He-Cooled Divertor for DEMO: Technological Study on Joining Tungsten Components with Titanium Interlayer (Englisch)
- Neue Suche nach: Norajitra, P.
- Neue Suche nach: Basuki, W.W.
- Neue Suche nach: Spatafora, L.
- Neue Suche nach: Stegmaier, U.
- Neue Suche nach: Norajitra, P.
- Neue Suche nach: Basuki, W.W.
- Neue Suche nach: Spatafora, L.
- Neue Suche nach: Stegmaier, U.
In:
FUSION SCIENCE AND TECHNOLOGY
;
66
, 1
;
266-271
;
2014
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ISSN:
- Aufsatz (Zeitschrift) / Print
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Titel:He-Cooled Divertor for DEMO: Technological Study on Joining Tungsten Components with Titanium Interlayer
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Beteiligte:Norajitra, P. ( Autor:in ) / Basuki, W.W. ( Autor:in ) / Spatafora, L. ( Autor:in ) / Stegmaier, U. ( Autor:in )
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Erschienen in:FUSION SCIENCE AND TECHNOLOGY ; 66, 1 ; 266-271
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Verlag:
- Neue Suche nach: AMERICAN NUCLEAR SOCIETY, INC.
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Erscheinungsdatum:01.01.2014
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Format / Umfang:6 pages
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ISSN:
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Medientyp:Aufsatz (Zeitschrift)
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Format:Print
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Sprache:Englisch
- Neue Suche nach: 621.484
- Weitere Informationen zu Dewey Decimal Classification
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Klassifikation:
DDC: 621.484 -
Datenquelle:
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Inhaltsverzeichnis – Band 66, Ausgabe 1
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Die Inhaltsverzeichnisse werden automatisch erzeugt und basieren auf den im Index des TIB-Portals verfügbaren Einzelnachweisen der enthaltenen Beiträge. Die Anzeige der Inhaltsverzeichnisse kann daher unvollständig oder lückenhaft sein.
- 1
-
DEMO Activities in the Broader Approach and BeyondNishitani, Takeo et al. | 2014
- 9
-
Comparative Assessment of Material Performance in DEMO Fusion ReactorsGilbert, M R et al. | 2014
- 18
-
Structural Design Criteria Development Needs for a European DEMOPorton, M et al. | 2014
- 28
-
Current Status of Beryllium Materials for Fusion Blanket ApplicationsVladimirov, Pavel et al. | 2014
- 38
-
Overview of the Structural Materials Program for Fusion Reactors Under EFDAGonzalez De Vicente, Sehila M et al. | 2014
- 46
-
Engineering Validation and Engineering Design of Lithium Target Facility in IFMIF/EVEDA ProjectWakai, E et al. | 2014
- 57
-
Irradiation Response of Next Generation High Temperature Superconductors for Fusion Energy ApplicationsLeonard, Keith J et al. | 2014
- 63
-
Laboratory Experiments and Modeling on Bi-Directional Hydrogen Isotopes Permeation Through the First Wall of a Magnetic Fusion DEMO ReactorHirooka, Yoshi et al. | 2014
- 70
-
Plasma-Facing Material Erosion Products Formed Under ITER-Like Transient Loads at QSPA-T Plasma Gun FacilityPutrik, A B et al. | 2014
- 77
-
Validation of Ultrasonic Velocity Measurements for Detecting Void Swelling in First-Wall Structural MaterialsOkita, T et al. | 2014
- 83
-
Thermal Discrete Element Analysis of EU Solid Breeder Blanket Subjected to Neutron IrradiationGan, Yixiang et al. | 2014
- 91
-
MD Simulation of Atomic Displacement Cascades in Random Fe-9at.%Cr Binary Alloy with Twin Grain BoundariesTikhonchev, Mikhail et al. | 2014
- 100
-
Effect of Thermal Loadson Different Modulesof DEMO PFCsIgitkhanov, Yu et al. | 2014
- 106
-
