kevin G. Field2, J. Wilna Geringer2, Yutai Kato2, Sho Kano3, Hiroaki Abe3
MICROSTRUCTURAL EVOLUTION OF F82H UNDER HIGH DOSE IRRADIATION 28a
163
M. Šćepanović, M.A. Auger*, T. Leguey, J. Macías, V. de Castro
Atom Probe Tomography analysis of dual ion beam irradiated ODS steel 28b
164
Chenxu Wang1, 2*, Rodney C. Ewing1, Yugang Wang2 Disorder in Mn+1AXn phases at the atomic scale 29a
165
Chenyang Lu1,2*, Yanwen Zhang3, Fei Gao1, Lumin Wang1
INFLUENCE OF CHEMICAL COMPLEXITY ON RADIATION EFFECTS: FROM PURE METAL TO HIGH ENTROPY ALLOY
29b
166
Naoyuki Hashimoto1*, Wei-Ying Chen2, Jien-Wei Yeh3
In-situ observation of radiation damage in FeCrNiMn high entropy alloys 30a
167
Akihiko Kimura1*, Jin Gao1, Kiyohiro Yabuuchi1, Eva Hasenhuetl2, Zhexian Zhang3 ORDERED DEFECT STRUCTURES IN BCC METALS 30b
168
Koichi Sato1*, Yohei Kondo1, Masakiyo Ota1, Masahira Onoue2, Masahiko Hatakeyama3, Satoshi Sunada3, Qiu Xu4, Yoshiyuki Watanabe5, Dai Hamaguchi5, Hiroyasu Tanigawa5
DEPENDENCE OF POSITRON ANNIHILATION LIFETIME OFVACANCY-TYPE DEFECTS ON HYDROGEN ATOMS IN METALS
31a
169
Ling Wang1, Arunodaya Bhattacharya2, David Martin3, Chad M. Parish2, Spencer Kropf3, Brian D. Wirth2,3, Steven J. Zinkle1,2,3*
Phase stability of coherent precipitates in dilute binary alloys after ion irradiation 31b
170
Yosuke Abe1*, Yuhki Satoh2, Nariaki Okubo1, Azusa Konno1
EFFECT OF ONE-DIMENSIONAL MIGRATION OF SELF- INTERSTITIAL ATOM CLUSTERS ON THEIR
32a
58
No. Author Abstract Title Poster Address
NUMBER DENSITY IN ALPHA-IRON UNDER ELECTRON IRRADIATION
171
Yoshiyuki Watanabe1*, Kazunori Morishita2, Masami Ando1 and Hiroyasu Tanigawa1
Microstructure correlation of RAFM steel under different irradiation fields: Reaction rate theory analysis 32b
172
Yajie Zhao1*, Arunodaya Bhattacharya2, Philip D. Edmondson2, Caleb Massey1, Jean Henry3, and Steven J. Zinkle1,2
DOSE RATE AND TEMPERATURE EFFECT ON IRRADIATION-ENHANCED ALPHA PRIME PRECIPITATION IN ULTRA-HIGH PURITY FeCr ALLOYS
33a
173 Yuta Ono1*, N. Hashimoto2, Wei-Ying Chen3 Mobility of point defects in CoCrFeNi-base High
Entropy Alloys 33b
174
Mitsuki Zushi1*, N. Hashimoto2, D. Hamaguchi3, Y. Watanabe3, H. Tanigawa3
Determination of grain boundary character in ferritic/martensitic steel F82H 34a
175
Zhiwei Hu1, MF Barthe1*, C Genevois-Mazellier1, B Decamps2, P Desgardin1, R Schaublin3
Damage induced in self irradiated tungsten as a function of its purity 34b
176
Amy Sarah Gandy1*, Alice Marcella Williams1, 2, Kai Kang3, Dhinisa Patel1, Jack Haley4, Russell Goodall1
Surface nano-structuring in High Entropy Alloys from He plasma irradiation 35a
177
Georg Holzner1*, Thomas Schwarz-Selinger1, Udo von Toussaint1, Stefan Elgeti1
Inductive heating based apparatus to revise the Frauenfelder data set for hydrogen diffusion in tungsten 35b
178
Yiqiang Wang1*, Andrej Turk2, Biao Cai3, Robert Dalglish4, Adam Washington4, Jan Hoffmann5, Elizabeth Surrey1, Mike Gorley1
Quantitative analysis of hydrogen trapping in ODS-EUROFER97 using small-angle neutron scattering 36a
179
Congyi Li1*, Xunxiang Hu2, Qiu Jie1, Yutai Katoh2, Brian Wirth1,2
INVESTIGATING THE DEPENDENCE OF MICROSTRUCTURE AND SURFACE ORIENTATION ON THE HELIUM DESORPTION BEHAVIOR FROM TUNGSTEN
36b
180 Duc Nguyen-Manh1,* and Sergei L. Dudarev1
RELAXATION VOLUMES OF IRRADIATION-INDUCED DEFECTS CONTAINING HELIUM AND NOBLE GASES: A SYSTEMATIC TREND PREDICTED BY FIRST-PRINCIPLES MODELLING
37a
181 Shijun Zhao, Da Chen, and Ji-Jung Kai Assessment of He behavior in a NiCoFeCr High-Entropy
Alloy 37b
182
Vladimir Krsjak1*, Jarmila Degmova1, Jana Simeg-Veternikova1, Stanislav Sojak1 and Vladimir Slugen1
EXPERIMENTAL COMPARISON OF THE (ODS)EUROFER STEELS IMPLANTED BY HELIUM 38a
59
No. Author Abstract Title Poster Address
IONS AND IRRADIATED IN SPALLATION NEUTRON TARGET
183 Lei Peng1*, Jingyi Shi2, Liuliu Li1, Yong Dai3 Molecular dynamics simulation on barrier strength of
irradiation induced helium bubble in RAFM steels 38b
184
S. Davies1*, A. Hollingsworth1, A. De Backer1, M.Yu. Lavrentiev1, R. Smith1, Z. Kollo1, A. Davies1, A. Widdowson1, K. Heinola2, K. Mizohata2, J. Likonen3, A. Baron-Wiechec1, I. Jepu4, J. Hess1, E. Meslin5, A. Morellec5, M.-F. Barthe6, K. Abraham1, G. Papadopoulos1
NEW RESULTS FROM A STUDY OF CHANGES IN HYDROGEN ISOTOPE RETENTION AND RELEASE FROM FUSION RELEVANT MATERIALS DUE TO EVOLUTION OF THE MICROSTRUCTURE
39a
185
Hirokazu Ando1*, Masato Yamawaki2, Tetsuya Hirade3, Xunxiang Hu4, Masafumi Akiyoshi1
ADVANCED FAST PALS SYSTEM FOR IRRADIATED SINGLE MINIATURE SPECIMEN 39b
186
Jarmila Degmova1*, Vladimir Krsjak1, Alzbeta Kubiritova1, Adam Jakabovic1, Stanislav Sojak1 and Martin Petriska1
CDBS CHARACTERIZATION OF ADVANCED STEELS FOR FUSION APPLICATIONS 40a
187
Andrew J. London1*, Chris Hardie1, Joven J. H. Lim1, Rob Bamber1 2
RAPID INVESTIGATION OF IRRADIATION TEMPERATURE SENSITIVITY WITH CHARGED PARTICLES
40b
188
Lijuan Cui1*, Yong Dai1, Stephan Gerstl2, Xing Huang2, Manuel Pouchon1, Robin Schäublin2
Irradiation induced Segregation analyses in grain boundaries and phase boundaries by using APT/TEM in F82H steels after irradiated in SINQ
41a
189 Lijuan Cui1, Yong Dai1*, Stephan Gerstl2 Systematically indexing APT mass spectrum of ODS and
RAFM steels after irradiation in SINQ 41b
190
M. Roldán1*, F. J. Sánchez1, P. Galán2, A. Gómez-Herrero3
ON THE STRAIN EFFECT IN DISLOCATION LOOPS PRODUCED BYSELF-ION IRRADIATION TO EMULATE IN-SERVICE REACTOR CONDITION.
