Related references
Note: Only part of the references are listed.The EUROfusion materials property handbook for DEMO in-vessel components-Status and the challenge to improve confidence level for engineering data
Michael Gorley et al.
FUSION ENGINEERING AND DESIGN (2020)
A route to standardised high heat flux testing: An example for tungsten
Frank Schoofs et al.
FUSION ENGINEERING AND DESIGN (2019)
European materials development: Results and perspective
Gerald Pintsuk et al.
FUSION ENGINEERING AND DESIGN (2019)
Development of self passivating W-Eurofer brazed joints
J. de Prado et al.
FUSION ENGINEERING AND DESIGN (2019)
An overview of the EU breeding blanket design strategy as an integral part of the DEMO design effort
G. Federici et al.
FUSION ENGINEERING AND DESIGN (2019)
Development of the material property handbook and database of CuCrZr
Kuo Zhang et al.
FUSION ENGINEERING AND DESIGN (2019)
Fabrication of thin-walled fusion blanket components like flow channel inserts by selective laser melting
C. Koehly et al.
FUSION ENGINEERING AND DESIGN (2019)
Towards reliable design-by-analysis for divertor plasma facing components - Guidelines for inelastic assessment (part 1: Unirradiated)
M. Fursdon et al.
FUSION ENGINEERING AND DESIGN (2019)
On the history and status of reactor pressure vessel steel ductile to brittle transition temperature shift prediction models
G. R. Odette et al.
JOURNAL OF NUCLEAR MATERIALS (2019)
Tritium retention in W plasma-facing materials: Impact of the material structure and helium irradiation
E. Bernard et al.
NUCLEAR MATERIALS AND ENERGY (2019)
The European ITER Test Blanket Modules: Fabrication R&D progress for HCLL and HCPB
Laurent Forest et al.
FUSION ENGINEERING AND DESIGN (2018)
Development of EUROFER97 database and material property handbook
Ermile Gaganidze et al.
FUSION ENGINEERING AND DESIGN (2018)
The IFMIF-DONES project: preliminary engineering design
A. Ibarra et al.
NUCLEAR FUSION (2018)
European divertor target concepts for DEMO: Design rationales and high heat flux performance
J. H. You et al.
NUCLEAR MATERIALS AND ENERGY (2018)
Improvement of EUROFER's mechanical properties by optimized chemical compositions and thermo-mechanical treatments
J. Hoffmann et al.
NUCLEAR MATERIALS AND ENERGY (2018)
Melt infiltrated tungsten-copper composites as advanced heat sink materials for plasma facing components of future nuclear fusion devices
A. Von Mueller et al.
FUSION ENGINEERING AND DESIGN (2017)
WCLL breeding blanket design and integration for DEMO 2015: status and perspectives
A. Del Nevo et al.
FUSION ENGINEERING AND DESIGN (2017)
ITER-like divertor target for DEMO: Design study and fabrication test
F. Crescenzi et al.
FUSION ENGINEERING AND DESIGN (2017)
Self-passivating W-Cr-Y alloys: Characterization and testing
Aida Calvo et al.
FUSION ENGINEERING AND DESIGN (2017)
Ductilisation of tungsten (W): Tungsten laminated composites
Jens Reiser et al.
INTERNATIONAL JOURNAL OF REFRACTORY METALS & HARD MATERIALS (2017)
Materials testing facilities and programmes for fission and ion implantation damage
S. M. Gonzalez de Vicente et al.
NUCLEAR FUSION (2017)
Materials-related issues in the safety and licensing of nuclear fusion facilities
N. Taylor et al.
NUCLEAR FUSION (2017)
Development of advanced high heat flux and plasma-facing materials
Ch. Linsmeier et al.