Effect of Hydrogen in a Vanadium Grain Boundary by First PrinciplesZhang, Pengbo et al. | 2014
- 112
-
Molecular Dynamics Simulation of the Displacement Cascades in Tungsten with Interstitial Helium AtomsYang, Xiaodan et al. | 2014
- 118
-
Plasma-Facing Materials Erosion Under ITER-Like Transient Loads at QSPA Plasma Gun FacilityKlimov, N S et al. | 2014
- 125
-
Nondestructive Testing of EAST W/Cu Divertor ComponentsWang, Wanjing et al. | 2014
- 131
-
Creep-Fatigue Interaction in Eurofer 3 Electron Beam WeldsCommin, Lorelei et al. | 2014
- 136
-
Size-Dependent Crush Analysis of Lithium Orthosilicate PebblesAnnabattula, R K et al. | 2014
- 142
-
Thermal-Structural Analysis of Water-Cooled Plasma-Facing Mockups with Diamond/Copper Composite InterlayerLi, Peng et al. | 2014
- 150
-
Specific Features of Mechanism for Dust Production from Tungsten Armor Under Action of ELMsPestchanyi, S et al. | 2014
- 157
-
Development of Advanced Neutron Multipliers for DEMO BlanketsNakamichi, M et al. | 2014
- 163
-
Thermo-Mechanical Analysis of W/Cu-Alloy Joints for Plasma-Facing Components Under Various ConditionsHao, X N et al. | 2014
- 171
-
Study of Beryllium Damage Under ITER-Relevant Transient Plasma and Radiative LoadsKupriyanov, Igor et al. | 2014
- 180
-
Fabrication Technique Development of Dual Functional Lithium Lead Test Blanket ModuleLi, Chunjing et al. | 2014
- 187
-
Effect of ITER ELM Conductor Manufacturing Process on the Properties of the Inconel 625 JacketJin, H et al. | 2014
- 192
-
Development of Laser Welding Process for Reduced Activation Ferritic Martensitic Steel for Indian Test Blanket ModuleKumar, Hemant et al. | 2014
- 200
-
Strength Evaluation of a Single Layer Passed TIG Weld Joint in Advanced Reduced Activation Alloy by Small Punch Test for HCCR TBM in ITERShin, Kyu In et al. | 2014
- 208
-
Nb3Sn Strand Verification for ITER TF Conductors of CNDALiu, F et al. | 2014
- 214
-
Honeycomb Palladium Catalyst for the Oxidation of Tritiated Hydrocarbons Produced in Tritium FacilitiesIwai, Yasunori et al. | 2014
- 221
-
Formation of Double Oxide Insulator Coating foran Advanced Breeding BlanketHishinuma, V et al. | 2014
- 228
-
Neutronic Analysis of the IFMIF Tritium Release Test Module Based on the EVEDA DesignKondo, Keitaro et al. | 2014
- 235
-
Evolution of Defects and Defect Clusters in beta -SiC Irradiated at High TemperatureXi, J. / Zhang, P. / He, C. / Zheng, M. / Zang, H. / Guo, D. / Ma, L. et al. | 2014
- 235
-
Evolution of Defects and Defect Clusters in β-SiC Irradiated at High TemperatureXi, Jianqi et al. | 2014
- 245
-
Overview of Material Challenges in IFMIF Test Cell DesignTian, Kuo et al. | 2014
- 252
-
A Stepped Approach from IFMIF/EVEDA Toward IFMIFIbarra, A et al. | 2014
- 260
-
Design and Preparation of Water-Cooled Plasma-Facing Mockups with Diamond/Copper Composite InterlayerShen, Weiping et al. | 2014
- 266
-
He-Cooled Divertor for DEMO: Technological Study on Joining Tungsten Components with Titanium InterlayerNorajitra, P et al. | 2014
- 272
-
Transmutation of Tungsten in Fusion and Fission Nuclear EnvironmentsSawari, M E et al. | 2014
- 278
-
Fabrication and Helium Irradiation of Potassium-Doped TungstenShu, Xiaoyan et al. | 2014
- 283
-
Interaction of Dislocations with Carbides in BCC Fe Studied by Molecular DynamicsGranberg, F et al. | 2014
- 289
-
Effect of the Stacking Fault Energy on Interactions Between an Edge Dislocation and a Spherical Void in FCC Metals at Various Spatial GeometriesOkita, T et al. | 2014
- 295
-
INDEXES - Volume 66, Number 1 Author Index| 2014
-
Volume 66, Number 1 Subject Index| 2014
-
Proceedings of the - SIXTEENTH INTERNATIONAL CONFERENCE ON FUSION REACTOR MATERIALS (ICFRM-16) - Part A: Fusion Technology October 20-26, 2013, Beijing, China - PrefaceZhou, Zhangjian et al. | 2014