42a
191
Takaaki Koyanagi1*, Yutai Katoh1, Christian Petrie1, Gyanender Singh2, Xunxiang Hu1, José Arregui-Mena1, Christian Deck3, Kurt Terrani1
RESPONSE OF SiC COMPOSITES TO NEUTRON-IRRADIATION WITH A HIGH HEAT FLUX: EXPERIMENTS AND MODELING
42b
192
Azusa Konno*1, Yojiro Oba1, Aki Tominaga1, Satoshi Morooka1, Naoko H. Oono2, Naoyuki Hashimoto2, Shigeharu Ukai2, Kenji Ohwada3, Ryuhei Motokawa1, Takayuki Kumada1, Takahisa Shobu1, Shinichiro Yamashita1
NOVEL QUALITATIVE EVALUATION METHOD OF MICROSTRUCTURE IN ODS ALLOY BY ANOMALOUS SMALL-ANGLE X-RAY SCATTERING TECHNIQUE
43a
60
No. Author Abstract Title Poster Address
193
Dalong Zhang1*, Maxim Gussev2, Samuel A. Briggs3, Philip D. Edmondson2, Yukinori Yamamoto2, and Kevin G. Field2
Deformation Mechanisms in a Neutron Irradiated FeCrAl Alloy and its Weldment 43b
194
Edgar Leon-Gutierrez1*, Rafael Vila1, JET Contributors2++See the author list of “X. Litaudon et al 2017 Nucl. Fusion 57 102001”
SYSTEM OPTIMIZATION AND OFF-LINE CHARACTERIZACION OF FUSED SILICA FIBERS FOR IN-SITU MEASUREMENTS IN THE NEXT TRITIUM-TRITIUM AND DEUTERIUM-TRITIUM JET’S CAMPAINGS
44a
195 Maosheng Li*, Jing Xia, Hongming Li Micromechanical Investigations Radiation Hardening
Effect of FCC Metals 44b
196
Lorenzo Malerba1*, Mar.a J. Caturla2, Ermile Gaganidze3, Cornelia Heintze4, Milan Konstantinovic5, Pär Olsson6, David Rodney7, Ana M. Ruiz8, Marta Serrano1, François Willaime9
MODELLING ION IRRADIATION AND SLIP LOCALISATION IN FERRITIC-MARTENSITIC STEELS: THE FUSION-FISSION CROSS-CUTTING M4F PROJECT
45a
197
Fernando Mota1*, Christophe J. Ortiz1, Rafael Vila1, Angel Ibarra1
NEW PRIMARY DISPLACEMENT DAMAGE CALCULATION METHODS FOR INTERCOMPARISON OF IRRADIATION EXPERIMENTS
45b
198
Mingjie Zheng1*, Wenyi Ding1, Weitao Cao1, Shenyang Hu2, Qunying Huang1, Shaojun Liu1, Xiaodong Mao1, Yican Wu1, FDS Team1
QUICK SCREENING DESIGN OF MULTI-PRINCIPAL ELEMENT ALLOYS FOR NEW GENERATION OF FUSION STRUCTURAL MATERIALS
46a
199
Jingming Shi1*, Naoyuki Hashimoto2, Shigehito Isobe2
EFFECT OF H AND HE ON INCOHERENT FE/W INTERFACE: A DFT STUDY 46b
200
Wenyi Ding*, Mingjie Zheng, Chao Wang, Jingping Xin, Qunying Huang, FDS Team
EFFECT OF NEUTRON ENERGY SPECTRUM ON MATERIAL IRRADIATION DAMAGE 47a
201
Emil Levo1*, Fredric Granberg1, Kai Nordlund1, Flyura Djurabekova,1,2
RADIATION TOLERANCE OF EQUIATOMIC MULTICOMPONENT ALLOYS 47b
202
Yangchun Chen1, Lixia Liu2, Jun Fu1, Wangyu Hu2, Fei Gao3, 2, Huiqiu Deng1*
DEVELOPMENT OF INTERATOMIC POTENTIALS FOR BINARY W-X (X = TA, V, MO, NB, RE) ALLOYS
48a
203
Padhraic L. Mulligan*, Christian M. Petrie, Lauren Garrison, Takaaki Koyanagi, Josina W. Geringer, Yutai Katoh
THERMAL AND STRUCTURAL MODELING OF CAPSULES TO 48b
61
No. Author Abstract Title Poster Address
IRRADIATE NONSTANDARD MATERIALS FOR FUSION APPLICATIONS
204 Taira Okita1 , Sho Hayakawa2, Mitsuhiro Itakura3 Effects of applied strain on defect formation through
collision cascade in FCC metals 49a
205
Kota Ninomiya1, Sutatch Ratanaphan2, Sho Hayakawa1, Mitsuhiro Itakura3, Taira Okita4
MD simulations to evaluate a stable configuration of a vacancy cluster in FCC metals and its interaction with an edge dislocation
49b
206
Lukas Vlcek1*, German Samolyuk2, James Morris1,2 and Yuri Osetsky2
A NEW APPROACH FOR INTERATOMIC FORCES TRAINING FOR MODELING HIGH-TEMPERATURE PHENOMENA IN W-Re SYSTEMS
50a
207 Liuliu Li1, Jingyi Shi2, Lei Peng1*, Wei Jiang1
Atomistic simulation on formation and evolution of heliumvacancy cluster in bcc Fe
50b
208
Jingyi Shi1*, Lei Peng2, Liuliu Li2, Fei Gao3, Jianjun Huang1, Jiangang Li1, 4
Molecular Dynamics Study on Effects of GB Characteristics on Helium Embrittlement 51a
209
Xunxiang Hu1*, Lizhen Tan1, David T. Hoelzer1, Yutai Katoh1, Guiyang Huang2, Ze Chen2,3, Brian D. Wirth2
DEUTERIUM RETENTION IN ADVANCED STEELS FOR FUSION STRUCTURAL APPLICATIONS 51b
210
Akito Ipponsugi1*, Kazunari Katayama1, Tsuyoshi Hoshino2
Li mass loss and structure change due to long time heating in hydrogen atmosphere from Li2TiO3 with excess Li
52a
211
Kazunari Katayama1*, Naoko Ashikawa2,3, Takumi Chikada4
MASS TRANSFER AT THE INTERFACE BETWEEN STAINLESS STEEL AND SUPERCRITICAL CARBON DIOXIDE
52b
212
Kazuki Nakamura1*, Hikari Fujita2, Jan Engels3, Masayuki Tokitani4, Yoshimitsu Hishinuma4, Kiyohiro Yabuuchi5, Sho Kano2, Takayuki Terai2, Wataru Inami1, Yoshimasa Kawata1, Takumi Chikada1
EFFECTS OF HELIUM IMPLANTATION WITH HEAVY ION IRRADIATION ON DEUTERIUM PERMEATION IN YTTRIUM OXIDE COATING
53a