NUCLEAR FUSION (2017)
Towards a programme of testing and qualification for structural and plasma-facing materials in 'fusion neutron' environments
D. Stork et al.
NUCLEAR FUSION (2017)
Development of benchmark reduced activation ferritic/martensitic steels for fusion energy applications
H. Tanigawa et al.
NUCLEAR FUSION (2017)
European DEMO design strategy and consequences for materials
G. Federici et al.
NUCLEAR FUSION (2017)
Functional materials for tokamak in-vessel systems-status and developments
S. M. Gonzalez de Vicente et al.
NUCLEAR FUSION (2017)
Development of next generation tempered and ODS reduced activation ferritic/martensitic steels for fusion energy applications
S. J. Zinkle et al.
NUCLEAR FUSION (2017)
Overview of the JET ITER-like wall divertor
A. Widdowson et al.
NUCLEAR MATERIALS AND ENERGY (2017)
Conceptual design studies for the European DEMO divertor: Rationale and first results
J. H. You et al.
FUSION ENGINEERING AND DESIGN (2016)
European DEMO divertor target: Operational requirements and material-design interface
J. H. You et al.
NUCLEAR MATERIALS AND ENERGY (2016)
In search of technology readiness level (TRL) 10
Jeremy Straub
AEROSPACE SCIENCE AND TECHNOLOGY (2015)
Mechanical and microstructural investigations of tungsten and doped tungsten materials produced via powder injection molding
Steffen Antusch et al.
NUCLEAR MATERIALS AND ENERGY (2015)
Damage and fatigue crack growth of Eurofer steel first wall mock-up under cyclic heat flux loads. Part 2: Finite element analysis of damage evolution
Jeong-Ha You
FUSION ENGINEERING AND DESIGN (2014)
Damage and fatigue crack growth of Eurofer steel first wall mock-up under cyclic heat flux loads. Part 1: Electron beam irradiation tests
J. H. You et al.
FUSION ENGINEERING AND DESIGN (2014)
Materials R&D for a timely DEMO: Key findings and recommendations of the EU Roadmap Materials Assessment Group
Derek Stork et al.
FUSION ENGINEERING AND DESIGN (2014)
Two component tungsten powder injection molding - An effective mass production process
Steffen Antusch et al.
JOURNAL OF NUCLEAR MATERIALS (2014)
Developing structural, high-heat flux and plasma facing materials for a near-term DEMO fusion power plant: The EU assessment
D. Stork et al.
JOURNAL OF NUCLEAR MATERIALS (2014)
Evaluation of irradiation facility options for fusion materials research and development
Steven J. Zinkle et al.
FUSION ENGINEERING AND DESIGN (2013)
Neutron irradiation of modern KU-1 and KS-4V fused silica
I. I. Orlovskiy et al.
JOURNAL OF NUCLEAR MATERIALS (2013)
Recent progress of R&D activities on reduced activation ferritic/martensitic steels
Q. Huang et al.
JOURNAL OF NUCLEAR MATERIALS (2013)
Recent progress in research on tungsten materials for nuclear fusion applications in Europe
M. Rieth et al.
JOURNAL OF NUCLEAR MATERIALS (2013)
ITER safety and licensing update
Neill Taylor et al.
FUSION ENGINEERING AND DESIGN (2012)
Review of candidate welding processes of RAFM steels for ITER test blanket modules and DEMO
P. Aubert et al.
JOURNAL OF NUCLEAR MATERIALS (2011)
Mockups of blanket cooling plates manufactured in different diffusion welding setups
A. von der Weth et al.
JOURNAL OF NUCLEAR MATERIALS (2009)
Tensile and fracture toughness properties of neutron-irradiated CuCrZr
Meimei Li et al.
JOURNAL OF NUCLEAR MATERIALS (2009)
Conceptual design of a component test facility based on the spherical tokamak
G. M. Voss et al.
FUSION ENGINEERING AND DESIGN (2008)
A component test facility based on the spherical tokamak
YKM Peng et al.
PLASMA PHYSICS AND CONTROLLED FUSION (2005)
Share Paper