213
Takumi Chikada1*, Hikari Fujita2, Kazuki Nakamura1, Keisuke Kimura1, Teruya Tanaka3, Wataru Inami1, Yoshimasa Kawata1
DEUTERIUM PERMEATION MECHANISM IN CERAMIC COATINGS UNDER GAMMA-RAY IRRADIATION
53b
214
Hongtao Huang, Jianpin Zheng, Shuo Ding,Weijun Wang,Zheng Zhang
Effect of Oxide Film on the Deuterium Permeation Behavior of 430 Stainless Steel 54a
62
No. Author Abstract Title Poster Address
215
Hao Yang, Xiang Ji, Siwei Zhang, Wei Wang*, Qunying Huang, FDS Team
SYNTHESIS AND CHARACTERISTIC OF BIOMIMETIC GRAPHENE OXIDE/Al2O3 COMPOSITE TRITIUM PERMEATION BARRIER
54b
216
A. Houben1*, M. Rasiński1, L. Gao2, Ch. Linsmeier1, and WP PFC contributors Tungsten Nitride as Tritium Permeation Barrier 55a
217
Yu-Ping Xu*, Yi-Ming Lyu, Xiao-Chun Li, Hai-Shan Zhou, Guang-Nan Luo
Repair the damaged tritium permeation barrier by cold spray 55b
218
Wei Mao1*, Wilde Markus2, Shohei Ogura2, Takumi Chikada3, Katsuyuki Fukutani2, Hiroyuki Matsuzaki4,5, Takayuki Terai1,5
H isotope behaviors in rutile TiO2(110) surface 56a
219
Hisashi Serizawa1*, Jun Shimaoka2, Yuji Sato3, Takahiro Hara2, Masahiro Tsukamoto1, Hiroyasu Tanigawa4
DEVELOPMENT OF COPPER DEPOSITION ON TUNGSTEN WITH BLUE AND INFRARED DIODE LASERS
56b
220
Teresa Hernández1*, Fernando J. Sánchez1, Eric Platacis2, Kalvis Kravalis2
COATINGS COMPATIBILITY WITH Pb-17Li FLOW AND MAGNETIC FIELD 57a
221
Sarah Stevenson1*, Mehdi Balooch1, Andrew Scott1, Peter Hosemann1,2, Frances Allen1,2, and Saryu Fensin3
CHARACTERIZATION OF HELIUM IMPLANTED SINGLE CRYSTAL TITANIUM
57b
222
Sarah Stevenson*, Peter Hosemann1, Lee Bernstein1,2, Andrew Voyles1,2, and Saryu Fensin3
DEEP ION BEAM IMPLANTATION AT THE 88-INCH CYCLOTRON 58a
223
Enrique Martínez1*, Nithin Mathew1, Danny Perez1, Giacomo Po2, Jaime Marian3 Overdamped Langevin Dislocation Dynamics 58b
224 Peng Song1*, Kiyohiro Yabuuchi1, Akihiko Kimura1 Phase stability under ion-irradiation in ODS ferritic steels
strengthened by different sorts of oxides 59a
225
Jin Gao1*, Kiyohiro Yabuuchi1, Peng Song1, Akihiko Kimura1, Yuuki Yamasaki2, Kan Sakamoto3, Shinichiro Yamashita4
COMPARISON BETWEEN NEUTRON AND SELF-ION IRRADIATION EFFECTS ON ODS Fe−12Cr−6Al AT 290 °C
59b
226
Hyoung Chan Kim1*, Kyungmin Kim1, Nojun Kwak2, Yeonju Oh2, Heung Nam Han2, S.-H. Son2, Eunnam Bang1, Heekyung Choi1, Suk-Ho Hong1
Comparison of material properties of Tungsten fabricated by spark plasma sintering in Tokamak plasma exposure and Heat flux test
60a
227
Timofey Frolov1*, Wahyu Setyawan2, Richard J. Kurtz2, Jaime Marian3, Artem R. Oganov4, Tomas Oppelstrup1, Qiang Zhu5 and Robert E. Rudd1
STRUCTURES AND TRANSITIONS IN TUNGSTEN GRAIN BOUNDARIES AND THEIR ROLE IN THE
60b
63
No. Author Abstract Title Poster Address
ABSORPTION OF POINT DEFECTS
No. Author Abstract Title Poster Address
228 Kai Nordlund1*, Flyura Djurabekova1, Gerhard Hobler2, K. Schlueter3,4 and M. Balden3
MAJOR EFFECT OF CRYSTAL ORIENTATION ON SPUTTERING 1a
229 Benjamin P Eftink1*, Tobias J Romero1, Matthew E Quintana1, David T Hoelzer2, Cheng Xu3, Tarik A Saleh1, Stuart A Maloy1
Shear Punch Testing of BOR60 Irradiated 14YWT and HT9 1b
230 David T. Hoelzer*, Ian A. Stinson and Caleb P. Massey
INVESTIGATING THE BENEFIT OF 1%W ON THE MICROSTRUCTURE AND MECHANICAL PROPERTIES OF ODS Fe-10Cr ALLOYS
2a
231 A. Issaoui1,2, J. Ribis1, J. Malaplate1, , A. Legris2 Characterization of Microstructural Evolution of ODS STEELS after LONG Thermal Aging and Ion Radiations 2b
232 Hiroshi Oka*, Takashi Tanno, Yasuhide Yano, Satoshi Ohtsuka, Takeji Kaito, Yoshiaki Tachi
Microstructural stability of ODS steel after long-time creep test 3a
233 Jian Feng1, Qingzhi Yan1* , Xiaoxin Zhang2* THERMODYNAMIC MODEL OF MICROSTRUCTURE FOR ODS STEELS FABRICATED BY VACUUM INDUCTION MELTING & CASTING TECHNIQUE
3b
234 Yingxue Chen1*, Xiaoxin Zhang2 and Qingzhi Yan1
HIGH TEMPERATURE MECHANICAL PROPERTIES OF FERRITIC/MARTENSITIC CNS-1-ODS STEEL FABRICATED BY VACUUM MELTING AND CASTING METHOD
4a
235 Zhongwei Jin1, Yina Huang1*, Laima Luo1, Yucheng Wu1,2
The effect of Cr in the nucleation and dispersion of Y2O3 in Fe-Cr ODS alloy 4b
236 P. Fernández(1)*, J. Hoffmann(2), M. Rieth(2), and A. Gómez-Herrero(3)
Secondary phases characterization on 9%Cr Advanced Steels by STEM and EELS 5a
237 P. Fernández(1)*, A. Gómez-Herrero(2), N. Ordás(3,4), D. Pazos(3,4) TEM characterization on ODS produced by STARS route 5b
64
No. Author Abstract Title Poster Address
238 D. Dorow-Gerspach*, J.W. Coenen, Th. Loewenhoff, G. Pintsuk, A. Terra, M. Wirtz
Realizing thermal shock proof micro-structured tungsten components 6a
239 Sosuke Kondo1*, Takaaki Koyanagi2, Tatsuya Hinoki3, Yutai Katoh2
SHEAR STRENGTH OF IRRADIATED W/SIC INTERPHASES 6b
240 G. D. Samolyuk*, Y. N. Osetsky STABILITY OF PHASES IN THE W-Re-Os SYSTEM UNDER IRRADIATION 7a
241
Saša Novak1, Petra Jenuš1, Matej Kocen1,2, Anže Abram1, Andreja Šestan Zavašnik2,3, Sabina Markelj4, Mitja Kelemen4, Andrei Galatanu5, Elena Tejado6, Jose Ygnacio Pastor6, G. Pintsuk7
WC as reinforcement for tungsten or matrix material for DEMO divertor 7b
242 Tomohito Tsuru1,2*, Tomoaki Suzudo3, Mitsuhiro Itakura3, Masato Wakeda4, Shigenobu Ogata5,2
A numerical description of the motion of screw dislocation around solutes in tungsten alloys 8a
243
Elizabeth A.I. Ellis1*, Michael M. Kirka1, Chase B. Joslin1, Lauren M. Garrison1, Christopher Ledford2, Sullivan Figurskey2, Chris Rock2, Timothy Horn2, Yutai Katoh1, and Ryan R. Dehoff1
ADDITIVE MANUFACTURING OF MODEL TUNGSTEN FUSION COMPONENTS 8b
244 M. E. Alam*, G. R. Odette
ON THE REMARKABLE FRACTURE TOUGHNESS OF W-Ni-Fe TUNGSTEN HEAVY ALLOYS: CHARACTERIZING AND EXPLOITING NEW PROCESS ZONE DUCTILIZING TOUGHENING MECHANISMS
9a
245 Zhisheng Yan1, Yina Huang1*, Laima Luo1, Yucheng Wu1,2
Microstructural comparison of effect of Y2O3 and TiC additions in tungsten 9b
246 Carsten Bonnekoh1*,,Harald Leiste1, Jan Hoffmann1, Andreas Hoffmann2, Jens Reiser1
KEY FACTORS FOR ROOM TEMPERATURE DUCTILITY OF MONOLITHIC TUNGSTEN SHEETS 10a
247 Philipp Lied1*, Wolfgang Pantleon2, Carsten Bonnekoh1, Michael Dürrschnabel1, Andreas Hoffmann3, Jens Reiser1
Comparison of K-doped and pure cold rolled tungsten sheets: As-rolled condition and recrystallization behavior after isochronal annealing at different temperatures
10b
248
Irina L. Tazhibaueva1,2*, Timur V. Kulsartov3, Yuriy V. Ponkratov1, Yuriy N. Gordienko1, Zhanna A. Zaurbekova1,3, Yevgen V. Chikhray3, Mazhyn K. Skakov3, Giuseppe Mazzitelli4
REACTOR EXPERIMENTS AND MODELING OF HYDROGEN ISOTOPES INTERACTION WITH LITHIUM CPS
11a
249 Yuta Toramoto1*, N. Hashimoto2, H. Noto3 Fabrication of Fe-based composite material with high thermal conductivity 11b
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No. Author Abstract Title Poster Address
250 T. Zhang, Z. M. Xie Ultra-fine grained and nano-grained bulk W-ZrC alloy as plasma-facing components in fusion devices 12a
251 Zhe Chen1*, Xiang Liu1, Laizhong Cai1, Yu Li2, Thomas Morgan2, Hans van Eck2, Youyun Lian1, Fan Feng1, Jianbao Wang1, Yang Tan1
Response of W-Y2O3 alloy and CVD-W coating exposed to ELMy-like hydrogen plasma at Magnum-PSI 12b
252 Li Yang1*, Brian D. Wirth1,2 FIRST-PRINCIPLES STUDY OF HYDROGEN BEHAVIOR NEAR W/WC INTERFACES 13a
253 Li Yang1*, Zack J. Bergstrom1, Brian D. Wirth1,2
FIRST-PRINCIPLES STUDY OF HELIUM EFFECT ON HYDROGEN TRAPPING IN BULK AND NEAR SURFACES OF TUNGSTEN
13b
254 M. Minissale1,*, A. Durif2, T. Vidal3, P. Hiret3, J. Faucheux5, M. Lenci4, G. Kermouche4, Y. Pontillon5, M. Richou2, and L. Gallais3
A high power laser facility to submit plasma facing materials to extreme heats loads 14a
255 Eric Lang1*, Lauren Garrison2, Nathan Reid1, Xunxiang Hu2, Jean Paul Allain1
Surface Chemistry and Morphology Response of High-Temperature Ceramics to Low Energy, High Temperature D/He Irradiation
14b
256
Michael J. Simmonds1*, Russell P. Doerner1, Peihao Sun2, Siegfried H. Glenzer2, Phillip Heimann2, Qianran Yu3, Jaime Marian3, George R. Tynan1
Characterization of Post-Damage Defect Annealing in Heavy Ion Irradiated Tungsten by X-Ray Diffuse Scattering
15a
257 Sergey Pestchanyi1*, Francesco Maviglia2 SIMULATION OF THE FIRST WALL SHIELDING DURING UPWARD VDE IN DEMO 15b
258 Yini Lv1, Min Pan*1, Kaige Hu*2, Zelin Cao2, Shulong Wen1, Zheng Huang3, Yong Zhao1
THE STUDY OF W ELEMENT EFFECCT ON VACANCY CLUSTER BEHAVIOR IN Ta-W ALLOY 16a
259 Edward Gao 1 , Warren Nadvornick 1 , Russ Doerner 2 , Brian Williams 3 , and Nasr M Ghoniem 1
MULTISCALE MODELING AND EXPERIMENTAL VALIDATION OF HELIUM BUBBLE FORMATION AND SPUTTERING EROSION IN MICRO-ENGINEERED TUNGSTEN
16b
260 Miao Qu1*, Fanhang Kong1, Sha Yan1,Jianming Xue1, Yugang Wang1
Comparison of cracking behaviors on pure tungsten induced by different transient heat loads 17a
261 L.M. Luo1,3*, Y.F. Zhou1, X.Y. Tan1, Y. Xu1,3, X. Zan1,3, Q. Xu2, K. Tokunaga4, X.Y. Zhu1,3, Y.C. Wu1,3,5*
Dual-Effects from Thermal Shock and Helium Irradiation on W-TiC Composites 17b
66
No. Author Abstract Title Poster Address
262 Owais Ahmed Waseem1, 2*, Kevin Woller2, Dennis Whyte2, and Ho Jin Ryu1
Irradiation Resistance of High-Entropy Alloy-based Fusion Plasma Facing Material 18a
263 N. Catarino1, Luis C. Alves2, M. Dias1, Nuno P. Barradas2, Sander van Til3, Oxidation behaviour of neutron irradiated Be pebbles 18b
264 Jae-Hwan Kim, Masaru Nakamichi MECHANICAL STRENGTH OF BERYLLIDE PEBBLES AS ADVANCED NEUTRON MULTIPLIERS 19a
265 Keisuke Mukai,1* Ryuta Kasada,2 Kiyohiro Yabuuchi,1 Satoshi Konishi,1 Jae-Hwan Kim,3 and Masaru. Nakamichi3
Chemical state analysis of steamed Be12V beryllides by soft X-ray emission spectroscopy 19b
266 Ramil Gaisin1*, Vladimir Chakin1, Rolf Rolli1, Harald Leiste1, Aniceto Goraieb2, Pavel Vladimirov1
EFFECT OF HOT ISOSTATIC PRESSING TEMPERATURE ON MICROSTRUCTURE AND PROPERTIES OF HOT-EXTRUDED Be-Ti COMPOSITES
20a
267 Taotao jin*, Hongguang Yang, Shanshan Liu, Changshui He, Xiaoming Yuan, Qin Zhan
Study on the fabrication and properties of the lithium orthosilicate pebbles by improved gel-casting method 20b
268 Yuichi Furuyama, Masaaki Yamamoto, Yuma Akita, Tsubasa Takeda, Hiroaki Samata, Akira Taniike
CO2 absorption characteristics of a blanket candidate material Li2TiO3 under moist air exposure 21a
269 Megha Sanjeev*, Samuel T. Murphy Thermal Conductivity of Li2TiO3 by Atomistic Simulation 21b
270 Nicola Helfer1*, Jens Bröder2, Hans Rudolf Koslowski1, Christian Linsmeier1
Phase Stability of Beryllium-Titanium Intermetallic Compounds 22a
271 Yi-Hyun Park1*, Jongil Kim1, Mu-Young Ahn1, Youngmin Lee1, Seungyon Cho1
MAXIMUM OPERATING TEMPERATURE FOR LI2TIO3 PEBBLE BED BY SINTERING PHENOMENON
22b
272 Philip D Edmondson RADIATION EFFECTS IN HIGH TEMPERATURE SUPERCONDUCTORS: CURRENT PROGRESS AND PERSPECTIVES
23a
273 Naoko Ashikawa1,2*, Toshikio Takimoto3, Akira Tonegawa3, Yoshihito Matsumura3, Kazunari Katayama4
Detection of permeated hydrogen isotopes into plasma facing material using combined specimen with palladium and titanium
23b
274 Chang-An CHEN1*, Zhanlei WANG1, Xin Xiang1, Guangda Lu1, Chunjing Li2, Yongjin Feng3
Research Progress on Tritium Compatibility Issues for China RAFM Steels to Be Served as the Tritium Breeding Blanket Structure Material in CFETR
24a
275 Milan Zmitko1*, Noel Thomas2, Laurent Forest3, Laurence Cogneau4, Yves Poitevin5
Current achievements and future perspectives in development, standardization and qualification of 24b
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No. Author Abstract Title Poster Address
fabrication technologies used for the European ITER Test Blanket Modules
276 Arkady Serikov1*, Luciano Bertalot2, Ulrich Fischer1, Dieter Leichtle1
TRANSMUTATION EFFECTS IN MATERIALS FOR ITER DIAGNOSTICS 25a
277
Xiang Chen1*, Arunodaya Bhattacharya1, Tim Graening2, Logan N. Clowers1, Mikhail A. Sokolov1, Josina W. Geringer1, Kory D. Linton1, Yutai Katoh1, Michael Rieth2
POST-IRRADIATION EVALUATION OF EUROFER97 FRACTURE TOUGHNESS USING MINIATURE MULTINOTCH BEND BAR SPECIMENS
25b
278
Josina W. Geringer*, Padhraic L. Mulligan, Richard Howard, Nesrin Cetiner, Christian M. Petrie, Joel L. McDuffee, Kevin Field, Yutai Katoh
HFIR IRRADIATION ENGINEERING FOR FUSION MATERIALS 26a
279
Josina W. Geringer*, Xiang Chen, Philip Edmondson, Xunxiang Hu, Hsin Wang, Anne Campbell, Arunodaya Bhattacharya, Kory Linton, Yutai Katoh
RECENT ENHANCEMENT OF ORNL PIE CAPABILITIES 26b
280 Andres Morell-Pacheco*, Laura Hawkins, Hyosim Kim, Jonathan Gigax, Frank A. Garner, and Lin Shao
MAPPING OF SWELLING AND HARDNESS OF 316L AS A FUNCTION OF STRESS THROUGH A COMBINATION OF ION IRRADIATION AND A THREE-POINT BENDING TECHNIQUE
27a
281 Alexander Valentin Brabänder, Hans-Christian Schneider, Marc Kamlah
An Advanced Characterization Method of Ductile-to-brittle-transition-temperature of Neutron-irradiated Structure Materials
27b
282 Michael Mahler*, Stephane Fessi, Jarir Aktaa Simplified Ductile Approach for fracture-mechanical SSTT and its application to Eurofer97 28a
283 David Andres1*, Mike Gorley1, Elizabeth Surrey1 APPLICATION OF THE SMALL PUNCH TESTING TECHNIQUE ON FUSION MATERIALS 28b
284 Richard H. Howard*, Ryan C. Gallagher, Josina W. Geringer, Yutai Katoh
USING SURFACE RESPONSE METHODS TO RAPIDLY AND EFFICIENTLY DESIGN HFIR FUSION MATERIALS IRRADIATION CAPSULES
29a
285 Takuya Yamamoto*, Soupitak Pal and G. Robert Odette
DEVELOPING UNIFIED MICROHARDNESS - TENSILE – NANOINDENTATION RELATIONS TO 29b
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No. Author Abstract Title Poster Address
TRUE STRESS-STRAIN CONSTITUTIVE PROPERTIES
286 Kurt Terrani* ADVANCED MANUFACTURING FOR NUCLEAR ENERGY SYSTEMS: OPPORTUNITIES FOR FUSION ENERGY
30a
287 J. Aktaa*, M. Walter, Matthias Kolb, R. Knitter Assessment of the chemical compatibility between EUROFER and ceramic breeder with respect to fatigue lifetime
30b
288 A.F. Rowcliffe*, C.E. Kessel, Y. Katoh MATERIALS-DESIGN INTEGRATION FOR THE NEXT PHASE OF FNSF DESIGN STUDIES 31a
289 Simon Heuer*, Jan W. Coenen, Gerald Pintsuk, Christian Linsmeier
Ageing behavior of functionally graded iron/tungsten materials, used as stress-relieving interlayers in tungsten-steel joints
31b
290 Vladimir Vojtech*1, Robin Schäublin1, Dongsheng Song2, Rafal Dunin-Borkowski2, Jörg F. Löffler1
Relationship between radiation-induced dislocation loops and the local magnetic field in Fe(Cr) 32a
291 John Echols1*, Lauren M. Garrison1, Yutai Katoh1, Masafumi Akiyoshi2
ELECTRICAL RESISTIVITY OF IRRADIATED TUNGSTEN 32b
292 S. Agarwal1, C. Li1, Y-Ru Lin1, R. Stoller2, S. J. Zinkle1,2
On using SRIM for correctly calculating dpa: Quick Kinchin-Pease versus Full-cascade option 33a
293 Yuta Ono1*, N. Hashimoto2, Wei-Ying Chen3 Mobility of point defects in CoCrFeNi-base High Entropy Alloys 33b
294 Jingping Xin1,2, *, Qunying Huang1, Yong Dai2, FDSTeam1
NANOSCALE DEFECTS AND ITS EFFECT ON PROPERTIES OF CLAM STEEL UNDER HIGH ENERGY PROTON AND SPALLATION NEUTRON MIXED SPECTRUM IRRADIATION
34a
295 Pär Olsson1*, Timofiy Lukinov1, Charlotte Becquart2, Rebecca Alexander2, Zoi Kotsina3, Michal Axiotis3, George Apostolopoulos3
Coupled theoretical and experimental determination of residual resistivity for defects in fusion reactor materials 34b
296 Sana Cao1*, Qing Peng1, Brian Wirth2 , Fei Gao1 Modeling point defect cluster absorption bias of Cavities in FeCr Alloys 35a
297 Jesper Byggmästar1*, Ali Hamedani1, Kai Nordlund1, Flyura Djurabekova1
MACHINE-LEARNING INTERATOMIC POTENTIALS FOR RADIATION DAMAGE IN BCC METALS 35b
69
No. Author Abstract Title Poster Address
298 Yuri Osetsky DYNAMICS OF INTERSTITIAL DEFECTS IN TUNGSTEN-RHENIUM ALLOYS 36a
299 Robert E. Rudd1*, Timofey Frolov1 and Jaime Marian2 TUNGSTEN GRAIN BOUNDARY MOBILITY 36b
300 Masafumi Akiyoshi1, Lauren M. Garrison2, Josina W. Geringer2, Hsin Wang2, Akira Hasegawa3, Syuhei Nogami3 and Yutai Katoh2
THERMAL DIFFUSIVITY OF IRRADIATED TUNGSTEN ANDTUNGSTEN-RHENIUM ALLOYS 37a
301 Arunodaya Bhattacharya1*, Xiang Chen1, Josina W. Geringer1, Tim Graening2, Yutai Katoh1, Michael Rieth2
MICROSTRUCTURE AND PROPERTY DEGRADATION OF EUROFER97 IN NON-STANDARD METALLURGICAL CONDITIONS
37b
302 Yeonju Oh1,*, Nojun Kwak1, Ki-Baek Roh2, Gon-Ho Kim2, and Heung Nam Han1
Microstructure dependence on the nano-mechanical properties of deuterium irradiated tungsten 38a
303 S Dellis1, Xiazi Xiao2, A. Bakaev3, S. Krimpalis1, K. Mergia1,*, S. Messoloras1 and D. Terentyev3
Mechanical properties of neutron irradiated single crystal tungsten studied by non-destructive mechanical testing and FEM modelling
38b
304
Lauren M. Garrison1*, Yutai Katoh1, Wilna Geringer1, Masafumi Akiyoshi2, Takeshi Miyazawa3, Xiang Chen1, John Echols1, Tim Graening1, Akira Hasegawa3, Tatsuya Hinoki4, Xunxiang Hu1, Takaaki Koyanagi1, Eric Lang1, Chad Parish1, Nathan Reid1, Hsin Wang1
MECHANICAL AND THERMAL PROPERTY CHANGES IN IRRADIATED TUNGSTEN 39a
305 Atsushi Kiyohara1*, Koichi Sato1, Hayato Yamashita1, Masahira Onoue2, Qiu Xu3, Kiyohiro Yabuuchi4, Akihiko Kimura4, Ryuta Kasada5
EFFECT OF HYDROGEN ON THE SURFACE HARDNESS IN ION-IRRADIATED TUNGSTEN 39b
306 Shuhei Nogami1*, Akira Hasegawa1, and Masanori Yamazaki2
FATIGUE PROPERTIES OF FERRITIC/MARTENSITIC STEEL AFTER NEUTRON IRRADIATION AND HELIUM IMPLANTATION
40a
307 Pengcheng Zhu1*, Shradha Agarwal1, Yajie Zhao1, Steven J.Zinkle1,2
EXAMINATION OF HARDENING IN ION IRRADIATED Fe14Cr ALLOY BY SPHERICAL AND BERKOVICH NANOINDENTATION
40b
308 Yuguang Chen1, Chonghong Zhang1*, Zhaonan Ding1, Xianlong Zhang1, Yitao Yang1, Yin Song1, Akihiko Kimura2
Hardening/embrittlement of An Al-added 16Cr ODS Ferritic Steel Irradiated with High-energy Heavy Ions 41a
70
No. Author Abstract Title Poster Address
309 Wahyu Setyawan1*, Charles H. Henager Jr.1 AB INITIO STUDY OF HELIUM EFFECTS AND HYDROGEN RETENTION ON W/NI-FE COMPOSITE INTERPHASE BOUNDARIES
41b
310 Y.Q. Wang1*, D. Chen2, N. Li1, D. Yuryev3, K. Baldwin1, and M.J. Demkowicz4
CONFINEMENT OF HE PRECIPITATES GROWTH WITHIN METAL NANO-LAYERS AND IMPLICATIONS TO RADIATION DAMAGE
42a
311 A. Scott 1 , M. Balooch 1 , M. Ambat 1 , M. Popovic 1 , P. Hosemann 12
Microstructural Evolution of Helium Bubbles in Metals Using Nanoscale Implantation 42b
312 S. Karpov1, V. Voyevodin1, G. Tolstolutskaya1, I. Kopanets1, V. Ruzhytskiy1 and F. Garner2,3
RADIATION DEFECTS EFFICIENCY WITH RESPECT TO HYDROGEN TRAPPING IN AUSTENITIC STAINLESS STEELS
43a
313 Tianyao Wang1*, Zach Levin2, Hyosim Kim1, Karl T.Hartwig2 F.A. Garner1, Lin Shao1
GAS BUBBLE SUPERLATTICE FORMATION IN HELIUM-IMPLANTED TUNGSTEN: A STUDY ON HELIUM RETENTION AND SUPERLATTICE DEPENDENCE ON TEMPERATURE, DOSE AND GRAIN BOUNDARIES
43b
314 Kazuhito Ohsawa1*, Takeshi Toyama2, Yuji Hatano3, Masatake Yamaguchi4, Hideo Watanabe1
Interaction of divacancy with hydrogen in tungsten and stability induced by interstitial atoms 44a
315 Takuya Yamamoto1*, Daniel J. Edwards2, Karen Kruska2, Richard J. Kurtz2, Yutai Katoh3 andG. Robert Odette1
STATUS OF THE DESIGN AND SPECIMEN MATRICES FOR IN SITUHE INJECTION RE-IRRADIATIONS IN A HFIR RABBIT CAPSULE AND NEUTRON-ION BOOTSTRAPPING EXPERIMENTS
44b
316 D.V. Bachurin1*, P.V. Vladimirov1 AB INITIO STUDY OF HYDROGEN DIFFUSION IN TITANIUM BERYLLIDE 45a
317 N. Hashimoto*1, D. Hamaguchi2, and H. Tanigawa2
Direct observation of H and He effect on cavity formation in alpha-iron under irradiation 45b
318 Michael Klimenkov*, Ute Jäntsch, Jan Hoffmann, Pavel Vladimirov and Anton Möslang
Radiation induced formation gas bubbles in beryllium after neutron irradiation up to 6000 appm helium production 46a
319 Pietro Alessandro Di Maio1*, Fabio Cismondi2, Alessandro Del Nevo3, Ruggero Forte1, Nasr Ghoniem4, Yue Huang4
Multi-physics/multi-scale approach for breeding blanket design optimization 46b
320 Xuebang Wu 1*, X. Zhang 1, Z.M. Xie 1, Xiangyan Li 1, C.R. Miranda 2, and C.S. Liu 1*
First principles prediction of stability and light elements trapping of interfaces between tungsten and transition metal carbides
47a
71
No. Author Abstract Title Poster Address
321
Jan S. Wróbel1*, Marcin R. Zemła1, Marek Muzyk1,2, Duc Nguyen-Manh3, Sergei L. Dudarev3, Pär Olsson4, Luca Messina4, Christophe Domain5
FLUCTUATING PROPERTIES OF POINT DEFECTS IN CONCENTRATED FE-CR ALLOYS 47b
322 Roger Stoller1*, Yuri Osetsky1 and Alexander Barashev2
THE ROLE OF OVERPRESSURIZED HELIUM BUBBLES IN IRON IN MICROSTRUCTURE EVOLUTION UNDER IRRADIATION
48a
323 Sergey Pestchanyi1*, Francesco Maviglia2 SIMULATION OF THE FIRST WALL SHIELDING DURING UPWARD VDE IN DEMO 48b
324 Min Pan1, Zelin Cao2, Yini Lv2, Shulong Wen1, Zheng Huang2*, Yong Zhao1
EFFECT OF Ti ON PRECIPITATION PROPERTY OF TRANSMUTATION ELEMENTS IN W-Ti ALLOY FROM FIRST – PRINCIPLES CALCULATIONS
49a
325 David Cereceda1, Sicong He2, Vasily Bulatov3, Jaime Marian2,4
Understanding the plastic behavior of tungsten from first principles to crystal plasticity and its implications as a fusion material
49b
326 Jingyi Shi1*, Lei Peng2, Liuliu Li2, Fei Gao3, Jianjun Huang1, Jiangang Li1, 4
Molecular Dynamics Study on Effects of GB Characteristics on Helium Embrittlment 50a
327 Mitchell A. Wood, Mary Alice Cusentino*, and Aidan P. Thompson
Machine Learned Interatomic Potentials for Modeling Plasma Material Interactions 50b
328 Nithin Mathew*, Danny Perez, Enrique Martinez Diffusion of H, He, and self-interstitial atoms along dislocation cores in Tungsten 51a
329 Elena V. Rosa Adame1*, Patrick Bunting1, Mutaz Bashir1, Mike Fursdon1, Mike Gorley1
Implementation of multiaxial fatigue criterion based on Lagoda-Macha-Sakane Method for DEMO Design Criteria for In-Vessel Components (DDC-IC). Phase 1: Process definition from FE modelling to validation testing
51b
330 Giacomo Po1,2*, Yue Huang2, Nasr Ghoniem2 A MODEL OF 3D DISLOCATION CLIMB AND ANNEALING IN IRRADIATED MATERIALS 52a
331 Arian Ghazari1*, Giacomo Po1,2, Andrew Sheng1, Nasr Ghoniem1
A 3D DISLOCATION MODEL OF PLASTICITY AND FRACTURE IN IRRADIATED TUNGSTEN 52b
332 Michael Mahler1*, Giacomo Po2, Yinan Cui3, Nasr Ghoniem3, Jarir Aktaa1
Dislocation Dynamics simulation of irradiation induced hardening in ferritic-martensitic steel 53a
333 Juan P. Balbuena1*, Lorenzo Malerba2, Nicolas Castin3, Giovanni Bonny3, Maria J. Caturla1
Segregation and precipitation in Cell-OKMC simulations of iron alloys 53b
334 Haixuan Xu1 Comparative Study of Dislocation Bias in W and Fe using SEAKMC 54a
72
No. Author Abstract Title Poster Address
335 Yinan Cui1*, Giacomo Po1, Yue Huang1, Nasr Ghoniem1
Revealing Irradiation Creep Mechanisms in Nanostructured Materials Through Coupled Diffusion-Dislocation-Dynamics Simulations
54b
336 Hsing-Yin Chang1*, Dylan Dickstein2, Nasr Ghoniem2, Jaime Marian1,2
Computational Modeling of Secondary Electron Emission in Microarchitected Surfaces for Designing Plasma-resilient Devices
55a
337 Jacob B. J. Chapman1*, Pui-Wai Ma1, Sergei L. Dudarev1
The High-Temperature Dynamics of Magnetism in Irradiated FeCr Alloys 55b
338 Christian Hill1*, Kalle Heinola1, Andrea Sand2, Sergei Dudarev3, Wahyu Setyawan4
CASCADESDB: AN OPEN DATABASE OF COLLISION CASCADE SIMULATIONS FOR FUSION MATERIALS
56a
73
Hotel Layout
74
Grand Foyer Located adjacent to Aventine Ballroom and the Asteria Terrace, the 3,689 sq. ft. Ballroom Foyer is perfect for pre‐function gatherings, breaks and poster sessions.
75
Aventine Ballroom
This space offers a central location near the Asteria Terrace and Main Lobby. This is where oral presentations will be given.
76
Asteria Terrace
Located between the Aventine Ballroom and Vicino Ballroom, Asteria Terrace
77
78
79
The IEA Tungsten Workshop Palatine Room: 5-7 PM on Monday, October 28, 2019
The IEA Vanadium Workshop Palatine Room: 1-2:30 PM on Tuesday, October 29, 2019
The IEA SiC Workshop Portofino Room: 1-2:30 PM on Tuesday, October 29, 2019
Satellite Meetings
80
The US-Japan Frontier Meeting Palatine Room: 5-7 PM on Tuesday, October 29, 2019
The IEA RAFM Steels Workshop Palatine Room: 1:00-2:30 PM on Wednesday, October 30, 2019
The ARC Meeting Palatine Room: 5-7 PM on Wednesday, October 30, 2019
The IAC Lunch Meeting Portofino Room: 12:30-2:30 PM on Thursday, October 31, 2019
The IAE Executive Committee Meeting Palatine Room: 2:30-5:30 PM on Thursday, October 31, 2019
81
The following technical tours are planned for Friday, November 1,
immediately after lunch. Buses will pick up guests from the hotel
entrance. The tours are as follows:
(1) The experimental facility of D-III at General Atomics.
(2) The plasma-materials interaction experimental facility of PISCES at the University of
California, San Diego (UCSD).
Each tour is limited to 30 guests on a first enroll basis. Enrollment is
open through the conference website.
Technical Tours
82
General Atomics is a defense and diversified technologies company, founded in 1955 as a Division of General Dynamics and acquired by the Blue family in 1986. GA and affiliated companies operate on five continents and include GA Aeronautical Systems, Inc. (GA-ASI). GA is the principal private sector participant in thermonuclear fusion research through its internationally recognized DIII-D and inertial confinement programs for the US Department of Energy. GA developed the UCSD Supercomputer Center and has constructed more than 60 TRIGA nuclear research reactors in 24 countries. GA is a leader in development of next-generation nuclear fission and high-temperature materials technologies.
Ultramet, a California corporation, develops advanced materials solutions for government and commercial markets driven by extreme environments and high performance. Ultramet specializes in the chemical vapor deposition of refractory metals, platinum group metals, and ceramics in the form of coatings, freestanding shapes, composites, and porous materials. Ultramet devises the methods to produce the desired components and then manufactures or licenses said components with a commitment to reproducibility. Our company serves the aerospace, medical, chemical, semiconductor, nuclear, and oil and gas industries.
Sponsors & Partners
83
MIT’s Plasma Science & Fusion Center (PSFC) is a multi-disciplinary research laboratory on the MIT campus, affiliated with several academic departments, including Nuclear Science & Engineering, Physics, Mechanical Engineering, Aeronautics and Astronautics and Electrical Engineering. With more than 200 affiliated faculty members, students researchers and technicians, substantial technical infrastructure and 250,000 square feet of laboratory, shop and office space, the PSFC is the largest and most capable university-based fusion lab in the world. The Center was formed in the 1970s as a collaboration between engineers from the National Magnet Laboratory and fusion physicists, who recognized the advantages of high-field magnet engineering for fusion. We have built the three highest field fusion experiments in the world, which have set a number of plasma performance records, validating the high-field pathway. SPARC will be the fourth.